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VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12

Technical Report ·
DOI:https://doi.org/10.2172/3009418· OSTI ID:3009418
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [2];  [3];  [4];  [4];  [5];  [6]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
  3. Tennessee Valley Authority (TVA), Knoxville, TN (United States)
  4. Univ. of Michigan, Ann Arbor, MI (United States)
  5. Univ. of Tennessee, Knoxville, TN (United States)
  6. Westinghouse Electric Corp., Pittsburgh, PA (United States)
+ Show Author Affiliations
Among the most important accomplishments during Phase 1 of the Consortium for Advanced Simulation of Light Water Reactors (CASL) is the development and deployment of what is known as VERA-CS, the steady-state nuclear reactor core simulation capability of the Virtual Environment for Reactor Applications, VERA. With this product CASL now has the ability to perform and support analyses relating to common evolutions of operating commercial pressurized water reactors (PWRs), including startup testing, power escalation, fuel cycle depletion, and fuel assembly discharge, reinsert, and shuffling. VERA-CS is a high-fidelity, multi-physics engineering tool that utilizes modest high-performance computing (HPC) systems and engineering-scale clusters to simultaneously simulate the local fuel rod neutronics and coolant channel thermal-hydraulics over the life of the reactor. Though it is still under development, the results demonstrated in this report provide encouraging evidence that VERA-CS will become highly acclaimed for industrial, scientific, and educational applications alike.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
AC05-00OR22725; AC07-05ID14517
OSTI ID:
3009418
Report Number(s):
CASL-U--2015-0206-000
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING