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Investigation of irradiation embrittlement and annealing behaviour of JRQ pressure vessel steel by instrumented impact tests

Abstract

Seven series of A533-B type pressure vessel steel specimens irradiated as well as irradiated - annealed - re-irradiated to different fast neutron fluences (up to 5.10{sup 19}/cm{sup 2}) have been tested with a new type of instrumented impact test machine. The radiation embrittlement and the effect of the intermediate annealing was assessed by using the ductile and cleavage fracture initiation toughness. Although the ductile fracture initiation toughness exhibited scatter, the transition temperature shift corresponding to the dynamic cleavage fracture initiation agreed well with the 41 J Charpy-V shift. The results indicate that annealing is beneficial in restoring mechanical properties in an irradiated nuclear pressure vessel steel. (authors). 8 refs., 11 figs., 1 tab.
Authors:
Valo, M; Rintamaa, R; Nevalainen, M; Wallin, K; Torronen, K; [1]  Tipping, P [2] 
  1. Technical Research Centre of Finland, Espoo (Finland)
  2. Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Publication Date:
Dec 31, 1993
Product Type:
Conference
Report Number:
NEA-CSNI-R-94-1; CONF-9309237-
Reference Number:
SCA: 360106; 360103; 210200; PA: AIX-28:029684; EDB-97:055562; SN: 97001764681
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; IMPACT TESTS; PHYSICAL RADIATION EFFECTS; STEELS; ANNEALING; CLEAVAGE; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; FRACTURE PROPERTIES; MITIGATION; NEUTRON FLUENCE; REACTOR MONITORING SYSTEMS; TRANSITION TEMPERATURE
OSTI ID:
455782
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: XN9600159029684
Availability:
INIS; OSTI as DE97620233
Submitting Site:
INIS
Size:
pp. 1-13
Announcement Date:
Apr 18, 1997

Citation Formats

Valo, M, Rintamaa, R, Nevalainen, M, Wallin, K, Torronen, K, and Tipping, P. Investigation of irradiation embrittlement and annealing behaviour of JRQ pressure vessel steel by instrumented impact tests. NEA: N. p., 1993. Web.
Valo, M, Rintamaa, R, Nevalainen, M, Wallin, K, Torronen, K, & Tipping, P. Investigation of irradiation embrittlement and annealing behaviour of JRQ pressure vessel steel by instrumented impact tests. NEA.
Valo, M, Rintamaa, R, Nevalainen, M, Wallin, K, Torronen, K, and Tipping, P. 1993. "Investigation of irradiation embrittlement and annealing behaviour of JRQ pressure vessel steel by instrumented impact tests." NEA.
@misc{etde_455782,
title = {Investigation of irradiation embrittlement and annealing behaviour of JRQ pressure vessel steel by instrumented impact tests}
author = {Valo, M, Rintamaa, R, Nevalainen, M, Wallin, K, Torronen, K, and Tipping, P}
abstractNote = {Seven series of A533-B type pressure vessel steel specimens irradiated as well as irradiated - annealed - re-irradiated to different fast neutron fluences (up to 5.10{sup 19}/cm{sup 2}) have been tested with a new type of instrumented impact test machine. The radiation embrittlement and the effect of the intermediate annealing was assessed by using the ductile and cleavage fracture initiation toughness. Although the ductile fracture initiation toughness exhibited scatter, the transition temperature shift corresponding to the dynamic cleavage fracture initiation agreed well with the 41 J Charpy-V shift. The results indicate that annealing is beneficial in restoring mechanical properties in an irradiated nuclear pressure vessel steel. (authors). 8 refs., 11 figs., 1 tab.}
place = {NEA}
year = {1993}
month = {Dec}
}