Temperature-shift of void swelling observed in annealed Fe-18Cr-10Ni-Ti stainless steel irradiated in the reflector region of BOR-60

被引：16

作者：

Neustroev, VS ^{[1
]}

Shamardin, VK ^{[1
]}

Ostrovsky, ZE ^{[1
]}

Pecherin, AM ^{[1
]}

Garner, FA ^{[1
]}

机构：

[1] Res Inst Atom Reactors, Dimitrovgrad, Russia

来源：

EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM | 2000年 / 1366卷

关键词：

stainless steels; swelling; pressurized water reactors; fast reactors;

D O I：

10.1520/STP12432S

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Evidence has been provided to support the "temperature-shift'' concept of swelling. The swelling of annealed X18H10T stainless steel in the BOR-60 fast reactor at PWR-relevant dpa rates was found to be higher than predicted by a swelling equation developed from data obtained at dpa rates almost an order of magnitude higher. These data were derived from identical hexagonal wrappers irradiated in both in-core and reflector positions. Based on these results, irradiation in PWRs would yield higher swelling to lower temperatures than would occur in core regions of fast reactors.

引用

页码：792 / 800

页数：3

共 11 条

[1]

Garner F. A., 1994, Transactions of the American Nuclear Society, V71, P190

[2]

Garner F.A., 1994, MAT SCI TECHNOLOGY A, V10, P419

[3] Irradiation creep and void swelling of austenitic stainless steels at low displacement rates in light water energy systems [J].