Published November 2002 | Version v1
Book

Transient analysis for the case of increase in heat removal for advanced heavy water reactor

  • 1. Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)

Description

Full text: Increase in heat removal is one of the categories considered for PIEs for nuclear power reactors. Couple of transients are analysed for the proposed Advanced Heavy Water Reactor to find the effect of increase in heat removal on core thermal-hydraulics. This set of analyses conveys important inputs to the designer and assesses the safety of the proposed reactor in this type of event. A summary of the results is presented

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. 336

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
34011408
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HEAT TRANSFER; HWLWR TYPE REACTORS; HYDRAULICS; REACTOR CORES; REACTOR SAFETY; TRANSIENTS
Descriptors DEC
ENERGY TRANSFER; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; MECHANICS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS

Optional Information