PWR core and spent fuel pool analysis using scale and nestle
- Dept. of Nuclear Engineering, Univ. of Tennessee, Knoxville, TN 37996-2300 (United States)
- Duke Energy, 526 S. Church St, Charlotte, NC 28202 (United States)
The SCALE nuclear analysis code system [SCALE, 2011], developed and maintained at Oak Ridge National Laboratory (ORNL) is widely recognized as high quality software for analyzing nuclear systems. The SCALE code system is composed of several validated computer codes and methods with standard control sequences, such as the TRITON/NEWT lattice physics sequence, which supplies dependable and accurate analyses for industry, regulators, and academia. Although TRITON generates energy-collapsed and space-homogenized few group cross sections, SCALE does not include a full-core nodal neutron diffusion simulation module within. However, in the past few years, the open-source NESTLE core simulator [NESTLE, 2003], originally developed at North Carolina State Univ. (NCSU), has been updated and upgraded via collaboration between ORNL and the Univ. of Tennessee (UT), so it now has a growingly seamless coupling to the TRITON/NEWT lattice physics [Galloway, 2010]. This study presents the methodology used to couple lattice physics data between TRITON and NESTLE in order to perform a three-dimensional full-core analysis employing a 'real-life' Duke Energy PWR as the test bed. The focus for this step was to compare the key parameters of core reactivity and radial power distribution versus plant data. Following the core analysis, following a three cycle burn, a spent fuel pool analysis was done using information generated from NESTLE for the discharged bundles and was compared to Duke Energy spent fuel pool models. The KENO control module from SCALE was employed for this latter stage of the project. (authors)
- Research Organization:
- American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
- OSTI ID:
- 22105883
- Resource Relation:
- Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 4 refs.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPARATIVE EVALUATIONS
COMPUTER CODES
COOLING PONDS
CROSS SECTIONS
NEUTRON DIFFUSION EQUATION
ORNL
POWER DISTRIBUTION
PWR TYPE REACTORS
QUALITY CONTROL
REACTIVITY
REACTOR CORES
REACTOR LATTICES
REACTOR SIMULATORS
SIMULATION
SPENT FUELS
THREE-DIMENSIONAL CALCULATIONS