Published 1991 | Version v1
Book Metadata-only

Thermal hydraulics work in support of PFBR

Creators

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

Description

This paper aims at a review of some of the important thermal hydraulics work carried out for PFBR design. They include, shape optimization of Inner Vessel, estimation of cooling flow requirement for Main Vessel, identification of suitable location for core monitors, flow and temperature distributions in Control Plug, Grid Plate, IHX and Steam Generator, maximum pressure seen by various components during sodium/water reaction, and plant incident analysis. Besides, this paper briefly describes the Computer codes utilised in these studies. (author)

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
International conference on fast reactors and related fuel cycles
Imprint Pagination
[2900 p.].
Journal Page Range
v. 4 p. 4.14/1-4.14/10.

Conference

Title
International conference on fast reactors and related fuel cycles.
Dates
28 Oct - 1 Nov 1991.
Place
Kyoto (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
24050931
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTER CODES; DESIGN; HEAT EXCHANGERS; HYDRODYNAMICS; LMFBR TYPE REACTORS; PRESSURE DEPENDENCE; REACTOR COMPONENTS; REACTOR VESSELS; STEAM GENERATORS; TEMPERATURE RANGE 0400-1000 K; THERMODYNAMICS
Descriptors DEC
BOILERS; BREEDER REACTORS; CONTAINERS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTORS; TEMPERATURE RANGE; VAPOR GENERATORS

Optional Information

Notes
Imprint:Composed of four volumes.