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Title: THE MANUFACTURE OF THE GRAPHITE-URANIA FUEL MATRIX FOR TREAT. Final Report--Metallurgy Program 7.6.9

Abstract

The fabrication of the graphite-urania fuel blocks to be used in the Transient Reactor Test is described. A flowsheet of the fabrication process and an evaluation of the fabricated blocks are presented. (C.J.G.)

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab., Lemont, Ill.
Sponsoring Org.:
USDOE
OSTI Identifier:
4180580
Report Number(s):
ANL-5963
NSA Number:
NSA-14-010763
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND MATERIALS; DISPERSIONS; FABRICATION; FUEL ELEMENTS; GRAPHITE; MATERIALS TESTING; RESEARCH REACTORS; TRANSIENTS; TREAT; URANIUM DIOXIDE

Citation Formats

Handwerk, J.H., and Lied, R.C. THE MANUFACTURE OF THE GRAPHITE-URANIA FUEL MATRIX FOR TREAT. Final Report--Metallurgy Program 7.6.9. United States: N. p., 1960. Web. doi:10.2172/4180580.
Handwerk, J.H., & Lied, R.C. THE MANUFACTURE OF THE GRAPHITE-URANIA FUEL MATRIX FOR TREAT. Final Report--Metallurgy Program 7.6.9. United States. doi:10.2172/4180580.
Handwerk, J.H., and Lied, R.C. Fri . "THE MANUFACTURE OF THE GRAPHITE-URANIA FUEL MATRIX FOR TREAT. Final Report--Metallurgy Program 7.6.9". United States. doi:10.2172/4180580. https://www.osti.gov/servlets/purl/4180580.
@article{osti_4180580,
title = {THE MANUFACTURE OF THE GRAPHITE-URANIA FUEL MATRIX FOR TREAT. Final Report--Metallurgy Program 7.6.9},
author = {Handwerk, J.H. and Lied, R.C.},
abstractNote = {The fabrication of the graphite-urania fuel blocks to be used in the Transient Reactor Test is described. A flowsheet of the fabrication process and an evaluation of the fabricated blocks are presented. (C.J.G.)},
doi = {10.2172/4180580},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {1}
}