Published 2002 | Version v1
Book Metadata-only

Pre-service leakage test of HTR-10 primary pressure boundary

Creators

  • 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology

Description

no abstract available

Part of:
The 13th pacific basin nuclear conference. Abstracts

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
7-5022-2682-6
Imprint Title
The 13th pacific basin nuclear conference. Abstracts
Imprint Pagination
347 p.
Journal Page Range
p. 95

Conference

Title
13. pacific basin nuclear conference
Dates
21-25 Oct 2002
Place
Shenzhen (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
34083937
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
BOUNDARY LAYERS; DESIGN; HTR-10 REACTOR; INSTALLATION; LEAK TESTING; PNEUMATICS; PRIMARY COOLANT CIRCUITS
Descriptors DEC
COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; LAYERS; MECHANICS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TEST REACTORS; TESTING

Optional Information