Spent LWR fuel dry storage in large transport and storage casks after extended burnup

被引：19

作者：

Spilker, H

Peehs, M

Dyck, HP

Kaspar, G

Nissen, K

机构：

[1] SIEMENS AG,POWER GENERAT GRP KWU,D-91050 ERLANGEN,GERMANY

[2] GESSEL NUKL ARBEHALTER,ESSEN,GERMANY

来源：

JOURNAL OF NUCLEAR MATERIALS | 1997年 / 250卷 / 01期

关键词：

Creep - Interpolation - Light water reactors - Mathematical models - Nuclear fuel cladding - Spent fuels - Stresses;

D O I：

10.1016/S0022-3115(97)00209-2

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Dry spent LWR fuel storage is licensed for single fuel assemblies with rod burnup to 65 GWd/tHM. This allows dry spent fuel storage of reloads with a batch average up to 55 GWd/tHM. The leading defect mechanism for spent fuel rods in dry storage is hoop strain. Fuel rod degradation can be prevented by limiting creep. Post-pile creep of fuel rod cladding can be described conservatively by the creep of unirradiated cladding. In order to extend the database, internally pressurized creep samples were investigated for time intervals up to 10 000 h. Test temperatures were between 250 and 400 degrees C, and the hoop stresses applied ranged from 80 to 150 N/mm(2). The resulting data were described mathematically by an interpolation formula. Based on the fuel assemblies end-of-life data the maximum CASTOR V cask storage temperature was calculated to be between 348 degrees C and 358 degrees C at the beginning. (C) 1997 Elsevier Science B.V.

引用

页码：63 / 74

页数：12

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