Published 1986 | Version v1
Book Metadata-only

Thermal hydraulic characteristics in reactor vessel of pool-type fast breeder reactor

Creators

  • 1. Central Research Inst. of Electric Power Industry, Tokyo (Japan)

Description

A feasibility study has been conducted to evaluate the feasibility of a large pool-type fast-breeder reactor (FBR) under Japanese seismic and safety design conditions. The objective of the study was to establish original reactor structure designs which meet these conditions. The investigative results of the thermal hydraulic tests are described here for some structure designs including the original. The investigation was performed with the assistance of the Mitsubishi Heavy Industries, Ltd. (author)

Additional details

Publishing Information

Publisher
Atomic Energy Soc. of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
Imprint Pagination
1191 p.
Journal Page Range
p. 5/61-5/70.

Conference

Title
2. international topical meeting on nuclear power plant thermal hydraulics and operations.
Dates
15-17 Apr 1986.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
18061930
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLOW MODELS; HEAT EXCHANGERS; HYDRAULICS; LMFBR TYPE REACTORS; PUMPS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; REYNOLDS NUMBER; STEADY-STATE CONDITIONS; TEMPERATURE DEPENDENCE; THERMODYNAMICS
Descriptors DEC
BREEDER REACTORS; CONTAINERS; COOLING SYSTEMS; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; REACTOR COMPONENTS; REACTORS