Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages

  • Received : 2018.02.27
  • Accepted : 2018.05.29
  • Published : 2018.10.25
Download PDF
⟨ Previous Next ⟩

Abstract

In this paper, McCARD code was verified using various models listed in the NUREG/CR-6361 benchmark guide, which provides specifications for single pin-cells, single assemblies, and the whole core classified depending on the nuclear properties and structural characteristics. McCARD code was verified by comparing its results with those of SCALE code for single pin-cell and single assembly benchmark problems. The difference in the multiplication factor obtained through the two codes did not exceed 90 pcm. The benchmark guide treats a total of 173 whole core experiments. The experiments are categorized as simple lattices, separator plates, reflecting walls, reflecting walls and separator plates, burnable absorber fuel rods, water holes, poison rods, and borated moderator. As a result of numerical simulation using McCARD, the mean value of the multiplication factors is 1.00223 and the standard deviation of the multiplication factors is 285 pcm. The difference between the multiplication factors and the experimental value is in the range of -665 pcm to + 1609 pcm. In addition, statistics of results for experiments categorized by reactor shape, additional structure, burnable poison, etc., are detailed in the main text.

Keywords

References

  1. H.J. Shim, C.H. Kim, McCARD User's Manual ver 1.1, Seoul National University, 2016.
  2. Hyung-Jin Shim, et al., McCARD: Monte Carlo code for advanced reactor design and analysis, Nucl. Eng. Technol. 44 (2) (2012) 161-176. https://doi.org/10.5516/NET.01.2012.503
  3. Park, Ho Jin, et al., Assembly depletion with critical spectrum in McCARD Monte Carlo calculations and comparison with HELIOS, PHYSOR 2010 (2010) 9-14.
  4. Yoo Seung Yeol, Hyung Jin Shim, Chang Hyo Kim, Monte Carlo few-group constant generation for CANDU 6 core analysis, Sci. Technol. Nucl. Installations 2015 (2015).
  5. Han, Tae Young, et al., Verification of the procedure to generate the homogenized multi-group cross section for VHTR fuel block using McCARD, in: Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, 2012.
  6. J.J. Lichtenwalter, et al., Criticality Benchmark Guide for Light-water-reactor Fuel in Transportation and Storage Packages, No. NUREG/CR-6361; ORNL/TM-13211, Nuclear Regulatory Commission, Washington, DC (United States), Office of Nuclear Material Safety and Safeguards; Oak Ridge National Lab., TN (United States), 1997.
  7. Oak Ridge National Laboratory, SCALE: a Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, Oak Ridge National Laboratory, 2011.
  8. T.C. Engelder, et al., Spectral Shift Control Reactor Basic Physics Program, Critical Experiments on Lattices Moderated by D2O-H2O Mixtures, BAW-1231, Babcock & Wilcox Company, December 1961.
  9. L.W. Newman, Urania-gadolinia: Nuclear Model Development and Critical Experiment Benchmark, DOE/ET/34212-34241 (BAW-1810), Babcock & Wilcox, April 1984.
  10. D. Haon, et al., in: Validation of the Apollo-Moret Neutronic Codes on Critical Experimental Configurations Simulating the Shipping Casks for Light Water Fuels, PATRAM'80, 1980.