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Table of contents of journal: *Nuclear engineering and design

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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
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