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The irradiation embrittlement of two pressure vessel steels -Contribution of local approach

Abstract

Within the IAEA Coordinated Research Programme on ``Optimizing the Reactor Pressure Vessel Surveillance Programmes and their Analyses``, the French participation has been focused on the contribution of the local approach to the determination of the sensitivity to radiation embrittlement of two different pressure vessel steels: a low sensitive French forging steel (FFA) and a high sensitive ``monitor`` Japanese plate steel (JRQ) were irradiated to a fluence of 3.10{sup 19} n/cm{sup 2} at 290 C. The irradiation embrittlement of the two steels measured by the shift of Charpy V transition curves is in good agreement with the estimated shifts given by theoretical prediction. The fracture toughness properties were examined at low temperature with brittle fracture, and at service temperature (290 C), with ductile tearing. The values of K{sub 1C} or K{sub JC} for the brittle fracture and J{sub 1C} for the ductile fracture are compared to predictions established using the local approach of cleavage fracture (Weibull analysis) and the critical rate of void growth respectively. 8 refs., 14 figs., 10 tabs.
Authors:
Soulat, P; Marini, B; [1]  Miannay, D; Horowitz, H; [2]  Schill, R [3] 
  1. CEA Centre d`Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service de Recherches Metallurgiques Appliquees
  2. CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire
  3. CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie
Publication Date:
Dec 31, 1993
Product Type:
Conference
Report Number:
NEA-CSNI-R-94-1; CONF-9309237-
Reference Number:
SCA: 360106; 210200; PA: AIX-28:029662; EDB-97:055545; SN: 97001764659
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; PRESSURE VESSELS; EMBRITTLEMENT; STEELS; FRACTURE PROPERTIES; PHYSICAL RADIATION EFFECTS; CLEAVAGE; DAMAGING NEUTRON FLUENCE; DUCTILE-BRITTLE TRANSITIONS; DUCTILITY; FRACTURE MECHANICS; FRANCE; RUPTURES; STATISTICAL MODELS; TEMPERATURE DEPENDENCE; TRANSITION TEMPERATURE
OSTI ID:
455760
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: XN9600137029662
Availability:
INIS; OSTI as DE97620233
Submitting Site:
INIS
Size:
pp. 1-16
Announcement Date:
Apr 18, 1997

Citation Formats

Soulat, P, Marini, B, Miannay, D, Horowitz, H, and Schill, R. The irradiation embrittlement of two pressure vessel steels -Contribution of local approach. NEA: N. p., 1993. Web.
Soulat, P, Marini, B, Miannay, D, Horowitz, H, & Schill, R. The irradiation embrittlement of two pressure vessel steels -Contribution of local approach. NEA.
Soulat, P, Marini, B, Miannay, D, Horowitz, H, and Schill, R. 1993. "The irradiation embrittlement of two pressure vessel steels -Contribution of local approach." NEA.
@misc{etde_455760,
title = {The irradiation embrittlement of two pressure vessel steels -Contribution of local approach}
author = {Soulat, P, Marini, B, Miannay, D, Horowitz, H, and Schill, R}
abstractNote = {Within the IAEA Coordinated Research Programme on ``Optimizing the Reactor Pressure Vessel Surveillance Programmes and their Analyses``, the French participation has been focused on the contribution of the local approach to the determination of the sensitivity to radiation embrittlement of two different pressure vessel steels: a low sensitive French forging steel (FFA) and a high sensitive ``monitor`` Japanese plate steel (JRQ) were irradiated to a fluence of 3.10{sup 19} n/cm{sup 2} at 290 C. The irradiation embrittlement of the two steels measured by the shift of Charpy V transition curves is in good agreement with the estimated shifts given by theoretical prediction. The fracture toughness properties were examined at low temperature with brittle fracture, and at service temperature (290 C), with ductile tearing. The values of K{sub 1C} or K{sub JC} for the brittle fracture and J{sub 1C} for the ductile fracture are compared to predictions established using the local approach of cleavage fracture (Weibull analysis) and the critical rate of void growth respectively. 8 refs., 14 figs., 10 tabs.}
place = {NEA}
year = {1993}
month = {Dec}
}