NDLI: Three Dimensional Analysis of 3-Loop PWR RCCA Ejection Accident for High Burnup

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Marciulescu, Cristian Sung, Yixing Charles, L. Beard
Copyright Year	2006
Abstract	The Rod Control Cluster Assembly (RCCA) ejection accident is a Condition IV design basis reactivity insertion event for Pressurized Water Reactors (PWR). The event is historically analyzed using a one-dimensional (1D) neutron kinetic code to meet the current licensing criteria for fuel rod burnup to 62,000 MWD/MTU. The Westinghouse USNRC-approved three-dimensional (3D) analysis methodology is based on the neutron kinetics version of the ANC code (SPNOVA) coupled with Westinghouse’s version of the EPRI core thermal-hydraulic code VIPRE-01. The 3D methodology provides a more realistic yet conservative analysis approach to meet anticipated reduction in the licensing fuel enthalpy rise limit for high burnup fuel. A rod ejection analysis using the 3D methodology was recently performed for a Westinghouse 3-loop PWR at an uprated core power of 3151 MWt with reload cores that allow large flexibility in assembly shuffling and a fuel hot rod burnup to 75,000 MWD/MTU. The analysis considered high enrichment fuel assemblies at the control rod locations as well as bounding rodded depletions in the end of life, zero power and full power conditions. The analysis results demonstrated that the peak fuel enthalpy rise is less than 100 cal/g for the transient initiated at the hot zero power condition. The maximum fuel enthalpy is less than 200 cal/g for the transient initiated from the full power condition.
Sponsorship	Nuclear Engineering Division
Starting Page	303
Ending Page	308
Page Count	6
File Format	PDF
ISBN	0791842452
DOI	10.1115/ICONE14-89552
e-ISBN	0791837831
Volume Number	Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition
Conference Proceedings	14th International Conference on Nuclear Engineering
Language	English
Publisher Date	2006-07-17
Publisher Place	Miami, Florida, USA
Access Restriction	Subscribed
Subject Keyword	Design Dimensional analysis Enthalpy Neutrons Manufacturing Fuels Licensing Pressurized water reactors Accidents Transients (dynamics) Fuel rods
Content Type	Text
Resource Type	Article

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