ODS cladding fuel pins irradiation tests using the BOR-60 reactor

被引：13

作者：

Kaito, Takeji ^{[1
]}

Yano, Yasuhide ^{[1
]}

Ohtsuka, Satoshi ^{[1
]}

Inoue, Masaki ^{[1
]}

Tanaka, Kenya ^{[1
]}

Fedoseev, Alexander E. ^{[2
]}

Povstyanko, Alexander V. ^{[2
]}

Novoselov, Andrey ^{[2
]}

机构：

[1] Japan Atom Energy Agcy, Oarai, Ibaraki 3111393, Japan

[2] Joint Stock Co, Res Inst Atom Reactors, Dimitrovgrad 433510, Ulyanovsk Regio, Russia

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 2013年 / 50卷 / 04期

关键词：

FBR; cladding material; ODS; MOX fuel; fuel pin; irradiation; FCCI; BOR-60; FERRITIC STEEL CLADDINGS; NEUTRON-IRRADIATION; MARTENSITIC STEELS; TENSILE PROPERTIES; BOR-60; REACTOR;

D O I：

10.1080/00223131.2013.773165

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：

In order to confirm the irradiation behavior of ODS steels and thus judge their applicability to fuel claddings, fuel pin irradiation tests using 9Cr and 12Cr-ODS claddings developed by JAEA were conducted to burn-up of 11.9 at% and neutron dose of 51 dpa in the BOR-60. Superior properties of the ODS claddings concerning FCCI, dimensional stability under irradiation and so on were confirmed and indicated good application prospects for high burn-up fuel. On the other hand, anomalous irradiation behaviors, fuel pin failure and the microstructure change containing coarse and irregular precipitates, occurred in a part of the fuel pin with 9Cr-ODS cladding. This paper describes evaluation of the obtained irradiation data and the investigation results into the cause of the anomalous irradiation behaviors.

引用

页码：387 / 399

页数：13

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