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Recommendations for addressing axial burnup in PWR burnup credit analyses [microform] / prepared by J.C. Wagner, M.D. DeHart, C.V. Parks

Recommendations for addressing axial burnup in PWR burnup credit analyses [microform] / prepared by J.C. Wagner, M.D. DeHart, C.V. Parks
マイクロ図書
2003<YCA-Y 3.N 88:25/6801>
国立国会図書館
  • 著者標目Wagner, J. C DeHart, M. D Parks, C. V U.S. Nuclear Regu...

FUEL ELEMENT DESIGN AND ANALYSIS FOR ADVANCED TEST REACTOR CONVERSION TO LEU FUEL; 2013 ANS WINTER MEETING AND NUCLEAR TECHNOLOGY EXPO. (S&T Issue 2014-13)(CD-ROM) (DE131107272 ; DE131107272; INL/CON-13-29563)

FUEL ELEMENT DESIGN AND ANALYSIS FOR ADVANCED TEST REACTOR CONVERSION TO LEU FUEL; 2013 ANS WINTER MEETING AND NUCLEAR TECHNOLOGY EXPO. (S&T Issue 2014-13)(CD-ROM) (DE131107272 ; DE131107272; INL/CON-13-29563)
紙図書
DEHART, M.D.(et al.)2013.
全国の図書館

Advanced deterministic method for spent fuel criticality safety analysis ORNLCP96096 DE98 003369

Advanced deterministic method for spent fuel criticality safety analysis ORNLCP96096 DE98 003369
マイクロ規格・テクニカルリポート類
DeHart, M. D1998<LS-DE98/003369>
国立国会図書館

Evaluation of measured LWR spent fuel composition data for use in code validation ORNLM6121 DE98 003778

Evaluation of measured LWR spent fuel composition data for use in code validation ORNLM6121 DE98 003778
マイクロ規格・テクニカルリポート類
Hermann, O. W, DeHart, M. D, Murphy, B. D1998<LS-DE98/003778>
国立国会図書館

Review and prioritization of technical issues related to burnup credit for LWR fuel [microform] / prepared by C.V. Parks, M.D. DeHart, J.C. Wagner

Review and prioritization of technical issues related to burnup credit for LWR fuel [microform] / prepared by C.V. Parks, M.D. DeHart, J.C. Wagner
マイクロ図書
2000<YCA-Y 3.N 88:25/6665>
国立国会図書館
  • 著者標目Parks, C. V DeHart, M. D Wagner, J. C U.S. Nuclear Reg...

International studies on burnup credit criticality safety by an OECD/NEA working group ORNLCP99309 DE99 000395

International studies on burnup credit criticality safety by an OECD/NEA working group ORNLCP99309 DE99 000395
マイクロ規格・テクニカルリポート類
Brady, M. C, Okuno, H, DeHart, M. D, Nouri, A, Sartori, E1998<LS-DE99/000395>
国立国会図書館

Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages ORNL/TM-12973 DE96 012441

Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages ORNL/TM-12973 DE96 012441
マイクロ規格・テクニカルリポート類
DeHart, M. D1996<LS-DE96/012441>
国立国会図書館

Issues related to criticality safety analysis for burnup credit applications CONF-9509100-35 DE96 003018

Issues related to criticality safety analysis for burnup credit applications CONF-9509100-35 DE96 003018
紙マイクロ規格・テクニカルリポート類
DeHart, M. D, Parks, C. V1995<LS-DE96/003018>
国立国会図書館全国の図書館

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 1: Summary ORNL/TM-12294/V.1 DE95 010421

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 1: Summary ORNL/TM-12294/V.1 DE95 010421
マイクロ規格・テクニカルリポート類
DeHart, M. D1995<LS-DE95/010421>
国立国会図書館

Shielding analysis of depleted uranium silicate filler concept for spent fuel canister designs CONF-960415-33 DE96 008090

Shielding analysis of depleted uranium silicate filler concept for spent fuel canister designs CONF-960415-33 DE96 008090
紙マイクロ規格・テクニカルリポート類
DeHart, M. D, Tang, J. S, Forsberg, C. W1996<LS-DE96/008090>
国立国会図書館全国の図書館

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 4: Three Mile Island Unit 1 Cycle 5 ORNL/TM-12294/V.4 DE95 010427

