Published 1990 | Version v1
Journal article Metadata-only

Mathematical model of graphite fuel element abrasion during their motion in the HTGR reactor core

Creators

Description

A general solution of the problem on graphite spherical fuel element abrasion during their motion in the HTGR reactor core, is considered. It is believed that the material cut under tangential strain effect appears to be the main mechanism of wear. The expression for evaluating the relative change of a fuel element weight with regard to the assigned number of contact spots, is derived. It is determined that the relative weight loss of a single fuel element in the VG-400 reactor will make up 0.04x10-3

Additional details

Additional titles

Original title (Russian)
Математическая модель истирания графитовых твэлов при их движении в активной зоне ВТГР

Publishing Information

Journal Title
Voprosy Atomnoj Nauki i Tekhniki. Seriya, Yadernaya Tekhnika i Tekhnologiya
Journal Issue
no.6
Series
Vopr. At. Nauki Tekh., Ser. Yad. Tekh. Tekhnol.
ISSN
0321-3099

INIS

Country of Publication
Russian Federation
Country of Input or Organization
USSR
INIS RN
23067952
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ABRASION; ALGORITHMS; FRICTION; FUEL ELEMENTS; NUMERICAL SOLUTION; SPHERICAL CONFIGURATION; STRAINS; VG-400 REACTOR
Descriptors DEC
CONFIGURATION; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; PEBBLE BED REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS