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Title: Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor

This study describes a new method utilizing the Dancoff factor to model a non-standard TRISO fuel form characteristic of the AHTR reactor design concept for depletion analysis using the TRITON sequence of SCALE and the validation of this method by code-to-code comparisons. The fuel used in AHTR has the TRISO particles concentrated along the edges of a slab fuel element. This particular geometry prevented the use of a standard DOUBLEHET treatment, previously developed in SCALE to handle NGNP-designed fuel. The new method permits fuel depletion on complicated geometries that traditionally can be handled only by continuous energy based depletion code systems. The method was initially tested on a fuel design typical of the NGNP, where the DOUBLEHET treatment is available. A more comprehensive study was performed using the VESTA code that uses the continuous energy MCNP5 code as a transport solver and ORIGEN2.2 code for depletion calculations. Comparisons of the results indicate good agreement of whole core characteristics, such as the multiplication factor, and the isotopics, including their spatial distribution. Key isotopes analyzed included 235U, 239Pu, 240Pu and 241Pu. The results from this study indicate that the Dancoff factor method can generate estimates of core characteristics with reasonable precision formore » scoping studies of configurations where the DOUBLEHET treatment is unavailable.« less
Authors:
 [1] ;  [2]
  1. Texas A&M University
  2. ORNL
Publication Date:
OSTI Identifier:
1039231
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2012, Knoxville, TN, USA, 20120415, 20120420
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; ACCURACY; DESIGN; FUEL ELEMENTS; GEOMETRY; MULTIPLICATION FACTORS; SPATIAL DISTRIBUTION; TRANSPORT; VALIDATION; VERIFICATION; SCALE; VESTA; AHTR; salt cooled reactors; TRISO fuel