Published May 1991 | Version v1
Report Open

An explication of the graphite structural design code of core support components for the High Temperature Engineering Test Reactor

Creators

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

Description

The integrity evaluation of the core support graphite components for the High Temperature Engineering Test Reactor (HTTR) will be carried out based upon the Graphite Structural Design Code for core support components. In the application of this design code, it is necessary to clear the basic concept to evaluate the core support components of HTTR. Therefore, considering the detailed design of core support graphite structures of HTTR, this report explicates the design code in detail about the concepts of stress limit, fatigue limit, other special stress limit and integrity evaluation of oxidized graphite components etc.. (author)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
37 p.
Report number
JAERI-M--91-070

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
22077729
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
EVALUATION; FATIGUE; GRAPHITE; HTTR REACTOR; OXIDATION; REACTOR CORES; REACTOR SAFETY; SPECIFICATIONS; STRESS ANALYSIS; SUPPORTS
Descriptors DEC
CARBON; CHEMICAL REACTIONS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; NONMETALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY