Published 1989 | Version v1
Book Metadata-only

Behavior of the prestressed concepts pressure vessel of the HTR-500 at severe accident temperatures

Creators

  • 1. Institut fur Nukleare Sichergeitsforschung der Kernforschungsaniage, Julich GmBH, Julich (Germany, F.R.)

Description

For the risk of medium-sized high temperature reactors with PCRV the behavior of the vessel during a hypothetical core heat-up accident is decisive. Tests up to extremely high severe accident temperatures with representative models are carried out. The results of these tests are presented

Additional details

Publishing Information

Publisher
American Association for Structural Mechanics in Reactor Technology.
Imprint Place
Los Angeles, CA (USA)
ISBN
0-9623306-0-4
Imprint Title
Transactions of the 10th international conference on structural mechanics in reactor technology
Imprint Pagination
257 p.
Series
Concrete structures.
Journal Page Range
p. 119-124.

Conference

Title
10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
Dates
14-18 Aug 1989.
Place
Anaheim, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21076243
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HIGH TEMPERATURE; HTR REACTOR; MATHEMATICAL MODELS; PRESTRESSED CONCRETE; REACTOR ACCIDENTS; REACTOR VESSELS; TEMPERATURE DEPENDENCE; THERMODYNAMIC PROPERTIES
Descriptors DEC
ACCIDENTS; BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; PHYSICAL PROPERTIES; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-890855--.