Published 2006 | Version v1
Book

Evaluation of critical crack length and fracture toughness of pressure tubes using slit burst test method

  • 1. Post Irradiation Examination Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Pressure tubes (PTs) in Pressurized Heavy Water Reactors (PHWRs) operate at high temperature and pressure and undergo progressive embrittlement with increasing EFPY of operation due to synergistic effect of neutrons and hydriding. The embrittlement is manifested in reduction of fracture toughness and thereby lowers the magnitude of critical crack length (CCL) of PT. However, to satisfy Leak Before Break (LBB) criterion for assuring safe PT operation during service, CCL needs to be higher than the specified value. The slit burst test (SBT) along with fracture toughness test using CCT specimens need to be carried out to establish the CCL of the irradiated pressure tube

Part of:
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1
Imprint Pagination
179 p.
Journal Page Range
p. 156

Conference

Title
international conference on advances in nuclear materials processing, performance and phenomena; MBFE 2006: satellite conference on materials behaviour- far from equilibrium
Acronym
ANM 2006
Dates
12-16 Dec 2006
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
50064033
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRACK PROPAGATION; LEAK TESTING; PHWR TYPE REACTORS; PRESSURE TUBES; REACTOR OPERATION; REACTOR SAFETY
Descriptors DEC
HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; OPERATION; REACTOR LIFE CYCLE; REACTORS; SAFETY; TESTING; TUBES

Optional Information

Notes
This record replaces 50063253