Published 2021 | Version v1
Book

Status of the OECD/NEA TVA Watts Bar 1 benchmark and Monte Carlo modeling of the 'Zero power physics test' exercise

  • 1. North Carolina State University, Burlington Laboratories, 2500 Stinson Drive, Raleigh, NC, 27695-7909 (United States)

Description

This paper describes the status of the OECD/NEA Tennessee Valley Authority (TVA) Watts Bar 1 (WB1) Multi-Physics Multi-Cycle depletion benchmark and the results associated with the First Exercise - Zero Power Physics Tests (ZPPT) at Hot Zero Power (HZP) conditions. The OECD/NEA TVA WB1 benchmark is being developed for verification and validation of traditional and novel high-fidelity multi-physics codes for Pressurized Water Reactors (PWRs), Modeling and Simulation of different steady states and cycle depletion scenarios. The benchmark relies on real plant data of the first three cycles of the TVA WB1, a Westinghouse 17 x 17 PWR, and covers the distinct phases of typical operational conditions over 7 benchmark exercises. Exercise 1 corresponds to the start-up fresh-fuel only ZPPT stand-alone three-dimensional neutronics at HZP conditions; Exercise 2 covers the Hot Full Power (HFP) Beginning of Cycle (BOC) operations; Exercise 3 focuses on the WB1 Cycle 1 depletion; Exercise 4 covers the WB1 fuel shuffle and decay of Cycle 2 BOC ZPPT; Exercise 5 models the WB1 depletion for Cycle 2, Exercise 6 and Exercise 7 are similar to Exercise 4 and Exercise 5 but applied to core reload for Cycle 3. Validating cycle depletion modeling and simulation tools over the first 3 cycles (which are 18-month cycles associated with the current state-of-the-art PWR fuel management practices) is very important because it covers the transition of start-up cycles to near (pseudo) equilibrium cycle of operation. The paper provides the results for the first exercise obtained with the Monte Carlo code Serpent 2.131 and the comparison with the Monte Carlo code CE-KENO-VI. The Serpent calculations are performed with two nuclear cross-section libraries ENDF/B-VII.0 and ENDF/B-VII.1 to measure the sensitivity of the model upon the nuclear data library upgrade. Ten critical configurations are presented along with nine rod worth cases to evaluate the control bank worth for each control bank. Serpent and KENO have a good agreement with 56 pcm in absolute value as the highest difference. Serpent results are improved with a factor of ∼22 pcm as compared to measured data when upgrading from ENDF/B-VII.0 to ENDF/B-VII.1 cross-section library. (authors)

Availability note (English)

Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)
Part of:
Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021

Additional details

Publishing Information

Publisher
ANS - American Nuclear Society
Imprint Place
La Grange Park (United States)
Imprint Title
Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021
Imprint Pagination
2418 p.
Journal Page Range
p. 1918-1926

Conference

Title
International conference on mathematics and computational methods applied to nuclear science and engineering
Acronym
M and C 2021
Dates
3-7 Oct 2021
Place
Raleigh, NC (United States)

Optional Information

Notes
4 refs.; Virtual meeting