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Title: IMPROVED FUEL ELEMENTS FOR GAS-COOLED, GRAPHITE-MODERATED, NATURAL URANIUM REACTORS: THE GRAPHITE-CORED ELEMENT.

Authors:
; ; ;
Publication Date:
Research Org.:
and others; Commissariat a l'Energie Atomique, Cadarache (France). Centre d'Etudes Nucleaires
OSTI Identifier:
4754114
Alternate Identifier(s):
OSTI ID: 4754114
Report Number(s):
A/CONF.49/P--608; CONF-710901--405
NSA Number:
NSA-25-054091
Resource Type:
Technical Report
Resource Relation:
Other Information: Prepared for 4th international conference on the peaceful uses of atomic energy; Geneva, Switzerland (6 Sep 1971). UNCL. Orig. Receipt Date: 31-DEC-71
Country of Publication:
Country unknown/Code not available
Language:
English
Subject:
N38150* --Power Reactor Development--Fuels; FUEL ELEMENTS; GAS COOLED REACTORS; PERFORMANCE; TUBES; URANIUM ALLOYS REACTORS, GAS-COOLED/fuel elements of, performance uranium tube; REACTOR FUEL ELEMENTS/performance of uranium alloy tube, in gas cooled reactors

Citation Formats

Faussat, A., Millet, P., Ollier, H., and Peray, R. IMPROVED FUEL ELEMENTS FOR GAS-COOLED, GRAPHITE-MODERATED, NATURAL URANIUM REACTORS: THE GRAPHITE-CORED ELEMENT.. Country unknown/Code not available: N. p., 1971. Web.
Faussat, A., Millet, P., Ollier, H., & Peray, R. IMPROVED FUEL ELEMENTS FOR GAS-COOLED, GRAPHITE-MODERATED, NATURAL URANIUM REACTORS: THE GRAPHITE-CORED ELEMENT.. Country unknown/Code not available.
Faussat, A., Millet, P., Ollier, H., and Peray, R. Fri . "IMPROVED FUEL ELEMENTS FOR GAS-COOLED, GRAPHITE-MODERATED, NATURAL URANIUM REACTORS: THE GRAPHITE-CORED ELEMENT.". Country unknown/Code not available.
@article{osti_4754114,
title = {IMPROVED FUEL ELEMENTS FOR GAS-COOLED, GRAPHITE-MODERATED, NATURAL URANIUM REACTORS: THE GRAPHITE-CORED ELEMENT.},
author = {Faussat, A. and Millet, P. and Ollier, H. and Peray, R.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {Country unknown/Code not available},
year = {1971},
month = {1}
}

Technical Report:
Other availability
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