[{"run_id":"20260906T231458-5fdd2fff","semester":"1272","observed_at":"2026-09-06 23:14:58.172943+00:00","record_version_id":"b907202e33f646ca3e9ac7207fca64be03480223c48730ab4ed0cd24a5308317","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"20260907T155543-ce3781c4","semester":"1272","observed_at":"2026-09-07 15:55:43.033547+00:00","record_version_id":"b907202e33f646ca3e9ac7207fca64be03480223c48730ab4ed0cd24a5308317","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-03b0bbb9723907cf3d1b41cf0bb34837dc398e42","semester":"1262","observed_at":"2025-04-16 05:20:33.104844+00:00","record_version_id":"1809422b4187ce7dee0bb7074bd24bd325efd617e86d1ba8a2dfc6aaf53b202d","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-0837245627eb714ae6bb0375f7abe8f41042011f","semester":"1262","observed_at":"2025-04-16 05:20:33.104844+00:00","record_version_id":"1809422b4187ce7dee0bb7074bd24bd325efd617e86d1ba8a2dfc6aaf53b202d","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-08c92e359bbbc110b0778b7e0b15d6f40000e6b1","semester":"1262","observed_at":"2025-08-21 07:05:14.730696+00:00","record_version_id":"20f52382f64300c364e15d6d14358eb198af80d692a6f90378a928c048828652","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-0944d76440dc778fbb89626058c10451009ce9c6","semester":"1262","observed_at":"2025-05-21 03:36:18.194118+00:00","record_version_id":"7e58f79b72c96dbd60d91cb9d3b9856e2e9d093e3203fc1623d2e0ab665b7560","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-0a7f4bce29c816ef4d3d71b4eb8a2a3e15e33cc1","semester":"1262","observed_at":"2025-06-18 20:04:02.695444+00:00","record_version_id":"3cee50ef61c342bb54f0ace3cb842ae72abee4f55e6c4c4e3fdc07fcd038a202","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-0ab917f827a7de22ebdc1087114d377a31c4687b","semester":"1262","observed_at":"2025-05-22 02:11:02.531191+00:00","record_version_id":"763656cb958712cd41acbf318af54aa6e008eee3b21c4bdee5f791436463e871","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-0c40ecab4b6db9333d1f18aef816e3ee659e300c","semester":"1262","observed_at":"2025-05-25 18:02:34.797617+00:00","record_version_id":"33a8d8bf4c66f187e07aa8f83bddffb2e60caac87cfb7a8570def3d7a9f1ece3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-0cb4d29a588ec7f11c7e00b7cf5dc3a0d23d0349","semester":"1266","observed_at":"2026-01-22 01:00:26.555427+00:00","record_version_id":"896a1d1efd21c9c37111698ff588f6cdc7f66fd57d5df0115c1d4128579446b3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-11c30ec39e91498cbfcf3a923c53a4b03e387280","semester":"1262","observed_at":"2025-07-20 04:58:26.847117+00:00","record_version_id":"0417ba5acfeee5501b92640474f1aec8b7795ce152bf14dbc4d655822122c56d","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-13cd500edf2587e9a3428f326253738fbea965ea","semester":"1264","observed_at":"2025-12-14 04:50:04.653658+00:00","record_version_id":"a36afda76a22125872162e3adce3319c7f2ec3b8ed5910d1ca303af9f4e398ab","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-1da08b2de39f05e6bc877c189fc2fd6eeda563f5","semester":"1262","observed_at":"2025-07-01 00:03:56.707251+00:00","record_version_id":"11c0fc0c2297c145d65ace9681339e25d6784adf6131083e08071ae486867a5d","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-2031af47efe133b0e7877f433286ff07385afc41","semester":"1262","observed_at":"2025-07-02 20:16:45.749584+00:00","record_version_id":"8b3f513c8b81487428dd3827480f0e62b36d3e04e7388ad4cd3297b2b7c449c5","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-238eba6f32fbc30407f616dd0628ff02a2a824dd","semester":"1262","observed_at":"2025-08-17 