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 4: Three Mile Island Unit 1 Cycle 5 ORNL/TM-12294/V.4 DE95 010427
マイクロ規格・テクニカルリポート類
DeHart, M. D1995<LS-DE95/010427>
国立国会図書館

OECD/NEA burnup credit calculational criticality benchmark Phase I-B results ORNL-6901 DE96 012273 NEA-NSC-DOC-96-06

OECD/NEA burnup credit calculational criticality benchmark Phase I-B results ORNL-6901 DE96 012273 NEA-NSC-DOC-96-06
マイクロ規格・テクニカルリポート類
DeHart, M. D, Parks, C. V, Brady, M. C1996<LS-DE96/012273>
国立国会図書館

Validation of a method for prediction of isotopic concentrations in burnup credit applications CONF-9509100-12 DE95 017431

Validation of a method for prediction of isotopic concentrations in burnup credit applications CONF-9509100-12 DE95 017431
紙マイクロ規格・テクニカルリポート類
DeHart, M. D, Hermann, O. W, Parks, C. V1995<LS-DE95/017431>
国立国会図書館全国の図書館

Analysis of fresh fuel critical experiments appropriate for burnup credit validation ORNL/TM-12959 DE96 003595

Analysis of fresh fuel critical experiments appropriate for burnup credit validation ORNL/TM-12959 DE96 003595
マイクロ規格・テクニカルリポート類
DeHart, M. D, Bowman, S. M1995<LS-DE96/003595>
国立国会図書館

Benefits/impacts of utilizing depleted uranium silicate glass as backfill for spent fuel waste packages CONF-960421-35 DE96 008810

Benefits/impacts of utilizing depleted uranium silicate glass as backfill for spent fuel waste packages CONF-960421-35 DE96 008810
紙マイクロ規格・テクニカルリポート類
Pope, R. B, Forsberg, C. W, Ashline, R. C, DeHart, M. D, Childs, K. W1996<LS-DE96/008810>
国立国会図書館全国の図書館

Validation of the SCALE broad structure 44-group ENDF/B-Y cross-section library for use in critically safety analyses NUREG/CR-6102 TI95 001054 ORNL/TM-12460

Validation of the SCALE broad structure 44-group ENDF/B-Y cross-section library for use in critically safety analyses NUREG/CR-6102 TI95 001054 ORNL/TM-12460
マイクロ規格・テクニカルリポート類
DeHart, M. D, Bowman, S. M1994<LS-TI95/001054>
国立国会図書館

Potential benefits and impacts on the CRWMS transportation system of filling spent fuel shipping casks with depleted uranium silicate glass CONF-960804-12 DE96 009394

Potential benefits and impacts on the CRWMS transportation system of filling spent fuel shipping casks with depleted uranium silicate glass CONF-960804-12 DE96 009394
紙マイクロ規格・テクニカルリポート類
Pope, R. B, Forsberg, C. W, DeHart, M. D, Childs, K. W, Tang, J. S1996<LS-DE96/009394>
国立国会図書館全国の図書館

Validation of the SCALE broad structure 44-group ENDF/B-V cross-section library for use in criticality safety analyses NUREG/CR-6102 TI95 001054 ORNL/TM-12460

Validation of the SCALE broad structure 44-group ENDF/B-V cross-section library for use in criticality safety analyses NUREG/CR-6102 TI95 001054 ORNL/TM-12460
マイクロ規格・テクニカルリポート類
DeHart, M. D, Bowman, S. M1994<LS-TI95/001054>
国立国会図書館

Investigation of nuclide importance to functional requirements related to transport and long-term storage of LWR spent fuel ORNL/TM-12742 DE95 014462

Investigation of nuclide importance to functional requirements related to transport and long-term storage of LWR spent fuel ORNL/TM-12742 DE95 014462
マイクロ規格・テクニカルリポート類
Broadhead, B. L, DeHart, M. D, Ryman, J. C, Tang, J. S, Parks, C. V1995<LS-DE95/014462>
国立国会図書館

Recent validation experience with multigroup cross-section libraries and scale CONF-9509100-34 DE96 003046

Recent validation experience with multigroup cross-section libraries and scale CONF-9509100-34 DE96 003046
紙マイクロ規格・テクニカルリポート類
Bowman, S. M, Wright, R. Q, DeHart, M. D, Parks, C. V, Petrie, L. M1995<LS-DE96/003046>
国立国会図書館全国の図書館
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