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FMDP reactor alternative summary report. Volume 1 - existing LWR alternative ORNL/TM-13275/V1 DE97 001636

FMDP reactor alternative summary report. Volume 1 - existing LWR alternative ORNL/TM-13275/V1 DE97 001636
Microform規格・テクニカルリポート類
Greene, S. R, Bevard, B. B1996<LS-DE97/001636>
National Diet Library

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative ORNL/TM-13275/V2 DE97 051283

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative ORNL/TM-13275/V2 DE97 051283
Microform規格・テクニカルリポート類
Greene, S. R, Spellman, D. J, Bevard, B. B1996<LS-DE97/051283>
National Diet Library

FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative ORNL/TM-13275/V3 DE97 051284

FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative ORNL/TM-13275/V3 DE97 051284
Microform規格・テクニカルリポート類
Greene, S. R, Fisher, S. E, Bevard, B. B1996<LS-DE97/051284>
National Diet Library

REACTOR-BASED PLUTONIUM DISPOSITION: OPPORTUNITIES, OPTIONS, AND ISSUES. (ORNL ; ORNL/CP-102975; DE2001-9884)

REACTOR-BASED PLUTONIUM DISPOSITION: OPPORTUNITIES, OPTIONS, AND ISSUES. (ORNL ; ORNL/CP-102975; DE2001-9884)
Paper図書
GREENE, S.R.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1999.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

BWR MARK II EX-VESSEL CORIUM INTERACTION ANALYSES. (NUREG ; NUREG/CR-5623)

BWR MARK II EX-VESSEL CORIUM INTERACTION ANALYSES. (NUREG ; NUREG/CR-5623)
Paper図書
GREENE, S.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1991.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

RESPONSE OF BWR MARK II CONTAINMENTS TO STATION BLACKOUT SEVERE ACCIDENT SEQUENCES. (NUREG ; NUREG/CR-5565)

RESPONSE OF BWR MARK II CONTAINMENTS TO STATION BLACKOUT SEVERE ACCIDENT SEQUENCES. (NUREG ; NUREG/CR-5565)
Paper図書
GREENE, S.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1991.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

FACILITY MODIFICATION FOR SEVERE ACCIDENT MITIGATION AT THE HIGH FLUX ISOTOPE REACTOR (CONF ; CONF-930807-4)

FACILITY MODIFICATION FOR SEVERE ACCIDENT MITIGATION AT THE HIGH FLUX ISOTOPE REACTOR (CONF ; CONF-930807-4)
Paper図書
MORRIS, R.H.// LEPARD, B.L.// FISHER, S.E.// GREENE, S.R. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
Other Libraries in Japan
  • Author HeadingMORRIS, R.H. LEPARD, B.L. FISHER, S.E. GREENE, S.R.

RESPONSE OF BWR MARK IIICONTAINMENTS TO SHORT-TERM STATION BLACKOUT SEVERE ACCIDENT SEQUENCES. (NUREG ; NUREG/CR-5571)

RESPONSE OF BWR MARK IIICONTAINMENTS TO SHORT-TERM STATION BLACKOUT SEVERE ACCIDENT SEQUENCES. (NUREG ; NUREG/CR-5571)
Paper図書
GREENE, S.R.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1991.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

CHARACTERIZATION OF DEBRIS/CONCRETE INTERACTIONS FOR ADVANCED RESEARCH REACTOR AND COMMERCIAL BWR SEVERE ACCIDENTS (CONF ; CONF-911107-30)

CHARACTERIZATION OF DEBRIS/CONCRETE INTERACTIONS FOR ADVANCED RESEARCH REACTOR AND COMMERCIAL BWR SEVERE ACCIDENTS (CONF ; CONF-911107-30)
Paper図書
HYMAN, C.R.// TALEYARKHAN, R.P.// GREENE, S.R. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1991.
Other Libraries in Japan
  • Author HeadingHYMAN, C.R. TALEYARKHAN, R.P. GREENE, S.R.

ADVANCED NEUTRON SOURCE FACILITY: SAFETY PHILOSOPHY AND STUDIES. (CONF ; CONF-881011-9)

ADVANCED NEUTRON SOURCE FACILITY: SAFETY PHILOSOPHY AND STUDIES. (CONF ; CONF-881011-9)
Paper図書
GREENE, S.R.(et al.)1988.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

PRELIMINARY MODELING AND ANALYSIS FRAMEWORK FOR SEVERE ACCIDENT ANALYSIS OF HIGH POWER DENSITY RESEARCH REACTORS (IAEA ; IAEA-SM-310/63P)

PRELIMINARY MODELING AND ANALYSIS FRAMEWORK FOR SEVERE ACCIDENT ANALYSIS OF HIGH POWER DENSITY RESEARCH REACTORS (IAEA ; IAEA-SM-310/63P)
Paper図書
GREENE, S.R.//SIMPSON, D.B.//TALEYARKHAN, R.P. (INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA (AUSTRIA))International Atomic Energy Agency(International Atomic Energy Agency)1989.
Other Libraries in Japan
  • Author HeadingGREENE, S.R. SIMPSON, D.B. TALEYARKHAN, R....