05:15:07.788352+00:00","record_version_id":"1fb6e01cbe317d9d3215a9fe7bc817cdbb3c79e4a619639fa3aae737bf3c04d1","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-25f0ff56bc4d80f8a8afa1a0bcce8dae6fddb5e5","semester":"1262","observed_at":"2025-05-25 17:20:25.942090+00:00","record_version_id":"6d1f0a737d013e8de826418cfc3051accf7c785a612f9186ddd82ecccda0be72","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-2923f91826ce253b7aeefa9f75b4a39fe4c80ff0","semester":"1262","observed_at":"2025-08-10 05:10:25.938416+00:00","record_version_id":"7e9d4815d718b8a03c2918af8c93f72b15d6a13204d7a8e47ccbc4df63558ae0","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-2a05214a4023e0157fa6f7d188c85308f714176c","semester":"1262","observed_at":"2025-09-07 04:56:38.255315+00:00","record_version_id":"b02d68f0663ebcb8eb6e63554ab2f93d20e971d43285ecc133bc607b26f26323","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-2b1b8e39131de92b94620b25c5bbb25690efed4c","semester":"1262","observed_at":"2025-06-01 07:54:53.913454+00:00","record_version_id":"d4fc401ff7219f5f7d497899d7f549c8254cfa61947f5767e63c5c452c1409b3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-33a1225644e5a5855d60f66e65413946e72fedf4","semester":"1262","observed_at":"2025-06-22 01:52:05.152650+00:00","record_version_id":"1767878bc6084baf312d13dbe0e9491066d9e98c466abb2178116ce13aeedaf4","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-3b89c83dbf5208e13756184de1f2b2d0c09af35f","semester":"1262","observed_at":"2025-06-30 06:40:10.235522+00:00","record_version_id":"4de4d14ebdb585a498a96b9353db60d44292bdbabce29ae4275f3ca6cb12e096","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-3c3eebf7f35c39364b445a2fa5a112ce28dbb4a1","semester":"1262","observed_at":"2025-06-01 17:03:59.062985+00:00","record_version_id":"668e4388af0316f827b78618eee01f67f2039668b465e8aea49304cd18dbc5ab","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-3fa4dd71391f1c9cf4ab2216680bbc428689f92d","semester":"1262","observed_at":"2025-05-25 01:15:58.180530+00:00","record_version_id":"166154850d06a5896fe2b6884c131f76863568f90befc608a3d4c64958eb4f10","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-4040aa216da722a34483f68fc1e129ea571ae08d","semester":"1262","observed_at":"2025-06-01 07:27:39.695506+00:00","record_version_id":"6304ef6a4fdeab36920facdd7d2c9ab99247002e804407c23da810e203d410ad","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-454d53cd690294459f8ad0793cc3ed562060e56c","semester":"1262","observed_at":"2025-05-25 01:34:00.536004+00:00","record_version_id":"c64b5c6e2a3817c374f2ed268f61709ea51e219a27d78b2534a4a168a7e9c6e3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-486f091e051fdb4ccdb80ee7b4fb0a5814510324","semester":"1264","observed_at":"2025-11-16 05:32:31.273726+00:00","record_version_id":"bcb9e51c662f343ee867a1506860c14dd7125f7b3470fd6deb0fd3de5bb4c3a5","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-50393cfc5fd5598d4f4731ef1919f2ff53af07d9","semester":"1262","observed_at":"2025-06-30 06:05:57.438846+00:00","record_version_id":"2f210322a7e5a57286a1c2e3047d3fa44a345d413c56969a1e51456c6a86c546","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-50f6947786b208c800db8bbd0cec84a8f0f187d2","semester":"1262","observed_at":"2025-06-02 03:49:42.915428+00:00","record_version_id":"be9a0a05e5d997107b7e93db3e2bd97e5ca4c3de970fd5853f2f0fa73a1a646c","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-51d86ed4082dced3803c295419b0ec8440942016","semester":"1264","observed_at":"2025-11-12 04:50:41.141307+00:00","record_version_id":"1df98135f63d4be0639351871d75bf0c73a6255894f0f13a68806da0db5c96ce","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-53101bd1c10db0d00d094e4c9154d4c244ff23d9","semester":"1262","observed_at":"2025-10-05 