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Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant [microform] / prepared by C. Llopis, A. Tanarro, R.M. Fanegas (International agreement report ; NUREG/IA-0197)

Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant [microform] / prepared by C. Llopis, A. Tanarro, R.M. Fanegas (International agreement report ; NUREG/IA-0197)
マイクロ図書
2001<YCA-Y 3.N 88:53/0197>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Spain -- Computer simulati...

Analysis of inadvertent pressurizer spray valve opening real transient with RELAP5/MOD3.2 [microform] / prepared by J. Blanco ... [et al.] (International agreement report ; NUREG/IA-0194)

Analysis of inadvertent pressurizer spray valve opening real transient with RELAP5/MOD3.2 [microform] / prepared by J. Blanco ... [et al.] (International agreement report ; NUREG/IA-0194)
マイクロ図書
2001<YCA-Y 3.N 88:53/0194>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Spain -- Computer simulati...

Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions [microform] : phase I final report / prepared by S. Majumdar, W. Shack

Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions [microform] : phase I final report / prepared by S. Majumdar, W. Shack
マイクロ図書
2003<YCA-Y 3.N 88:25/6792>
国立国会図書館
  • 件名...-- Reliability Pressurized water reactors -- Accidents

Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code [microform] / prepared by J. Blanco ... [et al.] (International agreement report ; NUREG/IA-0183)

Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code [microform] / prepared by J. Blanco ... [et al.] (International agreement report ; NUREG/IA-0183)
マイクロ図書
2000<YCA-Y 3.N 88:53/0183>
国立国会図書館
  • 件名...ter simulation Pressurized water reactors -- Accidents -- Computer simulation

Study of transients related to AMSAC actuation, sensitivity analysis [microform] / prepared by J.M. Posada ... [et al.] (International agreement report ; NUREG/IA-0150)

Study of transients related to AMSAC actuation, sensitivity analysis [microform] / prepared by J.M. Posada ... [et al.] (International agreement report ; NUREG/IA-0150)
マイクロ図書
1998<YCA-Y 3.N 88:53/0150>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Spain -- Computer simulati...

Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant [microform] / prepared by C. Llopis, M. Martin (International agreement report ; NUREG/IA-0149)

Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant [microform] / prepared by C. Llopis, M. Martin (International agreement report ; NUREG/IA-0149)
マイクロ図書
1998<YCA-Y 3.N 88:53/0149>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Spain -- Computer simulati...

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
  • 件名...-- Forecasting Pressurized water reactors -- Accidents -- Forecasting Fuel burnup (N...

Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios [microform] / prepared by G.E. Wilson ... [et al.] Rev. 2

Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios [microform] / prepared by G.E. Wilson ... [et al.] Rev. 2
マイクロ図書
1997<YCA-Y 3.N 88:25/6541/REV.2>
国立国会図書館
  • 件名Pressurized water reactors -- Loss of coolant Pressurized water reactors -- Accidents

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
  • 件名Pressurized water reactors -- Accidents -- Forecasting -- Computer pr...

TRAC-M programmer's guide [microform] : Fortran 77, version 5.5 / prepared by R.G. Steinke, S.J. Jolly-Woodruff, J.W. Spore

TRAC-M programmer's guide [microform] : Fortran 77, version 5.5 / prepared by R.G. Steinke, S.J. Jolly-Woodruff, J.W. Spore
マイクロ図書
1999<YCA-Y 3.N 88:25/6658>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Forecasting -- Computer pr...

TRAC-M/FORTRAN 90 (version 3.0) programmer's manual [microform] / prepared by B.T. Adams ... [et al.]

TRAC-M/FORTRAN 90 (version 3.0) programmer's manual [microform] / prepared by B.T. Adams ... [et al.]
マイクロ図書
2001<YCA-Y 3.N 88:25/6725>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Forecasting -- Computer pr...

TRAC-M/FORTRAN 90 (version 3.0) theory manual [microform] / prepared by J.W. Spore ... [et al.]

TRAC-M/FORTRAN 90 (version 3.0) theory manual [microform] / prepared by J.W. Spore ... [et al.]
マイクロ図書
2001<YCA-Y 3.N 88:25/6724>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Forecasting -- Computer pr...

TRAC-M/FORTRAN 90 (version 3.0) user manual [microform] / prepared by R.G. Steinke ... [et al.]

TRAC-M/FORTRAN 90 (version 3.0) user manual [microform] / prepared by R.G. Steinke ... [et al.]
マイクロ図書
2001<YCA-Y 3.N 88:25/6722>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Forecasting -- Computer pr...

Identification and evaluation of PWR in-vessel severe accident management strategies microform / prepared by J.S. Dukelow, D.G. Harrison, M. Morgenstern

Identification and evaluation of PWR in-vessel severe accident management strategies microform / prepared by J.S. Dukelow, D.G. Harrison, M. Morgenstern
マイクロ図書
1992<YCA-Y 3.N 88:25/5856>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents Pressurized water reactors --...

Review and summary of TRAC assessment from the International Code Assessment and Application Program (ICAP) [microform] / prepared by N.M. Schnurr (International agreement report ; NUREG/IA-0078)

Review and summary of TRAC assessment from the International Code Assessment and Application Program (ICAP) [microform] / prepared by N.M. Schnurr (International agreement report ; NUREG/IA-0078)
マイクロ図書
1992<YCA-Y 3.N 88:53/0078>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Computer programs -- Evalu...

Summary of a workshop on severe accident management for PWRs [microform] / prepared by W.E. Kastenberg, editor ; G. Apostolakis ... [et al.]

Summary of a workshop on severe accident management for PWRs [microform] / prepared by W.E. Kastenberg, editor ; G. Apostolakis ... [et al.]
マイクロ図書
1991<YCA-Y 3.N 88:25/5781>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Management -- Congresses

Assessment of RELAP5/MOD2, cycle 36.04 against LOFT small break experiment L3-6 microform / prepared by John Eriksson (International agreement report ; NUREG/IA-0033)

Assessment of RELAP5/MOD2, cycle 36.04 against LOFT small break experiment L3-6 microform / prepared by John Eriksson (International agreement report ; NUREG/IA-0033)
マイクロ図書
1990<YCA-Y 3.N 88:53/0033>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Computer programs

LOFT input dataset reference document for RELAP5 validation studies [microform] / prepared by J.C. Birchley (International agreement report ; NUREG/IA-0072)

LOFT input dataset reference document for RELAP5 validation studies [microform] / prepared by J.C. Birchley (International agreement report ; NUREG/IA-0072)
マイクロ図書
1992<YCA-Y 3.N 88:53/0072>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents -- Computer programs Computer...

PWR dry containment issue characterization / prepared by J.W. Yang

PWR dry containment issue characterization / prepared by J.W. Yang
マイクロ図書
1990<YCA-Y 3.N 88:25/5567>
国立国会図書館
  • 件名Pressurized water reactors -- Accidents Nuclear reactors -- Containme...

Assessment of subcooled boiling model used in RELAP5/MOD2 (cycle 36.05, version E03) against experimental data [microform] / prepared by C.R. Brain (International agreement report ; NUREG/IA-0056)

Assessment of subcooled boiling model used in RELAP5/MOD2 (cycle 36.05, version E03) against experimental data [microform] / prepared by C.R. Brain (International agreement report ; NUREG/IA-0056)
マイクロ図書
1992<YCA-Y 3.N 88:53/0056>
国立国会図書館
  • 件名...ter simulation Pressurized water reactors -- Accidents -- Computer simulation
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