Results: 1-25/345
Authors:
MORIMOTO K
SATAKE K
ARAKI Y
MORIMURA K
TANAKA M
SHIMIZU N
IWAHASHI Y
Citation: K. Morimoto et al., APPLICATION OF NUMERICAL-ANALYSIS TECHNIQUES TO EDDY-CURRENT TESTING FOR STEAM-GENERATOR TUBES, Nuclear Engineering and Design, 153(1), 1994, pp. 1-9
Authors:
SAITO T
AKASAKA M
MAEKAWA O
KANAZAWA Y
MATSUMURA K
TAKAHASHI Y
UOZUMI H
Citation: T. Saito et al., DESIGN IMPROVEMENT OF WELD DESIGN OF THE REACTOR INTERNAL CIRCULATIONPUMP MOTOR CASING TO THE REACTOR PRESSURE-VESSEL NOZZLE, Nuclear Engineering and Design, 153(1), 1994, pp. 11-18
Authors:
SAKAI K
HOJO K
KATO A
UMEHARA R
Citation: K. Sakai et al., ONLINE FATIGUE-MONITORING SYSTEM FOR NUCLEAR-POWER-PLANT, Nuclear Engineering and Design, 153(1), 1994, pp. 19-25
Authors:
ITATANI M
FUKAKURA J
ASANO M
KIKUCHI M
CHUJO N
Citation: M. Itatani et al., FATIGUE-CRACK GROWTH-BEHAVIOR OF WELD HEAT-AFFECTED ZONE OF TYPE-304 STAINLESS-STEEL IN HIGH-TEMPERATURE WATER, Nuclear Engineering and Design, 153(1), 1994, pp. 27-34
Authors:
NAKATA K
SHIMANUKI S
ANZAI H
KUNIYA J
Citation: K. Nakata et al., INTERGRANULAR STRESS-CORROSION CRACKING SUSCEPTIBILITY OF SENSITIZED TYPE-304 STEEL IN 561 K PURE WATER UNDER GAMMA-RAY IRRADIATION, Nuclear Engineering and Design, 153(1), 1994, pp. 35-41
Authors:
YAMAUCHI K
HATTORI S
SHINDO T
KUNIYA J
Citation: K. Yamauchi et al., METHODOLOGY FOR FORMULATING PREDICTIONS OF STRESS-CORROSION CRACKING LIFE, Nuclear Engineering and Design, 153(1), 1994, pp. 43-55
Authors:
MIURA N
FUJIOKA T
KASHIMA K
KANNO S
HAYASHI M
ISHIWATA M
GOTOH N
Citation: N. Miura et al., LOW-CYCLE FATIGUE AND DUCTILE FRACTURE FOR JAPANESE CARBON-STEEL PIPING UNDER DYNAMIC LOADINGS, Nuclear Engineering and Design, 153(1), 1994, pp. 57-69
Authors:
SHIBATA K
ISOZAKI T
UEDA S
KURIHARA R
ONIZAWA K
KOHSAKA A
Citation: K. Shibata et al., RESULTS OF RELIABILITY TEST PROGRAM ON LIGHT-WATER REACTOR PIPING, Nuclear Engineering and Design, 153(1), 1994, pp. 71-86
Authors:
SUGIURA T
ISHIKAWA A
NAKAMURA T
ASADA Y
Citation: T. Sugiura et al., FORMULATION OF AIR ENVIRONMENTAL-EFFECT ON CREEP-FATIGUE INTERACTION, Nuclear Engineering and Design, 153(1), 1994, pp. 87-95
Authors:
AOTO K
KOMINE R
UENO F
KAWASAKI H
WADA Y
Citation: K. Aoto et al., CREEP-FATIGUE EVALUATION OF NORMALIZED AND TEMPERED MODIFIED 9CR-1MO, Nuclear Engineering and Design, 153(1), 1994, pp. 97-110
Authors:
KATAHIRA F
HIRANO K
TANAKA Y
YOSHIDA K
KURIBAYASHI M
UMEMOTO T
Citation: F. Katahira et al., SURFACE MELTING TECHNIQUE OF SMALL-DIAMETER STAINLESS-STEEL PIPE BY MEANS OF YTTRIUM-ALUMINUM-GARNET LASER, Nuclear Engineering and Design, 153(1), 1994, pp. 111-116
Authors:
ASADA Y
