IN-REACTOR CREEP OF HELIUM-PRESSURIZED 304L STAINLESS-STEEL TUBE

被引:31
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WALTERS, LC
WALTER, CM
PUGACZ, MA
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10.1016/0022-3115(72)90147-X
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T [工业技术];
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08 ;
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页码:133 / &
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共 14 条
[1]  
BEMENT AL, 1970, 2 INT C STRENGTH MET, V11, P693
[2]   UNIAXIAL IN-REACTOR CREEP OF ZIRCONIUM ALLOYS [J].
FIDLERIS, V .
JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) :51-&
[3]  
GARNER FA, 1971, P INT C RADIATION IN
[4]   IN-REACTOR CREEP OF ZR-2.5 AT PERCENT NB [J].
GILBERT, ER .
JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) :105-&
[5]   AN ANALYSIS OF FAST NEUTRON EFFECTS ON VOID FORMATION AND CREEP IN METALS [J].
HARKNESS, SD ;
TESK, JA ;
LI, CY .
NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 9 (01) :24-&
[6]  
KATTCHEE, 1965, IDO28595 USAEC RES D
[7]   RADIATION-ENHANCED RELAXATION IN ZIRCALOY-4 AND ZR/2.5 WT PERCENT NB/0.5 WT PERCENT CU ALLOYS [J].
KREYNS, PH ;
BURKART, MW .
JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) :87-&
[8]  
LI C, 1970, STP484 ASTM, P347
[9]  
MCELROY WN, 1970, BNWL1402 US
[10]  
Mosedale D., 1969, Nature, V224, P1301, DOI 10.1038/2241301b0