Published November 1990 | Version v1
Journal article Metadata-only

Thermal and hydraulic tests of standard fuel rod of HTTR with HENDEL

Creators

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

no abstract available

Availability note (English)

Available from DOI: https://doi.org/10.3327/jaesj.32.1107

Additional details

Additional titles

Original title (Japanese)
HENDELによるHTTR用標準燃料棒の伝熱流動試験

Identifiers

DOI
10.3327/jaesj.32.1107;

Publishing Information

Journal Title
Nippon Genshiryoku Gakkai-Shi
Journal Volume
32
Journal Issue
11
Journal Page Range
p. 1107-1110
ISSN
0004-7120

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
54033990
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
No Abstract
Descriptors DEI
CONVECTION; FRICTION; FUEL RODS; HELIUM; HTTR REACTOR; HYDRAULICS; HYDRODYNAMICS; REACTOR EXPERIMENTAL FACILITIES; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; THERMODYNAMICS
Descriptors DEC
ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID MECHANICS; FLUIDS; FUEL ELEMENTS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HEAT TRANSFER; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MASS TRANSFER; MECHANICS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE

Optional Information

Notes
This record replaces 22035036