04:58:05.366968+00:00","record_version_id":"2c74a13a471df4cf5da8a01e3ab8dcb18a40a21aad9e672dad3804e64a9067cf","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-58751151c564e11c5cb8aedd3a2d3527c22f73eb","semester":"1262","observed_at":"2025-06-01 06:59:01.536576+00:00","record_version_id":"31d67d0b8d0190b8b5fb5be081a9f5280fadda3b84ed7a5bfe159207d4e7911e","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-5c4c8d3701a333ba4ddadef7d0b5dde8440fcdf0","semester":"1262","observed_at":"2025-06-01 01:57:51.256704+00:00","record_version_id":"ca962650e710c0aef9a689fb97321c2825ead516eec9a18a0bc9d751c657aad1","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-5d20d9f81651d3c83fcaa2fd10870ce6e5d5a685","semester":"1262","observed_at":"2025-05-21 16:48:48.484741+00:00","record_version_id":"42d808e06e6bc680130c9dae84a827d6d8a5b9e03c41602037c633ddf4f678e3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-5feaebf2ab37051c86ad360cc0fa0d7e0e2ea295","semester":"1262","observed_at":"2025-05-24 15:58:23.378859+00:00","record_version_id":"adc66af3c57e404361d7d7ae04d279c998c1a6ad86f11bbe688968f1400b69d0","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-60949965544fce098cc006354e201149005fb77b","semester":"1264","observed_at":"2025-10-26 05:07:14.077864+00:00","record_version_id":"f6a72034a62eb6cc29d11c32a698ea5344f4dfbd13ddceaf68107943a7e2f3f8","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-639225ac3addf8522f1d30cb4fe26054ea7f8c49","semester":"1262","observed_at":"2025-06-01 08:14:42.497608+00:00","record_version_id":"ca962650e710c0aef9a689fb97321c2825ead516eec9a18a0bc9d751c657aad1","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-64093b17b3a9c67a41aa33eb37adb53ec38df714","semester":"1262","observed_at":"2025-05-22 02:11:02.531191+00:00","record_version_id":"4faa151ed649d8b87a2134e3649dc3063c96cb8717368dc0dfc37f5a81420a6b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-6885b56099f55e08aa0205546369fb0381d50e13","semester":"1262","observed_at":"2025-07-13 04:59:22.367394+00:00","record_version_id":"18677d02c78616ea8edb07d07319f7c21a8579b6bafda9ebc94bb5fddfa36975","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-69d4b2b16e8268f75b6390b3a0e2ce8bf73999da","semester":"1262","observed_at":"2025-06-30 03:21:29.925498+00:00","record_version_id":"a2294bb0f4903b4504db685f9847fa59fe903139df94cf39f0f9e32a23e60ace","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-6b29c3e0673b2f9a736d2363db5409e03d5b3ed4","semester":"1264","observed_at":"2025-12-03 12:33:41.418072+00:00","record_version_id":"de0edc5dba0d9c1df9ecdb79f40486113f70fa6da45eced9267fc1a468cf78d9","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-73259984748de484976ef2ad56ad7ab3d4cb4518","semester":"1262","observed_at":"2025-06-26 08:27:56.461216+00:00","record_version_id":"ca4d546691f75553c70db5693e25bf444eb1535d25d9e60f4d9492570da866cc","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-741602fbc6252c232a0b9e6bc1a9ae3101625f5a","semester":"1262","observed_at":"2025-06-30 22:49:32.522034+00:00","record_version_id":"b7a5bc1cc5f313db96e7131ebe4c143b872e464138fcfaa284635d725758dd6a","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-7774f45558276ec29bf626e58fffb4a27bdbb2a9","semester":"1264","observed_at":"2025-11-01 11:49:36.359151+00:00","record_version_id":"b43f60768d9dc2b42a1acaebd124add59911e734cdd045e8295ffc44a3622bdb","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-7ab7c5e783fc8ebef8b8ee8cea019ee37a72ce74","semester":"1262","observed_at":"2025-09-28 