Citation: Y. Asada, EXTENDED AND UPDATED SELECTED PAPERS FROM THE 6TH GERMAN-JAPANESE JOINT SEMINAR, STUTTGART, GERMANY, AUGUST 11 AND 12, 1993 - PREFACE, Nuclear Engineering and Design, 153(1), 1994, pp. 180000009-180000009
Authors:
LIDBURY DPG
SHERRY AH
BILBY BA
HOWARD IC
LI ZH
ERIPRET C
Citation: Dpg. Lidbury et al., PREDICTION OF THE FIRST SPINNING CYLINDER TEST USING CONTINUUM DAMAGEMECHANICS, Nuclear Engineering and Design, 152(1-3), 1994, pp. 1-10
Authors:
ERIPRET C
ROUSSELIER G
Citation: C. Eripret et G. Rousselier, FIRST SPINNING CYLINDER TEST ANALYSIS USING A LOCAL APPROACH TO FRACTURE, Nuclear Engineering and Design, 152(1-3), 1994, pp. 11-18
Authors:
SIEVERS J
BASS BR
Citation: J. Sievers et Br. Bass, COMPARATIVE-ASSESSMENT OF PROJECT FALSIRE - RESULTS, Nuclear Engineering and Design, 152(1-3), 1994, pp. 19-37
Authors:
WRIGHT DJ
SHARPLES JK
SHERRY AH
GARDNER L
Citation: Dj. Wright et al., EFFECT OF BIAXIAL LOADING ON THE FRACTURE-BEHAVIOR OF A FERRITIC STEEL-COMPONENT, Nuclear Engineering and Design, 152(1-3), 1994, pp. 39-55
Authors:
POOLE AB
CLINARD JA
BATTISTE RL
HENDRICH WR
Citation: Ab. Poole et al., FRACTURE-MECHANICS AND FULL-SCALE PIPE BREAK TESTING FOR THE DEPARTMENT-OF-ENERGY NEW PRODUCTION REACTOR HEAVY-WATER REACTOR, Nuclear Engineering and Design, 152(1-3), 1994, pp. 57-65
Authors:
WATKINS JC
STEELE R
DEWALL KG
WEIDENHAMER GH
ROTHBERG OO
Citation: Jc. Watkins et al., NRC TEST-RESULTS AND OPERATIONS EXPERIENCE PROVIDE INSIGHTS FOR A NEWGATE VALVE STEM FORCE CORRELATION, Nuclear Engineering and Design, 152(1-3), 1994, pp. 67-78
Authors:
JHUNG MJ
PARK KB
HWANG WG
Citation: Mj. Jhung et al., DYNAMIC-RESPONSE OF REACTOR INTERNALS TO PIPE BREAKS, Nuclear Engineering and Design, 152(1-3), 1994, pp. 79-90
Authors:
BERGER FP
IJAZ A
Citation: Fp. Berger et A. Ijaz, LOADING OF TUBULAR FILTERS IN AGR, Nuclear Engineering and Design, 152(1-3), 1994, pp. 91-101
Authors:
TANG Y
Citation: Y. Tang, ROCKING RESPONSE OF TANKS CONTAINING 2 LIQUIDS, Nuclear Engineering and Design, 152(1-3), 1994, pp. 103-115
Authors:
GUPTA AK
MEGAHED HA
Citation: Ak. Gupta et Ha. Megahed, 2 METHODS FOR SEISMIC ANALYSIS OF NONCLASSICALLY DAMPED SYSTEMS, Nuclear Engineering and Design, 152(1-3), 1994, pp. 117-120
Authors:
KAWAI M
Citation: M. Kawai, A COMPARATIVE-STUDY OF ANISOTROPIC CREEP THEORIES, Nuclear Engineering and Design, 152(1-3), 1994, pp. 121-133
Authors:
TING K
CHANG CS
CHANG KK
Citation: K. Ting et al., ALTERNATING METHOD APPLIED TO ANALYZE MODE-III FRACTURE PROBLEMS WITHMULTIPLE CRACKS IN AN INFINITE DOMAIN, Nuclear Engineering and Design, 152(1-3), 1994, pp. 135-145
Authors:
GOLLER B
Citation: B. Goller, PROTECTION AGAINST MISSILES DUE TO A FAILING PWR PRESSURE-VESSEL, Nuclear Engineering and Design, 152(1-3), 1994, pp. 147-157