Published August 2001 | Version v1
Report Metadata-only

Loss of coolant accident analysis for pressurized heavy water reactor

Creators

Description

This safety guide on Loss of Coolant Accident Analysis (LOCA) for Pressurised Heavy Water Reactor addresses issues related to LOCA analysis and provides necessary guidelines for developers and users of computer codes for the analysis. It highlights the requirements and considerations that need to be incorporated in the methodology to enhance regulatory confidence in the assumptions of initial conditions, boundary conditions, modelling and computer codes' validity for achievement of end objectives. It is recognised that modelling for LOCA analysis is still an evolving field and is a subject of research and development

Availability note (English)

Available from Atomic Energy Regulatory Board, Mumbai 400094 (IN)

Additional details

Publishing Information

Imprint Pagination
87 p.
Report number
AERB-SG-D--18

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
33070581
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COMPUTER CODES; FUNCTIONAL MODELS; HEALTH HAZARDS; HUMAN POPULATIONS; LOSS OF COOLANT; PHWR TYPE REACTORS; PRIMARY COOLANT CIRCUITS; RADIATION PROTECTION; RECOMMENDATIONS; REGULATORY GUIDES; SAFETY ANALYSIS; VALIDATION
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; DOCUMENT TYPES; ENERGY SYSTEMS; HAZARDS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; POPULATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING

Optional Information

Notes
47 refs., 1 fig., 3 tabs., 4 ills.