04:58:07.340658+00:00","record_version_id":"cd80480be5577685ec67cb3652a4aceabd6aceda820c6bba2d9a04e708eb8bd0","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-7b2f22d83ea05055ab90dcb77dc802382cccc6f7","semester":"1262","observed_at":"2025-05-21 17:56:46.096741+00:00","record_version_id":"ac81dc0338899c0736ea70de07462d1e4ff05b070a7c387cf8ed1065f69de520","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-7ca1175502be18eb51f7b016818a884a43fd4ebb","semester":"1262","observed_at":"2025-07-29 06:28:23.644795+00:00","record_version_id":"0794f4b7fc01b3b527a7ef0fca6ce0e04a5f112d242a444688e429178e493ed4","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-7d8cee5e42602ad9ba5dc0322085af2fa0dffaac","semester":"1262","observed_at":"2025-05-22 01:15:19.291664+00:00","record_version_id":"7c05569051b3a571f623027defffc920005a75907d6dbb5b22f62185b187f43b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-81a0d6a7f668c98c59bd05fa988aa079c5ad1f68","semester":"1262","observed_at":"2025-05-31 07:49:50.419452+00:00","record_version_id":"008f1d1c74fd8246e22b9f48dec17ce05eab9d5a76d8dc4e7ccd4d3ea55a480c","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-82f31c08c746a214872494cde6ecaeb9330441b4","semester":"1262","observed_at":"2025-06-17 21:26:08.547156+00:00","record_version_id":"edffaa73aaeb1c98a10ec623c50e324b8e2049dccf665f48161e35b5c03cee5a","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-84c248343c5a99ab42c5616c594812a5e3e31cbb","semester":"1262","observed_at":"2025-07-04 06:00:07.487827+00:00","record_version_id":"7ba90dfc8bf6230119b709f9983a4f48b0c9d310d5ee2f445fd95f99c387c3b5","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-86334e7275e315853287e8580c35456c68df800b","semester":"1262","observed_at":"2025-05-22 06:53:03.336354+00:00","record_version_id":"bdb81ccd2fc0fae261d599e0ead74515c405fd5130bdcf15b676cb7d8cf7a10f","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-8686dc1664f93a6c05f50321410961b39b12f91b","semester":"1262","observed_at":"2025-05-28 10:17:41.595894+00:00","record_version_id":"3d113f6c23016694b3242febb14917af2165c6a5984ecefb3edb064d9d436959","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-86d941366886c9a14a2581c04e20d0bdd25e1b02","semester":"1262","observed_at":"2025-08-31 04:54:14.656039+00:00","record_version_id":"26661ce3d860cda0bbc957164b4e7e5d046c2425f32e9e1da979d9ca02e729ee","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-8ba1d2e6cfbb1525b4f9f769ec164fb6ad0f237a","semester":"1262","observed_at":"2025-06-02 05:22:45.010398+00:00","record_version_id":"52dc2393ea7dd55c0827d12c101faf38d66331d316c53088d41d7657c6c3fcba","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-90e5aa456689a3b222016c05c319bbcd0bddd453","semester":"1262","observed_at":"2025-05-25 02:00:10.037905+00:00","record_version_id":"e70449bd8f5d24ced3d89672ff9564b3f3e160e76a8040aac77983526e49245a","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-92d960aa7e4cd6e4c9ac8b2e232092904038e9e4","semester":"1262","observed_at":"2025-06-08 01:50:46.451351+00:00","record_version_id":"05028e0845711aeeb49c0448b78586ecd10ec000e866c2f87a401eb67e6dfa72","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-94002ae588a8f71eca6d64105f2e603e8587293b","semester":"1262","observed_at":"2025-05-21 09:01:16.021508+00:00","record_version_id":"880bd311ec5f329ca30b6545a54fbd1966386759bac6765fd7443e6c4781bb2b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-9dd575e013c5c6e000ab3ad2d1288cc1dd9c96dc","semester":"1264","observed_at":"2025-12-21 