Published October 1969 | Version v1
Report Restricted

H.T.R. Fuel Element Design

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Description

In this report four designs of prismatic fuel pin suitable for use in H.T.R, power reactors are described and their relative thermal performance in a fully and continuously gagged core with a gas outlet temperature of 800°C is compared. The stresses arising in fuel pins are described and the nature of the change in these stresses during irradiation is discussed. Attention is drawn to the importance of the material properties and their variation with irradiation dose and particularly to the need for defining the properties of the fuel matrix. (author)

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Additional details

Publishing Information

Imprint Pagination
28 p.
Report number
DP-R--672

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54049098
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPARATIVE EVALUATIONS; DESIGN; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; FUEL PINS; HTGR TYPE REACTORS; IRRADIATION; NUCLEAR FUELS; PERFORMANCE; POWER REACTORS; RADIATION DOSES
Descriptors DEC
DEVELOPED COUNTRIES; DOSES; ENERGY SOURCES; EUROPE; EVALUATION; FUEL ELEMENTS; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; WESTERN EUROPE

Optional Information

Notes
Document from Juelich Preservation Project; 15 figs., 2 tabs.