Published 1996 | Version v1
Book Metadata-only

Materials data acquisition and life assessment for BWR reactor pressure vessel

Creators

  • 1. Hitachi Ltd., Ibaraki (Japan)
  • 2. Toshiba Corp., Yokohama (Japan). Nuclear Energy Div.
  • 3. Japan Power Engineering and Inspection Corp., Urayasu, Chiba (Japan)
  • 4. Tokyo Univ., Hongo, Tokyo (Japan). System Engineering Faculty
  • 5. Sophia Univ., Tokyo (Japan)
  • 6. Tokyo Univ., Shinbashi, Tokyo (Japan)

Description

The systematic testing of materials to obtain the data for life assessment on reactor pressure vessel (RPV) of boiling water reactor (BWR) is ongoing. The data of fatigue crack propagation in simulated BWR reactor water and fracture toughness of low alloy steels and nickel base alloys are summarized in this paper. As a case study, fatigue crack propagation and crack stability at the feed water nozzle corner, made of a low alloy steel were evaluated for RPV life assessment. Postulating an 80-year normal operation of an 800 MWe BWR plant, it was predicted that fatigue crack growth would not penetrate through the nozzle corner wall and the nozzle material has enough toughness to prevent unstable fracture

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1226-X
Imprint Title
ICONE-4: Proceedings. Volume 5: Radioactive waste disposal; Decontamination and decommissioning; Aging assessment and license renewals; Global advances in nuclear codes and standards; Major component reliability
Imprint Pagination
525 p.
Journal Page Range
p. 189-195.

Conference

Title
ASME/JSME international conference on nuclear engineering.
Acronym
ICONE 4
Dates
10-13 Mar 1996.
Place
New Orleans, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27074128
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; FRACTURE PROPERTIES; LOW ALLOY STEELS; MECHANICAL PROPERTIES; NICKEL BASE ALLOYS; PRESSURE VESSELS; REACTOR MATERIALS; SERVICE LIFE; STRESS INTENSITY FACTORS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MATERIALS; NICKEL ALLOYS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-960306--.