Effects of damage rate on irradiation hardening and post-irradiation annealing characteristics of carbon steel

被引:2
作者
Suzuki, M [1 ]
Idei, Y [1 ]
Kizaki, M [1 ]
Onizawa, K [1 ]
机构
[1] Japan Atom Energy Res Inst, Dept Nucl Safety Res, Tokai, Ibaraki 3191195, Japan
来源
EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM | 1999年 / 1325卷
关键词
irradiation embrittlement; carbon steel; pressure vessel; dose rate effect; Charpy shift; irradiation hardening; ageing; low flux; post-irradiation annealing; recovery;
D O I
10.1520/STP13876S
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Irradiation embrittlement in a low dose region was studied for an aluminium-killed carbon steel from the point of dose rate effects. The dose rate as low as similar to 5x10(8) n/cm(2)/s (E>1MeV) caused a Charpy transition temperature shift of more than 30 degrees C after irradiation to similar to 10(17) n/cm(2) (E>1MeV) at 240 degrees C, while a similar amount of Charpy shift was observed after similar to 10(18) n/cm(2) (E>1MeV) at higher dose rate (similar to 7x10(11) n/cm(2)/s). The effect of dose rate was obvious in the annealing response on hardness. The recovery characteristics indicated that more stable defects were produced in the material irradiated at a lower dose rate.
引用
收藏
页码:379 / 387
页数:9
相关论文
共 8 条
[1]  
DRUCE SG, 1990, ASTM STP, V1046, P30
[2]  
MADER E, 1993, PROCEEDINGS OF THE SIXTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, P739
[3]   ON MECHANISMS BY WHICH A SOFT NEUTRON-SPECTRUM MAY INDUCE ACCELERATED EMBRITTLEMENT [J].
MANSUR, LK ;
FARRELL, K .
JOURNAL OF NUCLEAR MATERIALS, 1990, 170 (03) :236-245
[4]   ACCELERATED NEUTRON EMBRITTLEMENT OF FERRITIC STEELS AT LOW FLUENCE - FLUX AND SPECTRUM EFFECTS [J].
NANSTAD, RK ;
FARRELL, K ;
BRASKI, DN ;
CORWIN, WR .
JOURNAL OF NUCLEAR MATERIALS, 1988, 158 :1-6
[5]  
NANSTAD RK, 1990, ASTM STP, V1046, P5
[6]  
ODETTE GR, 1996, NUREGCP0157, V2, P1
[8]   EFFECTS OF GAMMA-INDUCED DISPLACEMENTS ON HFIR PRESSURE-VESSEL MATERIALS [J].
REMEC, I ;
WANG, JA ;
KAM, FBK ;
FARRELL, K .
JOURNAL OF NUCLEAR MATERIALS, 1994, 217 (03) :258-268