Experimental Program to Monitor the Irradiation Induced Embrittlement of the French Reactor Pressure Vessel Steels

Author:

Chas Guillaume1,Rupa Nathalie2,Bourgoin Josseline2,Hotellier Astrid1,Saillet Se´bastien3

Affiliation:

1. EDF Generation and Trading, Avoine, France

2. EDF Generation and Trading, Saint-Denis Cedex, France

3. EDF R&D, Moret Sur Loing, France

Abstract

By monitoring the irradiation-induced embrittlement of materials, the Pressure Vessel Surveillance Program (PVSP) contributes to the RPV integrity and lifetime assessments. This program is implemented on each PWR Unit in France; it is mainly based on Charpy tests, which are widely used in the nuclear industry to characterize the mechanical properties of the materials. Moreover, toughness tests are also carried out to check the conservatism of the PVSP methodology. This paper first describes the procedure followed for the Pressure Vessel Surveillance Program. It presents the irradiation capsules: the samples materials (low alloy Mn, Ni, Mo vessel steel including base metals, heat affected zones, welds and a reference material) and the mechanical tests performed. Then it draws up a synthesis of the analysis of about 180 capsules removed from the reactors at fluence levels up to 7.1019 n/cm2 (E > 1 MeV). This database gathers the results of more than 10,000 Charpy tests and 250 toughness tests. The experimental results confirm the conservatism of the Code-based methodology applied to the toughness assessment.

Publisher

ASMEDC

Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Warm PreStress effect on highly irradiated reactor pressure vessel steel;Journal of Nuclear Materials;2015-09

2. Embrittlement of reactor pressure vessels (RPVs) in pressurized water reactors (PWRs);Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants;2015

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