ROLE OF BWR SECONDARY CONTAINMENTS IN SEVERE ACCIDENT MITIGATION: ISSUES AND INSIGHTS FROM RECENT ANALYSES. (CONF ; CONF-8806153-1)

ROLE OF BWR SECONDARY CONTAINMENTS IN SEVERE ACCIDENT MITIGATION: ISSUES AND INSIGHTS FROM RECENT ANALYSES. (CONF ; CONF-8806153-1)
Paper図書
GREENE, S.R.1988.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

IMPACT OF BWR MK I PRIMARY CONTAINMENT FAILURE DYNAMICS ON SECONDARY CONTAINMENT INTEGRITY. (CONF ; CONF-8710111-6)

IMPACT OF BWR MK I PRIMARY CONTAINMENT FAILURE DYNAMICS ON SECONDARY CONTAINMENT INTEGRITY. (CONF ; CONF-8710111-6)
Paper図書
GREENE, S.R.1987.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

ROLE OF BWR MK I SECONDARY CONTAINMENTS IN SEVERE ACCIDENT MITIGATION. (CONF ; CONF-8610135-41)

ROLE OF BWR MK I SECONDARY CONTAINMENTS IN SEVERE ACCIDENT MITIGATION. (CONF ; CONF-8610135-41)
Paper図書
GREENE, S.R.1986.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.

APPLICATION OF THERMIX-KONVEK CODE TO ACCIDENT ANALYSES OF MODULAR PEBBLE BED HIGH TEMPERATURE REACTORS (HTRS) (NUREG ; NUREG/CR-4694; ORNL/TM-9905)

APPLICATION OF THERMIX-KONVEK CODE TO ACCIDENT ANALYSES OF MODULAR PEBBLE BED HIGH TEMPERATURE REACTORS (HTRS) (NUREG ; NUREG/CR-4694; ORNL/TM-9905)
Paper図書
CLEVELAND, J.C./GREENE, S.R.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
Other Libraries in Japan
  • Author HeadingCLEVELAND, J.C. GREENE, S.R.

Realistic Simulation of Severe Accidents in BWRs; Computer Modeling Requirements (NUREG ; NUREG/CR-2940; ORNL/TM-8517)

Realistic Simulation of Severe Accidents in BWRs; Computer Modeling Requirements (NUREG ; NUREG/CR-2940; ORNL/TM-8517)
Paper図書
Greene, S.R.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
Other Libraries in Japan
  • Author HeadingGreene, S.R.

Loss of DHR Sequences at Browns Ferry Unit One; Accident Sequence Analysis (NUREG ; NUREG/CR-2973; ORNL/TM-8532)

Loss of DHR Sequences at Browns Ferry Unit One; Accident Sequence Analysis (NUREG ; NUREG/CR-2973; ORNL/TM-8532)
Paper図書
Cook, D.H./Greene, S.R./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1983.
Other Libraries in Japan
  • Author HeadingCook, D.H. Greene, S.R. and others

SBLOCA Outside Containment at Browns Ferry Unit One; Accident Sequence Analysis (NUREG ; NUREG/CR-2672-V1; ORNL/TM-8119/V1)

SBLOCA Outside Containment at Browns Ferry Unit One; Accident Sequence Analysis (NUREG ; NUREG/CR-2672-V1; ORNL/TM-8119/V1)
Paper図書
Condon, W.A./Greene, S.R./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.
Other Libraries in Japan
  • Author HeadingCondon, W.A. Greene, S.R. and others

Station blackout at browns ferry unit one; Accident sequence analysis. (NUREG ; NUREG/CR-2182; ORNL/NUREG/TM-455/V1)

Station blackout at browns ferry unit one; Accident sequence analysis. (NUREG ; NUREG/CR-2182; ORNL/NUREG/TM-455/V1)
Paper図書
Cook, D.H./Greene, S.R./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingCook, D.H. Greene, S.R. and others

PICES: A COMPUTER CODE FOR EVALUATION OF ELECTRIC UTILITY STATIC GENERATION RELIABILITY. (ORNL ; ORNL-5739)

PICES: A COMPUTER CODE FOR EVALUATION OF ELECTRIC UTILITY STATIC GENERATION RELIABILITY. (ORNL ; ORNL-5739)
Paper図書
GREENE, S.R.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1981.
Other Libraries in Japan
  • Author HeadingGREENE, S.R.
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