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Bodette, D.E.; Naegeli, R.E.
Sandia National Labs., Albuquerque, NM (United States). Funding organisation: USDOE, Washington, DC (United States)1997
Sandia National Labs., Albuquerque, NM (United States). Funding organisation: USDOE, Washington, DC (United States)1997
AbstractAbstract
[en] This document presents the criticality safety analysis for a new fuel storage rack to support modification of the Annular Core Research Reactor for production of molybdenum-99 at Sandia National Laboratories, Technical Area V facilities. Criticality calculations with the MCNP code investigated various contingencies for the criticality control parameters. Important contingencies included mix of fuel element types stored, water density due to air bubbles or water level for the over-moderated racks, interaction with existing fuel storage racks and fuel storage holsters in the fuel storage pool, neutron absorption of planned rack design and materials, and criticality changes due to manufacturing tolerances or damage. Some limitations or restrictions on use of the new fuel storage rack for storage operations were developed through the criticality analysis and are required to meet the double contingency requirements of criticality safety. As shown in the analysis, this system will remain subcritical under all credible upset conditions. Administrative controls are necessary for loading, moving, and handling the storage rack as well as for control of operations around it. 21 refs., 16 figs., 4 tabs
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Source
Oct 1997; 72 p; CONTRACT AC04-94AL85000; Also available from OSTI as DE98000964; NTIS; US Govt. Printing Office Dep
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Report
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ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, MECHANICAL STRUCTURES, MIXED SPECTRUM REACTORS, PULSED REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, SUPPORTS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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