Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit

Conference · Fri May 01 00:00:00 EDT 2015

OSTI ID:1223670

Ade, Brian J ^[1]; Marshall, William BJ J ^[1]; Martinez-Gonzalez, Jesus S ^[1]

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1. ORNL

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: Work for Others (WFO)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1223670
• Resource Relation: Conference: PHYSOR 2016, Sun Valley, ID, USA, 20160501, 20160505
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS