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Post-pulse detail metallographic examinations of low-enriched uranium silicide plate-type miniature fuel

Technical Report:

Abstract

Pulse irradiation at Nuclear Safety Research Reactor (NSRR) was performed using low-enriched (19.89 w% {sup 235}U) unirradiated silicide plate-type miniature fuel which had a density of 4.8 gU/cm{sup 3}. Experimental aims are to understand the dimensional stability and to clarify the failure threshold of the silicide plate-type miniature fuel under power transient conditions through post-pulse detail metallographic examinations. A silicide plate-type miniature fuel was loaded into an irradiation capsule and irradiated by a single pulse. Deposited energies given in the experiments were 62, 77, 116 and 154 cal/g{center_dot}fuel, which lead to corresponding peak fuel plate temperatures, 201 {+-} 28degC, 187 {+-} 10degC, 418 {+-} 74degC and 871 {+-} 74degC, respectively. Below 400degC, reliability and dimensional stability of the silicide plate fuel was sustained, and the silicide plate fuel was intact. Up to 540degC, wall-through intergranular crackings occurred in the Al-3%Mg alloy cladding. With the increase of the temperature, the melting of the aluminum cladding followed by recrystallization, the denudation of fuel core and the plate-through intergranular cracking were observed. With the increase of the temperature beyond 400degC, the bowing of fuel plate became significant. Above the temperature of 640degC molten aluminum partially reacted with the fuel core, partially flowed downward  More>>
Authors:
Yanagisawa, Kazuaki [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Oct 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-152
Reference Number:
SCA: 220300; 050700; PA: JPN-91:012172; SN: 92000659206
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; POST-IRRADIATION EXAMINATION; URANIUM SILICIDES; FUEL PLATES; FUEL INTEGRITY; MODERATELY ENRICHED URANIUM; METALLOGRAPHY; FUEL CANS; FUEL ELEMENT FAILURE; THRESHOLD ENERGY; NSRR REACTOR; TEMPERATURE DEPENDENCE; SWELLING; CREEP; 220300; 050700; FUEL ELEMENTS; FUELS PRODUCTION AND PROPERTIES
OSTI ID:
10117381
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768094; TRN: JP9112172
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
205 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Yanagisawa, Kazuaki. Post-pulse detail metallographic examinations of low-enriched uranium silicide plate-type miniature fuel. Japan: N. p., 1991. Web.
Yanagisawa, Kazuaki. Post-pulse detail metallographic examinations of low-enriched uranium silicide plate-type miniature fuel. Japan.
Yanagisawa, Kazuaki. 1991. "Post-pulse detail metallographic examinations of low-enriched uranium silicide plate-type miniature fuel." Japan.
@misc{etde_10117381,
title = {Post-pulse detail metallographic examinations of low-enriched uranium silicide plate-type miniature fuel}
author = {Yanagisawa, Kazuaki}
abstractNote = {Pulse irradiation at Nuclear Safety Research Reactor (NSRR) was performed using low-enriched (19.89 w% {sup 235}U) unirradiated silicide plate-type miniature fuel which had a density of 4.8 gU/cm{sup 3}. Experimental aims are to understand the dimensional stability and to clarify the failure threshold of the silicide plate-type miniature fuel under power transient conditions through post-pulse detail metallographic examinations. A silicide plate-type miniature fuel was loaded into an irradiation capsule and irradiated by a single pulse. Deposited energies given in the experiments were 62, 77, 116 and 154 cal/g{center_dot}fuel, which lead to corresponding peak fuel plate temperatures, 201 {+-} 28degC, 187 {+-} 10degC, 418 {+-} 74degC and 871 {+-} 74degC, respectively. Below 400degC, reliability and dimensional stability of the silicide plate fuel was sustained, and the silicide plate fuel was intact. Up to 540degC, wall-through intergranular crackings occurred in the Al-3%Mg alloy cladding. With the increase of the temperature, the melting of the aluminum cladding followed by recrystallization, the denudation of fuel core and the plate-through intergranular cracking were observed. With the increase of the temperature beyond 400degC, the bowing of fuel plate became significant. Above the temperature of 640degC molten aluminum partially reacted with the fuel core, partially flowed downward under the influence of surface tension and gravity, and partially formed agglomerations. Judging from these experimental observations, the fuel-plate above 400degC tends to reduce its dimensional stability. Despite of the apparent silicide fuel-plate failure, neither generation of pressure pulse nor that of mechanical energy occurred at all. (J.P.N.).}
place = {Japan}
year = {1991}
month = {Oct}
}