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          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC ContractorsValidation of SCALE for High Temperature Gas-Cooled Reactor Analysis (NUREG/CR-7107)

On this page: Publication Information AbstractDownload complete document NUREG/CR-7107 (PDF - 8.96 MB)Publication Information **Manuscript Completed:** November 2012**Date Published:** July 2012 **Prepared by:** Germina Ilas Dan Ilas Ryan P. Kelly Eva E. Sunny Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6170 Don Algama, NRC Project Manager NRC Job Code N6842 **Prepared for**: Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 R. Sullivan, NRC Technical Lead Availability Notice Abstract This report documents verification and validation studies carried out to assess the performance of the SCALE code system methods and nuclear data for modeling and analysis of High Temperature Gas-Cooled Reactor (HTGR) configurations. Validation data were available from the *International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE Handbook)*, prepared by the International Reactor Physics Experiment Evaluation Project, for two different HTGR designs: prismatic and pebble bed. SCALE models have been developed for HTTR, a prismatic fuel design reactor operated in Japan and HTR-10, a pebble bed reactor operated in China. The models were based on benchmark specifications included in the 2009, 2010, and 2011 releases of the *IRPhE Handbook*. SCALE models for the HTR-PROTEUS pebble bed configuration at the PROTEUS critical facility in Switzerland have also been developed, based on benchmark specifications included in a 2009 IRPhE draft benchmark. The development of the SCALE models has involved a series of investigations to identify particular issues associated with modeling the physics of HTGRs and to understand and quantify the effect of particular modeling assumptions on calculation-to-experiment comparisons. 
      
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