Neutron spectrum effect and damage analysis on pressure vessel steel irradiation behavior

被引:0
作者
Pichon, C [1 ]
Brillaud, C [1 ]
Alberman, A [1 ]
Soulat, P [1 ]
机构
[1] EDF, DE, SEPTEN, F-69628 Villeurbanne, France
来源
PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2 | 1997年
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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
A comprehensive program on pressure vessel irradiation behavior has been carried out by the Commissariat a l'Energie Atomique (CEA) and Electricite de France (EDF) from 1989 until 1995. This program is a key approach to EDF plant life assessment :strategy, It is based on experimental correlations:between pressure vessel steel irradiation behavior with regard to fluences obtained in two very different irradiation spectra specially designed in the OSIRIS and SILOE CEA test reactors. The aims of this program were, to assess a potential neutron spectrum effect in the range met in a Pressurized Water Reactor (PWR) between the vessel (internal surface, 1/4 thickness) and the surveillance capsules and correlatively to define the most appropriate exposure parameter for low alloy steel embrittlement. In order to fulfill this objective, all experimental parameters had to be accurately controlled. New high-capacity irradiation rigs have been therefore developed by the CEA to test two materials in parallel with-a large number of Charpy-V specimens in well-defined conditions (temperature, neutronic environment). Two weld materials were specifically manufactured from low alloy Mn Ni Mo steel. In terms of embrittling elements (Cu, Ni, P), these materials are representative of average and:upper bound chemical compositions found in French nuclear power reactor vessel welds. Target fluences were 0.1 dpa in both reactors, corresponding to 7.10(19) n.cm(-2) (F-E>1MeV) in the OSIRIS standard spectrum and to 4.10(19) n.cm(-2) (F-E>1MeV) in the SILOE "distorted" spectrum. The spectra characteristics were derived both by damage monitor dosimetry and neutron transport calculations. For each material in each state, Charpy-V transition curves were defined. The results in terms of Charpy-V transition shifts and fluences (F-E>1MeV, F-E>0.1MeV and F-dpa) are presented then discussed. In the range considered, no spectrum effect and a vary good correlation using fluence F-E>1MeV were found.
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页码:865 / 870
页数:4
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