Report of the Spert I Destructive Test Program on an Aluminum, Plate-type, Water-moderated Reactor
Year: 1964
Type: report
Abstract: facility are discussed. The water- moderated core that will be used for these experiments is mounted in the Spert I open-type reactor vessel, which has no provision for pressurization or forced coolant flow. The core is comprised of approximately 600 4%-enriched UO/sub 2/ fuel rods clad with stainless steel, and four blade-type, gang-operated control rods for reactor control. Reactor transients are initiated at ambient temperature by step-insertions of reactivity, using for this purpose a special control rod that can be quickly ejected from the core. On the basis of the results obtained from previous nondestructivelkinetic tests, an analysis was made to determine the nature of the results to be expected for an assumed 1.8- sec- period test in which tetal core destruction occurs. An evaluation of hazards involved in conducting the 1.8-msec test, based on conservative assumptions regarding fission product release and weather conditions, indicated that with the procedural controls normally exercised in the conduct of any transient test at Spert and the special controls to be in effect during the destructive test series, no significant hazard to personnel or to the general public will be incurred. (auth)
DOI: 10.2172/4034065
Authors: R Miller, A Sola, R McCardell
Language: English
Subfield: Nuclear Energy and Engineering
Field: Energy
Domain: Physical Sciences
Open Access status: green
OpenAlex ID: W80963241