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Overview of French activities on neutron radiation embrittlement of pressure vessel steel

Abstract

This paper describes recent developments in France`s pressure vessel surveillance program, particularly aimed at assessing the irradiation-caused embrittlement of EDF`s PWRs. The first part presents surveillance program results for base metal, weld metal and heat-affected zones for 74 capsules removed from 34 units. Fluence ranges from 0.3.10{sup 19} n.cm{sup -2} to 5.5.10{sup 19} n.cm{sup -2}. The second part considers research and development activities in this area: these include the metallurgical structure effects of segregated bands on mechanical properties and the embrittlement rate under irradiation, as well as the effect of irradiation parameters such as flux and neutron spectrum on irradiation embrittlement, and more especially to obtain the best damage assessment. (authors). 14 refs., 5 figs., 1 tab.
Authors:
Brillaud, C; [1]  Keroulas, F de; [2]  Pichon, C; [3]  Teissier, A [4] 
  1. Electricite de France (EDF), 37 - Tours (France)
  2. Electricite de France (EDF), 93 - Saint-Denis (France)
  3. Electricite de France (EDF), 69 - Villeurbanne (France)
  4. Electricite de France (EDF), 92 - Courbevoie (France). Service Etudes et Projets Thermiques et Nucleaires
Publication Date:
Dec 31, 1993
Product Type:
Conference
Report Number:
NEA-CSNI-R-94-1; CONF-9309237-
Reference Number:
SCA: 360106; 210200; PA: AIX-28:029660; EDB-97:055539; SN: 97001764657
Resource Relation:
Conference: International Atomic Energy Agency (IAEA) specialist meeting on irradiation embrittlement and optimization of annealing, Paris (France), 20-23 Sep 1993; Other Information: PBD: 1993; Related Information: Is Part Of Irradiation embrittlement and optimisation of annealing; PB: 292 p.
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FRANCE; PWR TYPE REACTORS; DAMAGING NEUTRON FLUENCE; EMBRITTLEMENT; PRESSURE VESSELS; ELECTRICITE DE FRANCE; FRACTURE MECHANICS; IN-SERVICE INSPECTION; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; REACTOR MAINTENANCE; RESEARCH PROGRAMS; SEGREGATION; STEELS; WELDED JOINTS
OSTI ID:
455758
Research Organizations:
Nuclear Energy Agency, 75 - Paris (France). Committee on the Safety of Nuclear Installations
Country of Origin:
NEA
Language:
English
Other Identifying Numbers:
Other: ON: DE97620233; TRN: XN9600135029660
Availability:
INIS; OSTI as DE97620233
Submitting Site:
INIS
Size:
pp. 2-9
Announcement Date:

Citation Formats

Brillaud, C, Keroulas, F de, Pichon, C, and Teissier, A. Overview of French activities on neutron radiation embrittlement of pressure vessel steel. NEA: N. p., 1993. Web.
Brillaud, C, Keroulas, F de, Pichon, C, & Teissier, A. Overview of French activities on neutron radiation embrittlement of pressure vessel steel. NEA.
Brillaud, C, Keroulas, F de, Pichon, C, and Teissier, A. 1993. "Overview of French activities on neutron radiation embrittlement of pressure vessel steel." NEA.
@misc{etde_455758,
title = {Overview of French activities on neutron radiation embrittlement of pressure vessel steel}
author = {Brillaud, C, Keroulas, F de, Pichon, C, and Teissier, A}
abstractNote = {This paper describes recent developments in France`s pressure vessel surveillance program, particularly aimed at assessing the irradiation-caused embrittlement of EDF`s PWRs. The first part presents surveillance program results for base metal, weld metal and heat-affected zones for 74 capsules removed from 34 units. Fluence ranges from 0.3.10{sup 19} n.cm{sup -2} to 5.5.10{sup 19} n.cm{sup -2}. The second part considers research and development activities in this area: these include the metallurgical structure effects of segregated bands on mechanical properties and the embrittlement rate under irradiation, as well as the effect of irradiation parameters such as flux and neutron spectrum on irradiation embrittlement, and more especially to obtain the best damage assessment. (authors). 14 refs., 5 figs., 1 tab.}
place = {NEA}
year = {1993}
month = {Dec}
}