Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

The multigroup library processing method for coupled neutron and photon heating calculation of fast reactor

  • Teng Zhang (North China Electric Power University, School of Nuclear Science and Engineering) ;
  • Xubo Ma (North China Electric Power University, School of Nuclear Science and Engineering) ;
  • Kui Hu (North China Electric Power University, School of Nuclear Science and Engineering) ;
  • GuanQun Jia (North China Electric Power University, School of Nuclear Science and Engineering)
  • Received : 2023.06.08
  • Accepted : 2023.11.10
  • Published : 2024.04.25
Download PDF
⟨ Previous Next ⟩

Abstract

To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups. The neutron cross-section processing code MGGC2.0 was used to generate few-group neutron cross sections in ISOTXS format. Additionally, the self-developed photon cross-section processing code NGAMMA was utilized to generate photon libraries for neutron-photon coupled heating calculations, including photo-atom cross sections for the ISOTXS format, prompt photon production cross sections, and kinetic energy release in materials (KERMA) factors for neutrons and photons, and the self-shielding effect from the capture and fission cross sections of neutron to photon have been taken into account when the photon source generated by neutron is calculated. The interface code GSORCAL was developed to generate the photon source distribution and interface with the DIF3D code to calculate the neutron-photon coupling heating distribution of the fast reactor core. The neutron-photon coupled heating calculation route was verified using the ZPPR-9 benchmark and the RBEC-M benchmark, and the results of the coupled heating calculations were analyzed in comparison with those obtained from the Monte Carlo code MCNP. The calculations show that the library was accurately processed, and the results of the fast reactor neutron-photon coupled heating calculations agree well with those obtained from MCNP.

Keywords

Acknowledgement

This study was supported by the National Natural Science Foundation of China (No.11875128).

References

  1. A. Luthi, R. Chawla, G. Rimpault, Improved gamma-heating calculational methods for fast reactors and their validation for plutonium-burning configurations[J], Nucl. Sci. Eng. 138 (3) (2001) 233-255.  https://doi.org/10.13182/NSE01-A2211
  2. P. Deng, B.K. Jeon, H. Park, et al., Coupled neutron and gamma heating calculation based on VARIANT transport solutions[J], Nucl. Sci. Eng. (2019).
  3. H. Park, B.K. Jeon, W.S. Yang, et al., Verification and validation tests of gamma library of MC2-3 for coupled neutron and gamma heating calculation, Ann. Nucl. Energy 146 (2020), 107609. 
  4. J.D. Chen, Y.Q. Zheng, X.N. Du, et al., Analysis of gamma-heating behavior in fast reactor based on SARAX-LAVENDER, Modern Applied Physics 12 (1) (2021) 75-80. 
  5. K.L. Derstine, DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory problems[R], Argonne National Lab., 1984. 
  6. R.E. Alcouffe, F.W. Brinkley, D.R. Marr, et al., User's Guide for TWODANT: a Code Package for Two-Dimensional, Diffusion-Accelerated, Neutral-Particle transport [R], Los Alamos National Lab., NM (USA), 1984. 
  7. W.S. Yang, Fast reactor physics and computational methods, Nucl. Eng. Technol. 44 (2) (2012) 177-198.  https://doi.org/10.5516/NET.01.2012.504
  8. G. Rimpault, D. Plisson, J. Tommasi, et al., The ERANOS code and data system for fast reactor neutronic analyses[C], in: PHYSOR 2002-International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, 2002. 
  9. C. Lee, Verification of the MC2-3 Gamma Library[R], Argonne National Lab.(ANL), Argonne, IL (United States), 2018. 
  10. B. Zhang, X. Ma, K. Hu, et al., Development and verification of neutron and photon multi-group cross sections processing code TXMAT2. 0[J], