The actual properties of WWER-440 reactor pressure vessel materials obtained by impact tests of subsize specimens fabricated out of samples taken from the RPV

被引：3

作者：

Korolev, YN ^{[1
]}

Kryukov, AM ^{[1
]}

Nikolaev, YA ^{[1
]}

Platonov, PA ^{[1
]}

Shtrombakh, YI ^{[1
]}

Langer, R ^{[1
]}

Leitz, C ^{[1
]}

Rieg, CY ^{[1
]}

机构：

[1] IV Kurchatov Atom Energy Inst, ORM, Russian Res Ctr, Moscow 123182, Russia

来源：

SMALL SPECIMEN TEST TECHNIQUES | 1998年 / 1329卷

关键词：

reactor pressure vessel; radiation embrittlement; subsize impact test; ductile-to-brittle transition temperature; post irradiation annealing;

D O I：

10.1520/STP37989S

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：

This paper presents the results of a study on degradation due to irradiation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subsize Charpy specimens (5x5x27.5 mm(3)). An application of subsize specimens for estimation of irradiation embrittlement of RPV steel has been substantiated. Comparison between ductile-to-brittle transition temperatures (DBTT) for full-size and subsize Charpy specimens has been carried out. The relation between these two values has been clarified. The results of testing trepans and templates cut out from WWER-440 reactor pressure vessels are considered. The main results of the program TACIS-91/1.1. are discussed.

引用

页码：145 / 159

页数：15