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VENTING OF NONCONDENSIBLE GAS FROM THE UPPER HEAD OF A B AND W REACTOR VESSEL USING HOT LEG U-BEND VENT VALVES. (NUREG ; NUREG-CR-4488)

VENTING OF NONCONDENSIBLE GAS FROM THE UPPER HEAD OF A B AND W REACTOR VESSEL USING HOT LEG U-BEND VENT VALVES. (NUREG ; NUREG-CR-4488)
Paper図書
WATERMAN, M.E.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
Other Libraries in Japan
  • Author HeadingWATERMAN, M.E.

Venting of noncondensible gas from the upper head of a B&W reactor vessel using hot leg u-bend vent valves. (NUREG ; NUREG/CR-4489; EGG-2436)

Venting of noncondensible gas from the upper head of a B&W reactor vessel using hot leg u-bend vent valves. (NUREG ; NUREG/CR-4489; EGG-2436)
Paper図書
Waterman, M.E./Kullberg, C.M./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
Other Libraries in Japan
  • Author HeadingWaterman, M.E. Kullberg, C.M. and others

Overview of TRAC-PD2 assessment calculations. (NUREG ; NUREG/CR-4195; EGG-2380)

Overview of TRAC-PD2 assessment calculations. (NUREG ; NUREG/CR-4195; EGG-2380)
Paper図書
Waterman, M.E.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan
  • Author HeadingWaterman, M.E.

VENTING OF NONCONDENSIBLE GAS FROM THE UPPER HEAD OF B AND W REACTOR VESSEL USING HOT LEG U-BEND VENT VALVES. (EGG ; EGG-RST-7006)

VENTING OF NONCONDENSIBLE GAS FROM THE UPPER HEAD OF B AND W REACTOR VESSEL USING HOT LEG U-BEND VENT VALVES. (EGG ; EGG-RST-7006)
Paper図書
WATERMAN, M.E.EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan
  • Author HeadingWATERMAN, M.E.

EFFECTS OF CONTROL SYSTEM FAILURES ON TRANSIENTS AND ACCIDENTS AT A 3-LOOP WESTINGHOUSE PRESSURIZED WATER REACTOR. MAIN REPORT. VOLUME 1 (EGG ; EGG--2405-VOL.1)

EFFECTS OF CONTROL SYSTEM FAILURES ON TRANSIENTS AND ACCIDENTS AT A 3-LOOP WESTINGHOUSE PRESSURIZED WATER REACTOR. MAIN REPORT. VOLUME 1 (EGG ; EGG--2405-VOL.1)
Paper図書
EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan

EFFECTS OF CONTROL SYSTEM FAILURES ON TRANSIENTS AND ACCIDENTS AT A 3-LOOP WESTINGHOUSE PRESSURIZED WATER REACTOR. VOLUME 2. APPENDICES (EGG ; EGG--2405-VOL.2)

EFFECTS OF CONTROL SYSTEM FAILURES ON TRANSIENTS AND ACCIDENTS AT A 3-LOOP WESTINGHOUSE PRESSURIZED WATER REACTOR. VOLUME 2. APPENDICES (EGG ; EGG--2405-VOL.2)
Paper図書
EG and G Idaho, Inc.(EG and G Idaho, Inc.)1985.
Other Libraries in Japan

RELAP5 THERMAL-HYDRAULIC ANALYSES OF OVERCOOLING SEQUENCES IN A PRESSURIZED WATER REACTOR (CONF ; CONF-840914-21)

RELAP5 THERMAL-HYDRAULIC ANALYSES OF OVERCOOLING SEQUENCES IN A PRESSURIZED WATER REACTOR (CONF ; CONF-840914-21)
Paper図書
1984.
Other Libraries in Japan

RELAP5 ANALYSES OF OVERCOOLING TRANSIENTS IN A PRESSURIZED WATER REACTOR (CONF ; CONF-830901-10)

RELAP5 ANALYSES OF OVERCOOLING TRANSIENTS IN A PRESSURIZED WATER REACTOR (CONF ; CONF-830901-10)
Paper図書
1983.
Other Libraries in Japan

Loss-of coolant accident test series-results of TC-1 tests. (NUREG ; NUREG/CR-1827; EGG-2072)

Loss-of coolant accident test series-results of TC-1 tests. (NUREG ; NUREG/CR-1827; EGG-2072)
Paper図書
Yackle, T.R./Waterman, M.E./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1981.
Other Libraries in Japan
  • Author HeadingYackle, T.R. Waterman, M.E. and others

PBF-LOCA TEST SERIES: TEST LOC-5 EXPERIMENT PREDICTIONS. (TFBP ; TFBP-TR-332)

PBF-LOCA TEST SERIES: TEST LOC-5 EXPERIMENT PREDICTIONS. (TFBP ; TFBP-TR-332)
Paper図書
WATERMAN, M.E.(et al.)1979.
Other Libraries in Japan
  • Author HeadingWATERMAN, M.E.

Corrected and updated data for IFA-429 from beginning of life through June 1978 (NUREG ; NUREG/CR-0478; TREE-1269)

Corrected and updated data for IFA-429 from beginning of life through June 1978 (NUREG ; NUREG/CR-0478; TREE-1269)
Paper図書
Waterman, M.E.Idaho National Engineering Lab.1978.12.
Other Libraries in Japan
  • Author HeadingWaterman, M.E.

Fuel rod temperature and pressure response in Halden reactor experiment IFA-226 (NUREG ; NUREG/CR-0267; TREE-1238; TRN: 79-001044)

Fuel rod temperature and pressure response in Halden reactor experiment IFA-226 (NUREG ; NUREG/CR-0267; TREE-1238; TRN: 79-001044)
Paper図書
MacDonald, P.E., Owen, D.E., Waterman, M.E.Idaho National Engineering Lab.1978.8.
Other Libraries in Japan
  • Author HeadingMacDonald, P.E. Owen, D.E. Waterman, M.E.

CORRECTED AND UPDATED DATA FOR IFA-429 FROM BEGINNING OF LIFE THROUGH JUNE 1978. (TREE ; TREE-1269; NUREG/CR-0478)

CORRECTED AND UPDATED DATA FOR IFA-429 FROM BEGINNING OF LIFE THROUGH JUNE 1978. (TREE ; TREE-1269; NUREG/CR-0478)
Paper図書
WATERMAN, M.E.1978.
Other Libraries in Japan
  • Author HeadingWATERMAN, M.E.

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