Published September 2011 | Version v1
Report Metadata-only

Evaluation of Ni-based alloy PWSCC integrity evaluation method

Creators

  • 1. Japan Nuclear Energy Safety Organization, Nuclear Energy System Safety Division, Tokyo (Japan)

Description

Estimation procedure for Stress corrosion crack (SCC) growth for the weld joint of main coolant piping system and its fracture assessment procedure are standardized in a part of JSME Codes Rules on fitness -for- Service for Nuclear Power Plants. Utilities apply the code for the integrity assessment of flawed pipe welds detected at periodical inspections. Recently, a deep and short crack of SCC has been found in the outlet nozzle and safe-end weld joint in the reactor vessel of a domestic PWR. The objective of this project is to verify the crack growth estimation method for the deep and short (high aspect ratio) crack in the Nickel based alloy weld metal. In the fiscal year of 2010, program outline of this project has been planned with a review of previous study results relating SCC crack growth evaluation. (author)

Part of:
Annual safety research report, JFY 2010

Additional details

Publishing Information

Imprint Title
Annual safety research report, JFY 2010
Imprint Pagination
444 p.
Journal Page Range
p. 211-214
Report number
JNES-RE--2011-0001

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
51066815
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COOLANT LOOPS; CRACK PROPAGATION; CRACKING; NICKEL BASE ALLOYS; PIPES; PWR TYPE REACTORS; STRESS CORROSION; STRESS INTENSITY FACTORS; WELDED JOINTS
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; DECOMPOSITION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; JOINTS; NICKEL ALLOYS; POWER REACTORS; PYROLYSIS; REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs., 3 figs., 2 tabs.; This record replaces 46091741