CRAWLER-TRANSPORTER CAN MOVE LARGEST NUCLEAR-REACTOR VESSEL

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POWER ENGINEERING | 1976年 / 80卷 / 04期

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中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

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0807 ; 0820 ;

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页码：148 / 148

页数：1

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[21] THE VIABILITY OF THE K1A PROCEDURE FOR PREDICTING THE ARREST OF A CRACK IN A NUCLEAR-REACTOR STEEL PRESSURE-VESSEL
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[23] ANALYSIS OF IMPACT PROPERTIES OF A533 STEEL FOR NUCLEAR-REACTOR PRESSURE-VESSEL BY INSTRUMENTED CHARPY-TEST
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[J]. ENGINEERING FRACTURE MECHANICS, 1984, 19 (01) : 49 - &
[24] PREDICTING CRACK ARREST IN A NUCLEAR-REACTOR PRESSURE-VESSEL DURING A HYPOTHETICAL PRESSURIZED THERMAL-SHOCK EVENT
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[J]. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1990, 42 (02) : 217 - 235
[25] CHANGE IN TOUGHNESS OF NUCLEAR-REACTOR PRESSURE-VESSEL STEEL AND ITS WELD JOINT DUE TO NEUTRON-IRRADIATION
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[J]. TRANSACTIONS OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1983, 23 (02) : B68 - B68
[26] EFFECTS OF NEUTRON-IRRADIATION ON FRACTURE-TOUGHNESS OF HEAVY SECTION STEELS FOR A NUCLEAR-REACTOR PRESSURE-VESSEL
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[J]. TRANSACTIONS OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1983, 23 (08) : B303 - B303
[27] FRACTOGRAPHY IN EVALUATION OF THE MECHANISM OF ENVIRONMENT-SENSITIVE CYCLIC CRACK-GROWTH OF NUCLEAR-REACTOR PRESSURE-VESSEL STEELS
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[J]. ULTRAMICROSCOPY, 1982, 9 (04) : 396 - 397
[28] LOW FLUENCE, 288 DEGREESC (550 DEGREESF) RADIATION ASSESSMENT OF NUCLEAR-REACTOR VESSEL STEELS HAVING VARIABLE COPPER CONTENT
HAWTHORNE, JR
WATSON, HE
[J]. REPORT OF NRL PROGRESS, 1976, (MAR): : 19 - 21
[29] THE DUCTILE-TO-BRITTLE TRANSITION OF FERRITIC STEEL-COMPONENTS - SOME RECENT DEVELOPMENTS IN RELATION TO NUCLEAR-REACTOR PRESSURE-VESSEL INTEGRITY
LIDBURY, DPG
[J]. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1995, 64 (03) : 191 - 197
[30] QUANTITATIVE-EVALUATION OF MICROCRACKS DURING FRACTURE-TOUGHNESS TESTING OF A533B NUCLEAR-REACTOR PRESSURE-VESSEL STEEL
KISHI, T
[J]. TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1985, 71 : 1378 - 1378

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