Published 1996 | Version v1
Book Metadata-only

Thermal hydraulic design in support of PFBR

Creators

  • 1. Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Nuclear Systems Div.

Description

An overview of important thermal hydraulic works carried out during the past 4 years, towards the design of 500 MWe, liquid sodium cooled fast breeder reactor (PFBR) is presented. It includes 2D analysis of natural convection in narrow vertical annular penetrations in the roof slab, 2D analysis of radiation, conduction and natural convection interaction in multiple enclosures formed in the reactor assembly, 3D analysis of grid plate and steam generator and 1D transient analysis including core, hot and cold pools, decay heat exchanger and sodium to air heat exchanger during the process of safety grade decay heat removal. It also includes estimation of design basis accident, due to sodium-water reaction

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1226-X
Imprint Title
ICONE-4: Proceedings. Volume 1 -- Part B: Basic technological advances
Imprint Pagination
564 p.
Journal Page Range
p. 581-589.

Conference

Title
ASME/JSME international conference on nuclear engineering.
Acronym
ICONE 4
Dates
10-13 Mar 1996.
Place
New Orleans, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27068810
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANNULAR SPACE; DESIGN; DESIGN BASIS ACCIDENTS; FBR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; ONE-DIMENSIONAL CALCULATIONS; REACTOR COMPONENTS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; CONFIGURATION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; REACTOR ACCIDENTS; REACTORS

Optional Information

Secondary number(s)
CONF-960306--.