Estimation of material degradation of VVER-1000 baffle

被引：4

作者：

Harutyunyan, Davit ^{[1
,2
]}

Kost'al, Michal ^{[2
]}

Vandlik, Stanislav ^{[2
]}

Hojna, Anna ^{[2
]}

Schulc, Martin ^{[2
]}

Flibor, Stanislav ^{[2
]}

机构：

[1] Czech Tech Univ, FNSFE, Dept Nucl Reactors, V Holesovickach 2, Prague 8, Czech Republic

[2] Res Ctr Rez Ltd, Husinec Rez 25068 130, Czech Republic

来源：

ICRS-13 & RPSD-2016, 13TH INTERNATIONAL CONFERENCE ON RADIATION SHIELDING & 19TH TOPICAL MEETING OF THE RADIATION PROTECTION AND SHIELDING DIVISION OF THE AMERICAN NUCLEAR SOCIETY - 2016 | 2017年 / 153卷

关键词：

LR-0 RESEARCH REACTOR; MOCK-UP;

D O I：

10.1051/epjconf/201715307019

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：

The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark. Service life extension for another 10 to 30 years is now under investigation. Life extension requires the evaluation of pressure vessel internals degradation under long-term irradiation. One of the possible limiting factors for the service life of VVERs is a void swelling of the Russian type titanium stabilized stainless 08Chl8N1OT steel used to construct the baffle surrounding the core. This article aims to show first steps towards deeper analysis of the baffle degradation process and to demonstrate the possibilities of precise calculation and measurements on the VVER-1000 mock-up in LR-0 reactor.

引用

页数：6

共 50 条

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