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Phenomenon identification and ranking tables (PIRTs) for power oscillations without scram in boiling water reactors containing high burnup fuel [microform] / prepared by B.E. Boyack ... [et al.]

Phenomenon identification and ranking tables (PIRTs) for power oscillations without scram in boiling water reactors containing high burnup fuel [microform] / prepared by B.E. Boyack ... [et al.]
マイクロ図書
2001<YCA-Y 3.N 88:25/6743>
国立国会図書館
  • 著者標目Boyack, B. E U.S. Nuclear Regulatory Commi...

Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel [microform] / prepared by B.E. Boyack ... [et al.] ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel [microform] / prepared by B.E. Boyack ... [et al.] ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
2001<YCA-Y 3.N 88:25/6744>
国立国会図書館
  • 著者標目Boyack, B. E U.S. Nuclear Regulatory Commi...

Phenomenon identification and ranking tables (PIRTs) for rod ejection accidents in pressurized water reactors containing high burnup fuel [microform] / prepared by B.E. Boyack ... [et al.]

Phenomenon identification and ranking tables (PIRTs) for rod ejection accidents in pressurized water reactors containing high burnup fuel [microform] / prepared by B.E. Boyack ... [et al.]
マイクロ図書
2001<YCA-Y 3.N 88:25/6742>
国立国会図書館
  • 著者標目Boyack, B. E U.S. Nuclear Regulatory Commi...

TRAC-M validation test matrix [microform] / prepared by B.E. Boyack, M. Straka, L.W. Ward

TRAC-M validation test matrix [microform] / prepared by B.E. Boyack, M. Straka, L.W. Ward
マイクロ図書
2001<YCA-Y 3.N 88:25/6720>
国立国会図書館
  • 著者標目Boyack, B. E Straka, M Ward, L. W Los Alam...

Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design LA-UR-95-1594 DE95 015287

Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design LA-UR-95-1594 DE95 015287
マイクロ規格・テクニカルリポート類
Lime, J. F, Boyack, B. E1995<LS-DE95/015287>
国立国会図書館

In-facility transport code review LA-UR-96-2952 DE96 014783

In-facility transport code review LA-UR-96-2952 DE96 014783
紙マイクロ規格・テクニカルリポート類
Spore, J. W, Boyack, B. E, Bohl, W. R1996<LS-DE96/014783>
国立国会図書館全国の図書館

Accelerator Production of Tritium Programmatic Environmental Impact Statement Input Submittal SAND-93-2094 DE96 006447

Accelerator Production of Tritium Programmatic Environmental Impact Statement Input Submittal SAND-93-2094 DE96 006447
マイクロ規格・テクニカルリポート類
Miller, L. A, Greene, G. A, Boyack, B. E1996<LS-DE96/006447>
国立国会図書館

1994 MCAP annual report. PROGRESS REPT LA-UR-95-1435 DE95 010936

1994 MCAP annual report. PROGRESS REPT LA-UR-95-1435 DE95 010936
マイクロ規格・テクニカルリポート類
Harmony, S. C, Boyack, B. E1995<LS-DE95/010936>
国立国会図書館

Analysis of an AP600 intermediatesize loss-of-coolant accident LA-UR-95-926 TI95 009422 CONF-9509043

Analysis of an AP600 intermediatesize loss-of-coolant accident LA-UR-95-926 TI95 009422 CONF-9509043
紙マイクロ規格・テクニカルリポート類
Boyack, B. E, Lime, J. F1995<LS-TI95/009422>
国立国会図書館全国の図書館

Intermediate-break LOCA analyses for the AP600 design LA-UR-95-1785 DE95 015318

Intermediate-break LOCA analyses for the AP600 design LA-UR-95-1785 DE95 015318
紙マイクロ規格・テクニカルリポート類
Boyack, B. E, Lime, J. F1995<LS-DE95/015318>
国立国会図書館全国の図書館

Assessment of the PIUS physics and thermal-hydraulic experimental data bases LA-UR-93-3564 DE95 014572

Assessment of the PIUS physics and thermal-hydraulic experimental data bases LA-UR-93-3564 DE95 014572
紙マイクロ規格・テクニカルリポート類
Boyack, B. E1993<LS-DE95/014572>
国立国会図書館全国の図書館

