Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit
Oak Ridge National Laboratory (ORNL) and the US Nuclear Regulatory Commission (NRC) have initiated a multiyear project to investigate the application of burnup credit (BUC) for boiling water reactor (BWR) fuel in storage and transportation systems (often referred to as casks) and spent fuel pools (SFPs). This work is divided into two main phases. The first phase investigated the applicability of peak reactivity methods currently used in SFPs to transportation and storage casks and the validation of reactivity calculations and spent fuel compositions within these methods. The second phase focuses on extending BUC beyond peak reactivity. This paper documents the analysis of the effects of control blade insertion history, and moderator density and burnup axial profiles for extended BWR BUC.
- Publication Date:
- OSTI Identifier:
- DOE Contract Number:
- Resource Type:
- Resource Relation:
- Conference: PHYSOR 2016, Sun Valley, ID, USA, 20160501, 20160505
- Research Org:
- Oak Ridge National Laboratory (ORNL)
- Sponsoring Org:
- ORNL work for others
- Country of Publication:
- United States
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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