04:47:46.589081+00:00","record_version_id":"5a795bd5e1018c9cf2dd2941d3df125beaf7cee371ecdefe413d7aade1f01bdf","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-a1ea26ed78cbd6e94bc3221e50a6ed9b6bf43871","semester":"1262","observed_at":"2025-05-25 09:16:55.180581+00:00","record_version_id":"82d77837aa7a33ca281e5743b645523b9d36e36c7a7f57f4b0649b526ee0d53b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-a76a3505853d5ea9c13bb98472b87361d469e2ee","semester":"1262","observed_at":"2025-05-28 18:03:41.793846+00:00","record_version_id":"33284467697f479f0c116c94e1779ed8467f344b6801b250d5faed4fc1e73962","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-b285d591f6acf3aa1910e02edc297664db86eb8c","semester":"1262","observed_at":"2025-06-10 22:48:22.460295+00:00","record_version_id":"793eb1bda5aeabf533918da143fd27296098ee7bc7135d4bcd938e8a9ad9218e","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-b79af756e4f00ba98231feb859ed8e98239eb811","semester":"1262","observed_at":"2025-05-22 02:47:56.931581+00:00","record_version_id":"5936598cc00bbf4b3d733663937e6d718db465e0841322eb96f604c46473dacd","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-b89e05b94730c6471439082d9279c0a834a4aeec","semester":"1262","observed_at":"2025-08-26 20:25:42.325239+00:00","record_version_id":"3d08e103613aace09b0873421fe02e2666f59c0161ee1d645763a1e254cd7db9","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-b9279a12d1f2688df9e556183c94d41a89e431dc","semester":"1262","observed_at":"2025-07-06 01:49:47.203835+00:00","record_version_id":"4de4d14ebdb585a498a96b9353db60d44292bdbabce29ae4275f3ca6cb12e096","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-bbdc905e96cc681a5e9a8b02c795b682206e36d1","semester":"1262","observed_at":"2025-06-25 08:02:45.445730+00:00","record_version_id":"84217edd6c827cf480fb2ca45d2ca23e498587fb19ca708759adaefef3b5c3d3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-bde225b5243a13d81827aa173e39c78a652b54a0","semester":"1262","observed_at":"2025-05-23 07:22:33.219345+00:00","record_version_id":"a2455fc899db5597b60cacf980fed422b3ea0fd67d12dbf03e07815c89023067","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-c1fac4cbfde737f4f4ac02cdf15e6f5a9b5b676d","semester":"1262","observed_at":"2025-05-22 01:15:19.291664+00:00","record_version_id":"7c05569051b3a571f623027defffc920005a75907d6dbb5b22f62185b187f43b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-c6b62be45f8a13cba109ef2a7741b9cd9a6b8272","semester":"1262","observed_at":"2025-08-24 08:48:09.035112+00:00","record_version_id":"8933b6eb1211571b27d18f94a817af26cf7290feb52b35ae0a1c2b5b67e6dc5f","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-cc83f62cb6db61f39320916d819ad48ce55cd96d","semester":"1262","observed_at":"2025-05-22 00:45:35.735230+00:00","record_version_id":"7e58f79b72c96dbd60d91cb9d3b9856e2e9d093e3203fc1623d2e0ab665b7560","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-d33818a01b6b4c5e2902e704da6e5b713742d4dc","semester":"1262","observed_at":"2025-10-13 10:46:24.251475+00:00","record_version_id":"50973cef9a0291e26437d3d099141d9518e9333cf682134fc89c6d8281bb8224","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-d3c17db9832d3064916046caf891dd23f10b1bb9","semester":"1262","observed_at":"2025-08-26 11:30:42.288639+00:00","record_version_id":"f573a1c8bb1991995f89f1c93b3101736f9a96e60e534a5e4a27654d9e6e4669","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-d4ee226dc44268e9b6767fb9f5f20343322f494b","semester":"1262","observed_at":"2025-06-15 01:52:23.911697+00:00","record_version_id":"05028e0845711aeeb49c0448b78586ecd10ec000e866c2f87a401eb67e6dfa72","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-d8f9fc7f136e2033556d9d65bbdbdf33425dbdc9","semester":"1262","observed_at":"2025-05-28 