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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
Microform図書
1997<YCA-Y 3.N 88:25/6541/REV.2>
National Diet Library

RELAP5/MOD3 code manual NUREG/CR-5535-Vol.7 TI94 015133

RELAP5/MOD3 code manual NUREG/CR-5535-Vol.7 TI94 015133
Microform規格・テクニカルリポート類
Sloan, S. M, Schultz, R. R, Wilson, G. E1994<LS-TI94/015133>
National Diet Library

Advanced Neutron Source Reactor (ANSR) phenomena identification and ranking (PIR) for large break loss of coolant accidents (LBLOCA) ORNL/TM-12496 DE95 002440

Advanced Neutron Source Reactor (ANSR) phenomena identification and ranking (PIR) for large break loss of coolant accidents (LBLOCA) ORNL/TM-12496 DE95 002440
Microform規格・テクニカルリポート類
Ruggles, A. E, Cheng, L. Y, Dimenna, R. A, Griffith, P, Wilson, G. E1994<LS-DE95/002440>
National Diet Library

STATISTICALLY BASED UNCERTAINTY ANALYSIS FOR RANKING OF COMPONENT IMPORTANCE IN THE THERMAL-HYDRAULIC SAFETY ANALYSIS OF THE ADVANCED NEUTRON SOURCE REACTOR. (EGG ; EGG-NE-10078)

STATISTICALLY BASED UNCERTAINTY ANALYSIS FOR RANKING OF COMPONENT IMPORTANCE IN THE THERMAL-HYDRAULIC SAFETY ANALYSIS OF THE ADVANCED NEUTRON SOURCE REACTOR. (EGG ; EGG-NE-10078)
Paper図書
WILSON, G.E.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1992.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

CSAU (CODE SCALING, APPLICABILITY AND UNCERTAINTY), A TOOL TO PRIORITIZE ADVANCED REACTOR RESEARCH. (EGG ; EGG-M-89114)

CSAU (CODE SCALING, APPLICABILITY AND UNCERTAINTY), A TOOL TO PRIORITIZE ADVANCED REACTOR RESEARCH. (EGG ; EGG-M-89114)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1990.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

QUANTIFYING REACTOR SAFETY MARGINS: PART 2, CHARACTERIZATION OF IMPORTANT CONTRIBUTORS TO UNCERTAINTY. (EGG ; EGG-M-88312)

QUANTIFYING REACTOR SAFETY MARGINS: PART 2, CHARACTERIZATION OF IMPORTANT CONTRIBUTORS TO UNCERTAINTY. (EGG ; EGG-M-88312)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1988.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

EXPERIMENTAL DATA BASES USEFUL FOR QUANTIFICATION OF MODEL UNCERTAINTIES IN BEST ESTIMATE CODES. (EGG ; EGG-M-88334)

EXPERIMENTAL DATA BASES USEFUL FOR QUANTIFICATION OF MODEL UNCERTAINTIES IN BEST ESTIMATE CODES. (EGG ; EGG-M-88334)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1988.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

ACHIEVING 95% PROBABILITY LEVEL USING BEST ESTIMATE CODES AND THE CODE SCALING, APPLICABILITY AND UNCERTAINTY (CSAU) (CODE SCALING. (EGG ; EGG-M-88333)

ACHIEVING 95% PROBABILITY LEVEL USING BEST ESTIMATE CODES AND THE CODE SCALING, APPLICABILITY AND UNCERTAINTY (CSAU) (CODE SCALING. (EGG ; EGG-M-88333)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1988.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

DEVELOPMENT AND APPLICATION OF METHODS TO CHARACTERIZE CODE UNCERTAINTY. (EGG ; EGG-M-27585)

DEVELOPMENT AND APPLICATION OF METHODS TO CHARACTERIZE CODE UNCERTAINTY. (EGG ; EGG-M-27585)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

OVERVIEW OF TRAC-BWR ASSESSMENT: TRAC-BD1/MOD1 AND TRAC-BF1. (EGG ; EGG-M-20285)

