Analysis of the Influence of Energy Group Structure on Iron Shielding Calculation-Reference-Cited by-同舟云学术

Analysis of the Influence of Energy Group Structure on Iron Shielding Calculation

Published:2023-04-19 Issue:8 Volume:16 Page:3538
ISSN:1996-1073
Container-title:Energies
language:en
Short-container-title:Energies

Author:

Wu Jun¹^ORCID,Zhang Bin¹,Chen Yixue¹

Affiliation:

1. School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China

Abstract

The energy group structure of a multi-group cross section library matched with a deterministic method has a significant influence on shielding calculation. The complex resonance cross section of Fe-56 has a significant influence on accuracy with different energy group structures when processing multi-group cross section data. In this study, in order to more accurately test the influence of the iron resonance phenomenon on shielding calculations, this group structure is modified by the 199-group with 69 points interpolated into its group boundaries at an energy range from 1.1 keV to 3.1164 MeV. The new 269-group library is then tested with selected SINBAD iron sphere benchmarks and compared with the results of 199-group, 299-group, and 172-group libraries and measurements. Upon analysis, it is shown that the resonance of Fe-56 has a great influence on the accuracy of the calculated leakage. Further, it is noted that the finer the energy group division, the greater the calculated leakage fluctuation, and the deeper the neutron passes through the iron sphere, the larger the calculated leakage fluctuation. This study and its leakage results may provide a good reference for the development of new multi-group structures for present and future shielding design.

Publisher

MDPI AG

Subject

Energy (miscellaneous),Energy Engineering and Power Technology,Renewable Energy, Sustainability and the Environment,Electrical and Electronic Engineering,Control and Optimization,Engineering (miscellaneous),Building and Construction

Link

https://www.mdpi.com/1996-1073/16/8/3538/pdf

Reference20 articles.

1. Lathrop, K.D. (1965). DTF-IV, a Fortran-IV Program for Solving the Multigroup Transport Equation with Anisotropic Scattering, Los Alamos Scientific Laboratory of the University of California. LA-3373.

2. Hansen, G.E., and Roach, W.H. (1961). Six and Sixteen Group Cross Sections for Fast and Intermediate Critical Assemblies, LAMS-2543.

3. Bandarenko, I.I., and Abagyan, L.P. (1964). Group Constants for Nuclear Reactor Calculations, Consultanta Buren.

4. Zmijarevic. Advanced neutronics tools for BWR design calculations;Santamarina;Nucl. Eng. Des.,2008

5. Validation of CASMO5 neutron kinetics parameters;Hykes;Ann. Nucl. Energy,2020