16:48:12.400438+00:00","record_version_id":"9460fac33b4376e7083160e8c7ba114818ebf57b524d8c7c98e87816d5138639","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-dbbc9739c616c3846b2e796e00a36fa41225f7d8","semester":"1262","observed_at":"2025-06-01 17:47:19.325144+00:00","record_version_id":"05028e0845711aeeb49c0448b78586ecd10ec000e866c2f87a401eb67e6dfa72","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-dbe5f2d24b48c3177297a3d69c553cc9d1194bac","semester":"1262","observed_at":"2025-09-14 05:00:27.366070+00:00","record_version_id":"9ca3d547fdf60400ae7f32a6ec8bc120f59d6de70ae249de59fd24c63b0b4800","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-dd357dc2758e9e282c30988a527ce37de92593b9","semester":"1264","observed_at":"2025-10-19 01:39:41.951404+00:00","record_version_id":"b4829e5ea3a5290e0babef79b8956ebbc7fef90227f859e295c0302f6c50b58b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-de74de559e409a3fe668685e28043b888d2e6841","semester":"1262","observed_at":"2025-06-27 07:38:50.882897+00:00","record_version_id":"c5b415c2a20e92f2aa11bfdbf9cbb98b40e0628e69e9bdbd335e44df343ce3b1","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-deca7188cf536ade3203cd88b52a45e92a059617","semester":"1262","observed_at":"2025-06-27 00:37:46.087071+00:00","record_version_id":"9549a24c592da77750177247a036f2377fd2a16e483dc406969d30265d06cdd3","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-df60fa9ac3931c5612b0fa641b7a6f5fbec86fab","semester":"1262","observed_at":"2025-05-24 06:36:37.554678+00:00","record_version_id":"82d77837aa7a33ca281e5743b645523b9d36e36c7a7f57f4b0649b526ee0d53b","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-e339da2d849aaf8bb4dceca07a84728af23cf755","semester":"1262","observed_at":"2025-07-23 08:49:22.748925+00:00","record_version_id":"2a7c5c7a20e1e40f6f247af2e85e856179e68a78520c96e589483259737ff137","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-e934b1784835f5d36ae9b7ef0992b11e72c39142","semester":"1262","observed_at":"2025-06-01 06:21:25.219533+00:00","record_version_id":"e822bf19e830461252a40764287e87a8abd030827cfcb88d93068886dd0bc58e","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-ef471690c082448deebd2687eab84b0b78813c36","semester":"1262","observed_at":"2025-06-29 01:47:56.317645+00:00","record_version_id":"afae534f7da9f22dc5ffe3753cd3d63da5a3eec38c41949748e6858b9be8ea11","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-efc4e8e2cd7c3f68e059a308990c00c77c7611eb","semester":"1264","observed_at":"2025-10-16 05:48:13.935141+00:00","record_version_id":"fdc1c34dc9a33033a38365f541756c87c47b82375ffa091dcb1912fbd6ea34ca","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"},{"run_id":"legacy-f18b7749725097d41f69c60779ff38cf073b93b3","semester":"1262","observed_at":"2025-05-21 19:52:03.259353+00:00","record_version_id":"79cbc97f90ec54af05a8d77a8c1bd6636123beed2232a2915d454590d7458141","course_id":"NE 505","course_uid":"course_86c7cafe9a4854eebce61fdd","catalog_version_id":"973a7c3ba9a7be3fac9d8e94f1973c8bf01dd256b3b4207c64c4c3c74d1fcf76","course_number":505,"subjects":["NE"],"title":"NUCLEAR REACTOR ANALYSIS","description":"The neutronics behavior of fission reactors, both from a theoretical and computational multi-group perspective. Multi-group diffusion theory, finite-difference and nodal methods, core heterogeneous effects, pin power reconstruction, thermal neutron spectra, fine group whole spectrum calculations and coarse group constant generation.","requirements_text":"N E 405, graduate/professional standing, or member of Engineering Guest Students"}]