Verification and Validation of the BISON Fuel Performance Code for PCMI Applications

Conference · Wed Jun 01 04:00:00 EDT 2016

OSTI ID:1348075

Gamble, Kyle Allan Lawrence ^[1]; Novascone, Stephen Rhead ^[1]; Gardner, Russell James ^[1]; Perez, Danielle Marie ^[1]; Pastore, Giovanni ^[1]; Hales, Jason Dean ^[1]

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1. Idaho National Laboratory

BISON is a modern finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 2D axisymmetric, or 3D geometries. A brief overview of BISON’s computational framework, governing equations, and general material and behavioral models is provided. BISON code and solution verification procedures are described. Validation for application to light water reactor (LWR) PCMI problems is assessed by comparing predicted and measured rod diameter following base irradiation and power ramps. Results indicate a tendency to overpredict clad diameter reduction early in life, when clad creepdown dominates, and more significantly overpredict the diameter increase late in life, when fuel expansion controls the mechanical response. Initial rod diameter comparisons have led to consideration of additional separate effects experiments to better understand and predict clad and fuel mechanical behavior. Results from this study are being used to define priorities for ongoing code development and validation activities.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1348075
• Report Number(s): INL/CON-16-37780
• Country of Publication: United States
• Language: English

Related Subjects

BISON
PCMI
validation