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Title: Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark 3 BWR Spent Fuel

Simulation of boiling water reactor (BWR) fuel depletion poses a challenge for nuclide inventory validation and nuclear criticality safety analyses. This challenge is due to the complex operating conditions and assembly design heterogeneities that characterize these nuclear systems. Fuel depletion simulations and in-cask criticality calculations are affected by (1) completeness of design information, (2) variability of operating conditions needed for modeling purposes, and (3) possible modeling choices. These effects must be identified, quantified, and ranked according to their significance. This paper presents an investigation of BWR fuel depletion using a complete set of actual design specifications and detailed operational data available for five operating cycles of the Swedish BWR Forsmark 3 reactor. The data includes detailed axial profiles of power, burnup, and void fraction in a very fine temporal mesh for a GE14 (10×10) fuel assembly. The specifications of this case can be used to assess the impacts of different modeling choices on inventory prediction and in-cask criticality, specifically regarding the key parameters that drive inventory and reactivity throughout fuel burnup. This study focused on the effects of the fidelity with which power history and void fraction distributions are modeled. The corresponding sensitivity of the reactivity in storage configurations ismore » assessed, and the impacts of modeling choices on decay heat and inventory are addressed.« less
Authors:
 [1] ;  [2] ;  [2] ;  [2] ;  [2] ;  [2]
  1. Univ. Politecnica de Madrid (Spain)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
OSTI Identifier:
1223658
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: ICNC 2015 International Cooperation in Nuclear Criticality Safety, Charlotte, NC (United States), 13-17 Sep 2015
Research Org:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
ORNL work for others
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SPENT FUELS; FORSMARK-3 REACTOR; CASKS; SIMULATION; RADIOISOTOPES; INVENTORIES; CRITICALITY; DESIGN; VOID FRACTION; BURNUP; REACTIVITY; SPECIFICATIONS; VALIDATION; FUEL ASSEMBLIES; SAFETY ANALYSIS; AFTER-HEAT; CONFIGURATION; FORECASTING; INFORMATION; SENSITIVITY ANALYSIS; SPENT FUEL STORAGE; POWER DENSITY