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DESCRIPTION OF THE TWO-LOOP RELAP5 MODEL OF THE L-REACTOR AT THE SAVANNAH RIVER SITE. (EGG ; EGG-EAST-8449)

DESCRIPTION OF THE TWO-LOOP RELAP5 MODEL OF THE L-REACTOR AT THE SAVANNAH RIVER SITE. (EGG ; EGG-EAST-8449)
Paper図書
COZZUOL, J.M.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1989.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

TRAC L REACTOR MODEL: GEOMETRY REVIEW AND BENCHMARKING (WSRC ; WSRC-TR-90-32)

TRAC L REACTOR MODEL: GEOMETRY REVIEW AND BENCHMARKING (WSRC ; WSRC-TR-90-32)
Paper図書
GRIGGS, D.P.// COZZUOL, J.M. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1990.
Other Libraries in Japan
  • Author HeadingGRIGGS, D.P. COZZUOL, J.M.

DECAY HEAT REMOVAL USING FEED-AND-BLEED FOR US PRESSURIZED WATER REACTORS (EGG ; EGG-2526)

DECAY HEAT REMOVAL USING FEED-AND-BLEED FOR US PRESSURIZED WATER REACTORS (EGG ; EGG-2526)
Paper図書
EG and G Idaho, Inc.(EG and G Idaho, Inc.)1988.
Other Libraries in Japan

LOSS-OF-PUMPING ACCIDENT IN SAVANNAH RIVER L-REACTOR. (EGG ; EGG-EAST-8273)

LOSS-OF-PUMPING ACCIDENT IN SAVANNAH RIVER L-REACTOR. (EGG ; EGG-EAST-8273)
Paper図書
COZZUOL, J.M.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1988.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

RELAP5/MOD2 CODE ASSESSMENT AT THE IDAHO NATIONAL ENGINEERING LABORATORY (EGG ; EGG--2428)

RELAP5/MOD2 CODE ASSESSMENT AT THE IDAHO NATIONAL ENGINEERING LABORATORY (EGG ; EGG--2428)
Paper図書
EG and G Idaho, Inc.(EG and G Idaho, Inc.)1986.
Other Libraries in Japan

RELAP5/MOD2 ASSESSMENT AT INEL (CONF ; CONF-8510173--54)

RELAP5/MOD2 ASSESSMENT AT INEL (CONF ; CONF-8510173--54)
Paper図書
1985.
Other Libraries in Japan

Application of a honeycomb insulator design in a variable high temperature, high pressure environment. (NUREG ; NUREG/CR-2361; EGG-2133)

Application of a honeycomb insulator design in a variable high temperature, high pressure environment. (NUREG ; NUREG/CR-2361; EGG-2133)
Paper図書
Larson, T.K./Cozzuol, J.M./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingLarson, T.K. Cozzuol, J.M. and others

INVESTIGATION OF THE INFLUENCE OF SIMULATED STEAM GENERATOR TUBE RUPTURES DURING LOSS OF COOLANT... (NUREG ; NUREG-CR-0175)

INVESTIGATION OF THE INFLUENCE OF SIMULATED STEAM GENERATOR TUBE RUPTURES DURING LOSS OF COOLANT... (NUREG ; NUREG-CR-0175)
Paper図書
COZZUOL, J.M.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1978.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

INFLUENCE OF STEAM GENERATOR TUBE RUPTURES DURING SEMISCALE LOSS-OF COOLANT EXPERIMENTS. (INIS ; INIS-MF-4868)

INFLUENCE OF STEAM GENERATOR TUBE RUPTURES DURING SEMISCALE LOSS-OF COOLANT EXPERIMENTS. (INIS ; INIS-MF-4868)
Paper図書
COZZUOL, J.M.(et al.)International Atomic Energy Agency(International Atomic Energy Agency)1978.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

SEMISCALE TEST S-02-8 MINI-TOPICAL FOR STANDARD PROBLEM FIVE. (TREE ; TREE-NUREG-1015)

SEMISCALE TEST S-02-8 MINI-TOPICAL FOR STANDARD PROBLEM FIVE. (TREE ; TREE-NUREG-1015)
Paper図書
COZZUOL, J.M.(et al.)1976.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

THERMAL-HYDRAULIC ANALYSIS OF THE SEMISCALE MOD-1 BLOWDOWN HEAT TRANSFER TEST SERIES. (ANCR ; ANCR-NUREG-1287)

THERMAL-HYDRAULIC ANALYSIS OF THE SEMISCALE MOD-1 BLOWDOWN HEAT TRANSFER TEST SERIES. (ANCR ; ANCR-NUREG-1287)
Paper図書
COZZUOL, J.M.1976.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

THERMAL-HYDRAULIC ANALYSIS OF SEMISCALE MOD-1 INTEGRAL BLOWDOWN-REFLOOD TESTS (BASELINE ECC TEST SERIES) (TREE ; TREE-NUREG-1077)

THERMAL-HYDRAULIC ANALYSIS OF SEMISCALE MOD-1 INTEGRAL BLOWDOWN-REFLOOD TESTS (BASELINE ECC TEST SERIES) (TREE ; TREE-NUREG-1077)
Paper図書
COZZUOL, J.M.1977.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

QUICK LOOK REPORT FOR SEMISCALE MOD-3 TEST S-07-3 BASELINE TEST SERIES.:SEMISCALE PROGRAM. (WR ; WR-S-78-017)

QUICK LOOK REPORT FOR SEMISCALE MOD-3 TEST S-07-3 BASELINE TEST SERIES.:SEMISCALE PROGRAM. (WR ; WR-S-78-017)
Paper図書
COZZUOL, J.M.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

INFLUENCE OF STEAM GENERATOR TUBE RUPTURES DURING SEMISCALE LOSS OF COOLANT EXPERIMENTS. (CONF ; CONF-781022-14)

INFLUENCE OF STEAM GENERATOR TUBE RUPTURES DURING SEMISCALE LOSS OF COOLANT EXPERIMENTS. (CONF ; CONF-781022-14)
Paper図書
COZZUOL, J.M.
Other Libraries in Japan
  • Author HeadingCOZZUOL, J.M.

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