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Studies on the behavior of graphite structures irradiated in the Dragon Reactor. Dragon Project report

Abstract

Design data for the physical and mechanical property changes which occur in graphite structural and fuel body components irradiated in an HTR are largely obtained from small specimens tested in the laboratory and in materials test reactors. A brief data summary is given. This graphite physics data can be used to predict dimensional changes, internal stress generation and strength changes in the graphite materials of HTR fuel elements irradiated in the Dragon Reactor. In this paper, the results which have been obtained from post-irradiation examination of a number of fuel pins, are compared with prediction.
Publication Date:
Nov 15, 1971
Product Type:
Technical Report
Report Number:
DP-Report-769
Reference Number:
NSA-32-027244
Resource Relation:
Conference: CEGB/Institute of Mechanical Engineers Meeting on Graphite Structures for Nuclear Reactors, London (United Kingdom), Mar 1972
Subject:
N77300* -Reactors-Power Reactors, Non-breeding, Graphite Moderated; 210300* -Nuclear Power Plants-Power Reactors, Non- Breeding, Graphite Moderated; FUEL ELEMENTS; PHYSICAL RADIATION EFFECTS; GRAPHITE; HTGR TYPE REACTORS; CREEP; DATA; DRAGON REACTOR; FATIGUE; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES
Sponsoring Organizations:
OECD High Temperature Reactor Project Dragon
OSTI ID:
4953761
Research Organizations:
UKAEA Reactor Group, Winfrith. Atomic Energy Establishment (United Kingdom)
Country of Origin:
United Kingdom
Language:
English
Submitting Site:
GB
Size:
28 p.
Announcement Date:
Dec 31, 1975

Citation Formats

Everett, M. R., Graham, L. W., and Ridealgh, F. Studies on the behavior of graphite structures irradiated in the Dragon Reactor. Dragon Project report. United Kingdom: N. p., 1971. Web.
Everett, M. R., Graham, L. W., & Ridealgh, F. Studies on the behavior of graphite structures irradiated in the Dragon Reactor. Dragon Project report. United Kingdom.
Everett, M. R., Graham, L. W., and Ridealgh, F. 1971. "Studies on the behavior of graphite structures irradiated in the Dragon Reactor. Dragon Project report." United Kingdom.
@misc{etde_4953761,
title = {Studies on the behavior of graphite structures irradiated in the Dragon Reactor. Dragon Project report}
author = {Everett, M. R., Graham, L. W., and Ridealgh, F.}
abstractNote = {Design data for the physical and mechanical property changes which occur in graphite structural and fuel body components irradiated in an HTR are largely obtained from small specimens tested in the laboratory and in materials test reactors. A brief data summary is given. This graphite physics data can be used to predict dimensional changes, internal stress generation and strength changes in the graphite materials of HTR fuel elements irradiated in the Dragon Reactor. In this paper, the results which have been obtained from post-irradiation examination of a number of fuel pins, are compared with prediction.}
place = {United Kingdom}
year = {1971}
month = {Nov}
}