You need JavaScript to view this

Transferability of results of PTS experiments to the integrity assessment of reactor pressure vessels

Abstract

The integrity assessment of the reactor pressure vessel (RPV) is based on the fracture mechanics concept as provided in the code. However this concept covers only the linear-elastic fracture mechanics regime on the basis of the reference temperature RT{sub NDT} as derived from charpy impact and drop-weight test. The conservatism of this concept was demonstrated for a variety of different materials covering optimized and lower bound material states with regard to unirradiated and irradiated conditions. For the elastic-plastic regime, methodologies have been developed to describe ductile crack initiation and stable crack growth. The transferability of both, the linear-elastic and elastic-plastic fracture mechanics concept was investigated with the help of large scale specimens focusing on complex loading situations as they result from postulated thermal shock events for the RPV. A series of pressurized thermal shock (PTS) experiments were performed in which the applicability of the fracture mechanics parameters derived from small scale specimen testing could be demonstrated. This includes brittle (static and dynamic) crack initiation and crack arrest in the low charpy energy regime as well as stable crack initiation, stable crack growth and crack arrest in the upper shelf toughness regime. The paper provides the basic material data, the load  More>>
Authors:
Roos, E; Eisele, U; Stumpfrock, L [1] 
  1. MPA Stuttgart (Germany)
Publication Date:
Sep 01, 1997
Product Type:
Technical Report
Report Number:
IWG-LMNPP-96/1; CONF-9705163-
Reference Number:
SCA: 220200; PA: AIX-28:059464; EDB-97:116712; SN: 97001844458
Resource Relation:
Conference: IAEA specialists` meeting on methodology for pressurized thermal shock evaluation, Esztergom (Hungary), 5-8 May 1997; Other Information: PBD: 1997; Related Information: Is Part Of Methodology for pressurized thermal shock evaluation. Proceedings of the IAEA specialists meeting. Working material; PB: 457 p.
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; PRESSURE VESSELS; AGING; LIFETIME; CRACKS; EVALUATION; EXPERIMENTAL DATA; FRACTURE MECHANICS; NUCLEAR POWER PLANTS; THEORETICAL DATA; THERMAL SHOCK
OSTI ID:
519620
Research Organizations:
International Atomic Energy Agency, Vienna (Austria). International Working Group on Life Management of Nuclear Power Plants
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ON: DE97640092; TRN: XA9744644059464
Availability:
INIS; OSTI as DE97640092
Submitting Site:
INIS
Size:
pp. 309-322
Announcement Date:
Sep 23, 1997

Citation Formats

Roos, E, Eisele, U, and Stumpfrock, L. Transferability of results of PTS experiments to the integrity assessment of reactor pressure vessels. IAEA: N. p., 1997. Web.
Roos, E, Eisele, U, & Stumpfrock, L. Transferability of results of PTS experiments to the integrity assessment of reactor pressure vessels. IAEA.
Roos, E, Eisele, U, and Stumpfrock, L. 1997. "Transferability of results of PTS experiments to the integrity assessment of reactor pressure vessels." IAEA.
@misc{etde_519620,
title = {Transferability of results of PTS experiments to the integrity assessment of reactor pressure vessels}
author = {Roos, E, Eisele, U, and Stumpfrock, L}
abstractNote = {The integrity assessment of the reactor pressure vessel (RPV) is based on the fracture mechanics concept as provided in the code. However this concept covers only the linear-elastic fracture mechanics regime on the basis of the reference temperature RT{sub NDT} as derived from charpy impact and drop-weight test. The conservatism of this concept was demonstrated for a variety of different materials covering optimized and lower bound material states with regard to unirradiated and irradiated conditions. For the elastic-plastic regime, methodologies have been developed to describe ductile crack initiation and stable crack growth. The transferability of both, the linear-elastic and elastic-plastic fracture mechanics concept was investigated with the help of large scale specimens focusing on complex loading situations as they result from postulated thermal shock events for the RPV. A series of pressurized thermal shock (PTS) experiments were performed in which the applicability of the fracture mechanics parameters derived from small scale specimen testing could be demonstrated. This includes brittle (static and dynamic) crack initiation and crack arrest in the low charpy energy regime as well as stable crack initiation, stable crack growth and crack arrest in the upper shelf toughness regime. The paper provides the basic material data, the load paths, representative for large complex components as well as experimental and theoretical results of PTS experiments. From these data it can be concluded that the available fracture mechanics concepts can be used to describe the component behavior under transient loading conditions. (author). 26 refs, 12 figs, 1 tab.}
place = {IAEA}
year = {1997}
month = {Sep}
}