The effects of flux on radiation embrittlement of low-copper pressure vessel steels

被引:4
作者
Xu, YC [1 ]
Jia, XJ [1 ]
Zhang, CY [1 ]
Ning, GS [1 ]
Yu, QK [1 ]
机构
[1] China Inst Atom Energy, Nucl Mat Lab, Beijing, Peoples R China
来源
EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM | 2000年 / 1366卷
关键词
reactor pressure vessels; low-copper steels; irradiation; neutron flux; test reactor; surveillance; effective fluence; Charpy V-norch impact; transition temperature shift; matrix defects;
D O I
10.1520/STP12386S
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The effects of neutron flux (E>1MeV) on the radiation embrittlement of the low-copper RPV steels are investigated. Tested materials include the forging matrix (JF) weld (JW) of Japan's SA 508-3 steel as well as the matrix (CF) and weld (CW) of China's domestic RPV steel. JF and CF were irradiated to fluences from 3.2 to 4.9 x 10(23)n/m(2)(E>1MeV) at 280+/-5 degrees C, JW and CW irradiated to fluences of 1.4 and 1.5 x 10(23)n/m(2) at 290+/-5 degrees C, respectively, in the test reactor. JF and JW are also used as surveillance specimens for PWR RPV, and two sets of surveillance data have been acquired. The experimental results indicate that the transition temperature shifts (Delta RTNDT) for JF irradiated in the test reactor are larger than those from surveillance specimens, when these Delta RTNDT are normalized to an effective fluence of 2 x 10(23)n/m(2) (E>1MeV) and an effective temperature of 290 degrees C. This shows notably the influence of neutron flux on Delta RTNDT. The mean Delta RTNDT for CF and CW is about 0.7 times that for JF and JW in terms of the normalized data, which imply the influences of the impurities besides Cu and microstructures on radiation embrittlement of low-copper RPV steels.
引用
收藏
页码:118 / 126
页数:5
相关论文
共 16 条
  • [1] EXPERIMENTAL-EVIDENCE OF SEVERAL CONTRIBUTIONS TO THE RADIATION-DAMAGE IN FERRITIC ALLOYS
    AKAMATSU, M
    VANDUYSEN, JC
    PAREIGE, P
    AUGER, P
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1995, 225 : 192 - 195
  • [2] MICROSTRUCTURAL DEVELOPMENTS IN NEUTRON-IRRADIATED MILD-STEEL SUBMERGED-ARC WELD METAL
    BUSWELL, JT
    BISCHLER, PJE
    FENTON, ST
    WARD, AE
    PHYTHIAN, WJ
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1993, 205 : 198 - 205
  • [3] IRRADIATION-INDUCED MICROSTRUCTURAL CHANGES, AND HARDENING MECHANISMS, IN MODEL PWR REACTOR PRESSURE-VESSEL STEELS
    BUSWELL, JT
    PHYTHIAN, WJ
    MCELROY, RJ
    DUMBILL, S
    RAY, PHN
    MACE, J
    SINCLAIR, RN
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1995, 225 : 196 - 214
  • [4] EASON ED, 1998, NUREGCR6551 NUCL REG
  • [5] HAGGAG FM, 1993, ASTM STP, V1175, P172
  • [6] Recent strategy and progress in Korean nuclear PLIM program
    Hong, SY
    Jeong, IS
    Jin, TE
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1997, 174 (01) : 25 - 32
  • [7] *IAEA, 1986, TECHNICAL REPORTS SE, V265
  • [8] JIA X, 1999, ASTM STP, V1366
  • [9] MOSER P, 1995, MATER SCI FORUM, V175-, P453, DOI 10.4028/www.scientific.net/MSF.175-178.453
  • [10] Odette G.R., 1993, 16 INT S ASTM STP 11, P373