Published January 1986 | Version v1
Report Open

Spent fuel behavior under abnormal thermal transients during dry storage

Description

This study was performed to determine the effects of abnormally high temperatures on spent fuel behavior. Prior to testing, calculations using the CIRFI3 code were used to determine the steady-state fuel and cask component temperatures. The TRUMP code was used to determine transient heating rates under postulated abnormal events during which convection cooling of the cask surfaces was obstructed by a debris bed covering the cask. The peak rate of temperature rise during the first 6 h was calculated to be about 150C/h, followed by a rate of about 10C/h. A Turkey Point spent fuel rod segment was heated to approx. 8000C. The segment deformed uniformly with an average strain of 17% at failure and a local strain of 60%. Pretest characterization of the spent fuel consisted of visual examination, profilometry, eddy-current examination, gamma scanning, fission gas collection, void volume measurement, fission gas analysis, hydrogen analysis of the cladding, burnup analysis, cladding metallography, and fuel ceramography. Post-test characterization showed that the failure was a pinhole cladding breach. The results of the tests showed that spent fuel temperatures in excess of 7000C are required to produce a cladding breach in fuel rods pressurized to 500 psing (3.45 MPa) under postulated abnormal thermal transient cask conditions. The pinhole cladding breach that developed would be too small to compromise the confinement of spent fuel particles during an abnormal event or after normal cooling conditions are restored. This behavior is similar to that found in other slow ramp tests with irradiated and nonirradiated rod sections and nonirradiated whole rods under conditions that bracketed postulated abnormal heating rates. This similarity is attributed to annealing of the irradiation-strengthened Zircaloy cladding during heating. In both cases, the failure was a benign, ductile pinhole rupture

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE86007480.

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Additional details

Publishing Information

Imprint Pagination
38 p.
Report number
PNL--5456

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17065201
Subject category
S42: ENGINEERING;
Descriptors DEI
DEFORMATION; DRY STORAGE; SAFETY; SPENT FUEL ELEMENTS; TEMPERATURE DEPENDENCE; THERMAL DEGRADATION; VERY HIGH TEMPERATURE
Descriptors DEC
FUEL ELEMENTS; REACTOR COMPONENTS; STORAGE

Optional Information

Notes
Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted.