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Title: ENGINEERING EVALUATION OF A MIXED ALLOY FUEL ELEMENT IRRADIATED AT ELEVATED TEMPERATURES IN THE SRE

Abstract

A fuel material evaluation was made by destructively examining a full- scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/ MTU. The fuel element contained beta-quenched 2.78% enriched unalloyed uranium, in both the cast and rolled forms; powder compacted U --1.2 wt.% Mo; cast U -1.5 wt.% Mo; cast U--2 wt.% Zr; and wrought Th--5.4 wt.% U (5% enriched). The Th-U alloy and the U--1.5 wt.% Mo alloy appeared to be promising fuels, and merit further work. The other U-Mo and U-Zr alloys, and the unalloyed uranium, in both the cast and wrought conditions, showed definite limitations. No significant difference in performance was noted between standard fuel slugs and slugs with intentionally included fabrication defects. Limited metallography, in both the preand postirradiation conditions, failed to show any significant radiation effeot, except for the appearance of voids in the U-2 wt.% Zr. (auth)

Authors:
; ;
Publication Date:
Research Org.:
Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
OSTI Identifier:
4180530
Report Number(s):
NAA-SR-3888
NSA Number:
NSA-14-017043
DOE Contract Number:  
AT-11-1-GEN-8
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 OTHER MATERIALS; ALLOTROPY; CASTING; COMPACTING; DEFECTS; ENRICHMENT; FABRICATION; FORGING; FUEL ELEMENTS; HEAT TREATMENTS; HIGH TEMPERATURE; IRRADIATION; METALLOGRAPHY; MOLYBDENUM ALLOYS; PERFORMANCE; POWDER METALLURGY; RADIATION EFFECTS; RODS; ROLLING; THORIUM ALLOYS; URANIUM; URANIUM ALLOYS; ZIRCONIUM ALLOYS

Citation Formats

Ballif, J L, Hayward, B R, and Walter, J W. ENGINEERING EVALUATION OF A MIXED ALLOY FUEL ELEMENT IRRADIATED AT ELEVATED TEMPERATURES IN THE SRE. United States: N. p., 1960. Web.
Ballif, J L, Hayward, B R, & Walter, J W. ENGINEERING EVALUATION OF A MIXED ALLOY FUEL ELEMENT IRRADIATED AT ELEVATED TEMPERATURES IN THE SRE. United States.
Ballif, J L, Hayward, B R, and Walter, J W. Wed . "ENGINEERING EVALUATION OF A MIXED ALLOY FUEL ELEMENT IRRADIATED AT ELEVATED TEMPERATURES IN THE SRE". United States.
@article{osti_4180530,
title = {ENGINEERING EVALUATION OF A MIXED ALLOY FUEL ELEMENT IRRADIATED AT ELEVATED TEMPERATURES IN THE SRE},
author = {Ballif, J L and Hayward, B R and Walter, J W},
abstractNote = {A fuel material evaluation was made by destructively examining a full- scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/ MTU. The fuel element contained beta-quenched 2.78% enriched unalloyed uranium, in both the cast and rolled forms; powder compacted U --1.2 wt.% Mo; cast U -1.5 wt.% Mo; cast U--2 wt.% Zr; and wrought Th--5.4 wt.% U (5% enriched). The Th-U alloy and the U--1.5 wt.% Mo alloy appeared to be promising fuels, and merit further work. The other U-Mo and U-Zr alloys, and the unalloyed uranium, in both the cast and wrought conditions, showed definite limitations. No significant difference in performance was noted between standard fuel slugs and slugs with intentionally included fabrication defects. Limited metallography, in both the preand postirradiation conditions, failed to show any significant radiation effeot, except for the appearance of voids in the U-2 wt.% Zr. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4180530}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {6}
}

Technical Report:
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