Published November 2002 | Version v1
Book

Assessment of fuel failure during LOCA

  • 1. Directorate of Reactor Safety Analysis, Nuclear Power Corporation of India Limited, Mumbai (India)

Description

Full text: One of the major design basis accident is loss of coolant accident (LOCA). This accident is characterized by high sheath temperature and rapid depressurization of coolant. One of the ECCS acceptance criteria for this type of accident is for all LOCA events the release of radioactive material from the fuel in the reactor shall be limited such that the calculated radiological consequences at exclusion zone boundary are within acceptable limits for accidents as specified by AERB. The assessment of above criteria requires the estimation of fuel failure. Two phenomena which cause fuel failure during such condition are oxygen embrittlement and clad ballooning. Oxygen embrittlement is assessed by the amount of oxidation. Failure due to ballooning is analysed by calculating stress and strain on the clad and comparing with ultimate burst stress. Failure data generated by analysing these two phenomena are used in assessing damage on fuel. This paper discusses the criteria of fuel failure followed by various regulating agencies or countries along with Indian criteria. This paper also discusses the damage phenomena along with detailed method of assessment of fuel failure during LOCA

Part of:
First national conference on nuclear reactor technology

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
First national conference on nuclear reactor technology
Imprint Pagination
421 p.
Journal Page Range
p. 367-368

Conference

Title
1. nuclear reactor safety
Acronym
NRT-1
Dates
25-27 Nov 2002
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
34011462
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EMBRITTLEMENT; ENVIRONMENTAL EFFECTS; FUEL ELEMENT FAILURE; LOSS OF COOLANT; RISK ASSESSMENT
Descriptors DEC
ACCIDENTS; REACTOR ACCIDENTS

Optional Information