Published June 1979 | Version v1
Book Metadata-only

Simplified analytical model and some results for HTGR core seismic behavior

Creators

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

Description

This paper describes the development of simplified modelings in seismic behavior of the high temperature gas-cooled reactor (HTGR) core consisting of graphite blocks. For the simplified model, one degree-of-freedom mass with nonlinear column characteristics is used instead of the stacked column. The results of the simplified model are compared with those of experiment and detailed model. The results are in good agreement with the latter two. (author)

Additional details

Publishing Information

Publisher
JAERI.
Imprint Place
Tokai, Ibaraki
Imprint Title
Proceedings of the second U.S.-Japan seminar on HTGR safety technology, 2
Imprint Pagination
411 p.
Journal Page Range
p. 340-349.

Conference

Title
2. U.S.-Japan seminar on HTGR safety technology.
Dates
22 - 25 Nov 1978.
Place
Tokyo; Fuji, Shizuoka, Japan.

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
11570438
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DAMPING; FREQUENCY DEPENDENCE; GRAPHITE; HTGR TYPE REACTORS; MATHEMATICAL MODELS; MECHANICAL VIBRATIONS; NONLINEAR PROBLEMS; REACTOR CORES; SEISMIC EFFECTS
Descriptors DEC
CARBON; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; NONMETALS; REACTOR COMPONENTS; REACTORS