UTPF experiment: Tests for cooling of reactor pressure vessels

被引：0
|
作者：
Hertlein, R [1 ]
Dauwel, W [1 ]
机构：
[1] SIEMENS AG,KWU,D-91058 ERLANGEN,GERMANY
来源：
ANNUAL MEETING ON NUCLEAR TECHNOLOGY '96 | 1996年
关键词：
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：98 / 101
页数：4
相关论文
共 50 条
  • [31] Reactor dosimetry in the surveillance program of Kozloduy NPP reactor pressure vessels
    Ilieva, KD
    Belousov, SI
    Apostolov, TG
    Monev, M
    REACTOR DOSIMETRY: RADIATION METROLOGY AND ASSESSMENT, 2001, 1398 : 77 - 84
  • [32] ON FABRICATION OF REACTOR PRESSURE VESSELS AND REACTOR COMPONENTS WITH SPECIAL REGARD TO WELDING
    SUDASCH, E
    BERGMANN.W
    KERNTECHNIK ISOTOPENTECHNIK UND CHEMIE, 1967, 9 (3-4): : 137 - &
  • [33] PRESSURE TESTS ON END SLABS FOR PRESTRESSED CONCRETE PRESSURE VESSELS
    CAMPBELL, D
    LOW, EWE
    NUCLEAR ENGINEERING AND DESIGN, 1967, 6 (04) : 345 - &
  • [34] CYCLIC PRESSURE TESTS OF FULL-SIZE PRESSURE VESSELS
    PICKETT, AG
    GRIGORY, SC
    WELDING RESEARCH COUNCIL BULLETIN, 1968, (135): : 1 - &
  • [35] PROOF PRESSURE TESTS OF THE 1ST REACTOR VESSELS AT HARTLEPOOL AND HEYSHAM NUCLEAR-POWER STATIONS
    FLEISCHER, CC
    KEIL, SG
    PATON, AA
    NUCLEAR ENGINEERING AND DESIGN, 1984, 77 (02) : 181 - 190
  • [36] INTEGRITY OF MAGNOX REACTOR STEEL PRESSURE-VESSELS
    FLEWITT, PEJ
    WILLIAMS, GH
    WRIGHT, MB
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1992, 31 (05): : 383 - 391
  • [37] STEELS FOR COMMERCIAL NUCLEAR POWER REACTOR PRESSURE VESSELS
    STERNE, RH
    STEELE, LE
    NUCLEAR ENGINEERING AND DESIGN, 1969, 10 (03) : 259 - &
  • [38] Research Progress of Steels for Nuclear Reactor Pressure Vessels
    Zhou, Linjun
    Dai, Jie
    Li, Yang
    Dai, Xin
    Xie, Changsheng
    Li, Linze
    Chen, Liansheng
    MATERIALS, 2022, 15 (24)
  • [39] EVALUATION OF TEMPERATURE AND DESIGN OF COOLING SYSTEMS FOR PRESSURE VESSELS
    TURTON, PJ
    HUTCHINS.J
    OLD, RAB
    NUCLEAR ENGINEERING AND DESIGN, 1966, 4 (05) : 503 - &
  • [40] PREDICTING CRACK ARREST IN REACTOR PRESSURE-VESSELS
    SMITH, E
    GRIESBACH, TJ
    NUCLEAR ENGINEERING AND DESIGN, 1992, 137 (03) : 305 - 314
12345