CONTAIN independent peer review LA-12866 DE95 006356

CONTAIN independent peer review LA-12866 DE95 006356
紙マイクロ規格・テクニカルリポート類
Boyack, B. E, Corradini, M. L, Denning, R. S, Khatib-Rahbar, M, Loyalka, S. K1995<LS-DE95/006356>
国立国会図書館全国の図書館

A plan for the modification and assessment of TRAC-PF1/MOD2 for use in analyzing CANDU 3 transient thermal-hydraulic phenomena NUREG/CR-6269 TI95 003881 LA-12853-MS

A plan for the modification and assessment of TRAC-PF1/MOD2 for use in analyzing CANDU 3 transient thermal-hydraulic phenomena NUREG/CR-6269 TI95 003881 LA-12853-MS
マイクロ規格・テクニカルリポート類
Siebe, D. A, Boyack, B. E, Giguere, P. T1994<LS-TI95/003881>
国立国会図書館

Loss of offsite power transients in the updated PIUS 600 advanced reactor design LA-UR-94-2526 DE94 016161 CONF-94114224

Loss of offsite power transients in the updated PIUS 600 advanced reactor design LA-UR-94-2526 DE94 016161 CONF-94114224
紙マイクロ規格・テクニカルリポート類
Boyack, B. E, Steiner, J. L, Harmony, S. C, Stumpf, H. J, Lime, J. F1994<LS-DE94/016161>
国立国会図書館全国の図書館

Reactor scram events in the updated PIUS 600 advanced reactor design LA-UR-94-4403 DE95 005236 CONF-9508282

Reactor scram events in the updated PIUS 600 advanced reactor design LA-UR-94-4403 DE95 005236 CONF-9508282
紙マイクロ規格・テクニカルリポート類
Boyack, B. E, Steiner, J. L, Harmony, S. C, Stumpf, H. J, Lime, J. F1994<LS-DE95/005236>
国立国会図書館全国の図書館

VALIDATION TEST MATRIX FOR THE CONSOLIDATED TRAC (TRAC-M) CODE. (LA ; LA-UR-00-778)

VALIDATION TEST MATRIX FOR THE CONSOLIDATED TRAC (TRAC-M) CODE. (LA ; LA-UR-00-778)
紙図書
BOYACK, B.E.2000.
全国の図書館

Quantifying reactor safety margins [microform] : application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident / prepared by technical program group, B. Boyack ... [et al.] ; contributing authors, K.R. Katsma ... [et al.]

Quantifying reactor safety margins [microform] : application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident / prepared by technical program group, B. Boyack ... [et al.] ; contributing authors, K.R. Katsma ... [et al.]
マイクロ図書
1989<YCA-Y 3.N 88:25/5249>
国立国会図書館
  • 著者標目Boyack, B. E Katsma, K. R U.S. Nuclear Reg...

Application programming interface document for the modernized Transient Reactor Analysis Code (TRAC-M) (LA ; LA-UR-98-2717)

Application programming interface document for the modernized Transient Reactor Analysis Code (TRAC-M) (LA ; LA-UR-98-2717)
紙図書
Mahaffy, J., Boyack, B.E., Steinke, R.G.Los Alamos National Lab.1998.5.
全国の図書館

ACCELERATOR PRODUCTION OF TRITIUM PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT INPUT SUBMITTAL (SAND ; SAND-93-2094)

ACCELERATOR PRODUCTION OF TRITIUM PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT INPUT SUBMITTAL (SAND ; SAND-93-2094)
紙図書
MILLER, L.A.// GREENE, G.A.// BOYACK, B.E. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (UNITED STATES))Sandia National Laboratories(Sandia National Laboratories)1996.
全国の図書館

Dominant accident sequences in Oconee-I pressurized water reactor / J.F. Dearing, R.J. Henninger, B. Nassersharif ; compiled by B.E. Boyack, B. Nassersharif

Dominant accident sequences in Oconee-I pressurized water reactor / J.F. Dearing, R.J. Henninger, B. Nassersharif ; compiled by B.E. Boyack, B. Nassersharif
マイクロ図書
1985<YCA-Y 3.N 88:25/4140>
国立国会図書館
  • 著者標目...assersharif, B Boyack, B. E U.S. Nuclear Regulatory Commi...
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