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Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983
Author(s) -
W.C. Patrick,
T.R. Butkovich,
Ron Carlson,
W. B. Durham,
H C Ganow,
G.L. Hage,
Ernest L. Majer,
D.N. Montan,
R.A. Nyholm,
N.L. Rector
Publication year - 1984
Language(s) - English
Resource type - Reports
DOI - 10.2172/59308
Subject(s) - spent nuclear fuel , environmental science , test site , calibration , radioactive waste , interim , nuclear engineering , engineering , waste management , mining engineering , archaeology , geography , physics , quantum mechanics
The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables

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