OVERVIEW OF TRAC-BWR ASSESSMENT: TRAC-BD1/MOD1 AND TRAC-BF1. (EGG ; EGG-M-20285)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

INDEPENDENT ASSESSMENT OF THE TRAC-BD1/MOD1 COMPUTER CODE AT THE IDAHO NATIONAL. (EGG ; EGG-M-19084)

INDEPENDENT ASSESSMENT OF THE TRAC-BD1/MOD1 COMPUTER CODE AT THE IDAHO NATIONAL. (EGG ; EGG-M-19084)
Paper図書
WILSON, G.E.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1984.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

BOILING WATER REACTOR CONTAINMENT MODELING AND ANALYSIS AT THE IDAHO NATIONAL ENGINEERING LABORATORY (CONF ; CONF-841075-8)

BOILING WATER REACTOR CONTAINMENT MODELING AND ANALYSIS AT THE IDAHO NATIONAL ENGINEERING LABORATORY (CONF ; CONF-841075-8)
Paper図書
1984.
Other Libraries in Japan

CONCLUSIONS FROM THE INDEPENDENT ASSESSMENT OF TRAC-BD1/VERSION 12. (EGG ; EGG-M-20583)

CONCLUSIONS FROM THE INDEPENDENT ASSESSMENT OF TRAC-BD1/VERSION 12. (EGG ; EGG-M-20583)
Paper図書
WILSON, G.E.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1983.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

CONCLUSIONS FROM THE INDEPENDENT ASSESSMENT OF TRAC-BD1/VERSION 12. [BWR] (CONF ; CONF-8310143-43)

CONCLUSIONS FROM THE INDEPENDENT ASSESSMENT OF TRAC-BD1/VERSION 12. [BWR] (CONF ; CONF-8310143-43)
Paper図書
1983.
Other Libraries in Japan

INDEPENDENT ASSESSMENT OF THE TRAC-BD1/MOD1 COMPUTER CODE AT THE IDAHO NATIONAL ENGINEERING LABORATORY (CONF ; CONF-8410142-47)

INDEPENDENT ASSESSMENT OF THE TRAC-BD1/MOD1 COMPUTER CODE AT THE IDAHO NATIONAL ENGINEERING LABORATORY (CONF ; CONF-8410142-47)
Paper図書
1984.
Other Libraries in Japan

COMPARISON OF RELAP4/MOD6 WITH FORCED FEED REFLOOD DATA. (CVAP ; CVAP-TR-7-78)

COMPARISON OF RELAP4/MOD6 WITH FORCED FEED REFLOOD DATA. (CVAP ; CVAP-TR-7-78)
Paper図書
WILSON, G.E.1978.
Other Libraries in Japan
  • Author HeadingWILSON, G.E.

Developmental verification of RELAP4/MOD6 update 1 with FLECHT LFR cosine test data base (PG ; PG-R-77-24)

Developmental verification of RELAP4/MOD6 update 1 with FLECHT LFR cosine test data base (PG ; PG-R-77-24)
Paper図書
Fletcher, C.D., Wilson, G.E.Idaho National Engineering Lab.1977.7.
Other Libraries in Japan
  • Author HeadingFletcher, C.D. Wilson, G.E.

PHENOMENA IDENTIFICATION AND RANKING TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-OF-COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM GENERATOR TUBE RUPTURE SCENARIOS.

PHENOMENA IDENTIFICATION AND RANKING TABLES FOR WESTINGHOUSE AP600 SMALL BREAK LOSS-OF-COOLANT ACCIDENT, MAIN STEAM LINE BREAK, AND STEAM GENERATOR TUBE RUPTURE SCENARIOS.
Paper図書
BOUCHER, T. J.//BURTT, J. D.//DAVIS, C. B.//FLETCHER, C. D.//WILSON, G. E.IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY1997/06/30.
Other Libraries in Japan

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