Master Curve and Unified Curve applicability to highly neutron irradiated Western type reactor pressure vessel steels

被引：22
|
作者：
Zurbuchen, Conrad [1 ]
Viehrig, Hans-Werner [1 ]
Weiss, Frank-Peter
机构：
[1] Dresden Rossendorf eV, Res Ctr, Inst Safety Res, Dept Mat & Component Safety, D-01314 Dresden, Germany
来源：
NUCLEAR ENGINEERING AND DESIGN | 2009年 / 239卷 / 07期
关键词：
FRACTURE-TOUGHNESS PREDICTION; PROBABILISTIC MODEL; RPV STEELS; DEPENDENCE;
D O I：
10.1016/j.nucengdes.2009.03.008
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：
While the Master Curve (MC) method is gradually entering brittle fracture safety assessment procedures world-wide, knowledge is still lacking about its limits of applicability to highly neutron irradiated material. In this paper two reactor pressure vessel (RPV) steels A533B CIA (IAEA reference material code JRQ) and A508 Cl.3 (code JFL) were scrutinized for possible deviations of the postulated invariant MC shape and the MC validity for macroscopically inhomogeneous microstructure. Besides tensile and Charpy-V tests, MC tests were performed on Charpy-size three-point bend specimens in the unirradiated, neutron irradiated with fluences up to nearly 10(20) n/cm(2) (E > 1 MeV) and recovery heat treated condition. Evaluation procedures include Master Curve reference temperature T(0) determination according to ASTM E1921-05 as well as additional analysis methods such as SINTAP, multi-modal MC method (MML) and the Unified Curve (UC). Integrity assessment according to ASME Code Cases N-629 and N-631 has been applied. It is shown that the standard MC concept provides a precise description of the fracture toughness for all conditions, even exceptionally well for the highly irradiated state. No MC shape change could be observed, whereas the UC concept indicates a significant influence of irradiation on the fracture toughness curves for the highly irradiated JRQ. (C) 2009 Elsevier B.V. All rights reserved.
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收藏
页码：1246 / 1253
页数：8
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