Hardening and microstructure evolution in proton-irradiated model and commercial pressure-vessel steels

被引:1
作者
Was, GS [1 ]
Hash, M
Odette, RG
机构
[1] Univ Michigan, Ann Arbor, MI 48109 USA
[2] Univ Calif Santa Barbara, Santa Barbara, CA 93106 USA
关键词
D O I
10.1080/14786430412331319974
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In an effort to understand the mechanisms of irradiation embrittlement of reactor pressure-vessel steels, hardening and microstructure evolution in a number of simple ferritic model alloys and complex bainitic steels irradiated with 3.2 MeV protons over a range of doses, dose rates and temperatures were characterized. Irradiations were conducted on selected model alloys to 1 dpa, which is a much higher dose than has been explored for neutron irradiations of these materials. Irradiation hardening was determined from Vickers hardness measurements, and the microstructures were characterized using small angle X-ray scattering (SAXS) in selected cases. At low-to-intermediate dose, the hardening trends in the proton-irradiated ferritic alloys without nickel were similar to those under neutron irradiation. Hardening also decreased with the proton irradiation temperature in this case, broadly consistent with neutron irradiation trends, and was generally relatively insensitive to dose rate. Quantitative differences were observed between the proton and neutron irradiations of model alloys and, to a lesser extent, complex steels, containing both copper and nickel. These differences can be rationalized by shifts in the hardening curves to higher dose, due to proton dose rates that are 700 or more times higher than for neutrons. Precipitate sizes in the proton-irradiated alloys generally increase with dose and are qualitatively similar to those observed in neutron-irradiated alloys. However, much larger scattering features were also detected at 1 dpa. All the alloys irradiated to this high dose were remarkably hardened by amounts from 490 to 740 MPa.
引用
收藏
页码:703 / 722
页数:20
相关论文
共 50 条
[21]   POSITRON-ANNIHILATION STUDIES ON NEUTRON-IRRADIATED PRESSURE-VESSEL STEELS [J].
GHAZIWAKILI, K ;
ZIMMERMANN, U ;
BRUNNER, J ;
TIPPING, P ;
WAEBER, WB ;
HEINRICH, F .
PHYSICA STATUS SOLIDI A-APPLIED RESEARCH, 1987, 102 (01) :153-163
[22]   EXPERIENCE WITH NEUTRON-IRRADIATED REACTOR PRESSURE-VESSEL STEELS - A MOSSBAUER STUDY [J].
BRAUER, G ;
MATZ, W ;
FETZER, C .
HYPERFINE INTERACTIONS, 1990, 56 (1-4) :1563-1567
[23]   FATIGUE BEHAVIOR OF PRESSURE-VESSEL STEELS [J].
BARSOM, JM .
WELDING RESEARCH COUNCIL BULLETIN, 1974, (MAY) :1-22
[24]   DEVELOPMENT OF PWR PRESSURE-VESSEL STEELS [J].
DRUCE, SG ;
EDWARDS, BC .
NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1980, 19 (05) :347-360
[25]   RADIATION DAMAGE TO PRESSURE-VESSEL STEELS [J].
WECHSLER, MS .
NUCLEAR SAFETY, 1967, 8 (05) :461-&
[26]   HYDROGEN ATTACK OF PRESSURE-VESSEL STEELS [J].
SHEWMON, PG .
MATERIALS SCIENCE AND TECHNOLOGY, 1985, 1 (01) :2-11
[27]   PRESSURE-VESSEL STEELS - PROMISE AND PROBLEM [J].
GROSS, JH .
METALS ENGINEERING QUARTERLY, 1974, 14 (03) :36-40
[28]   TEMPER EMBRITTLEMENT OF PRESSURE-VESSEL STEELS [J].
SWIFT, RA ;
GULYA, JA .
WELDING JOURNAL, 1973, 52 (02) :S57-S68
[29]   RADIATION HARDENING IN A PRESSURE-VESSEL MILD STEEL [J].
WECHSLER, MS ;
HINKLE, NE .
JOURNAL OF METALS, 1968, 20 (01) :A81-&
[30]   FATIGUE CRACK-PROPAGATION IN NEUTRON-IRRADIATED FERRITIC PRESSURE-VESSEL STEELS [J].
JAMES, LA .
NUCLEAR SAFETY, 1977, 18 (06) :791-801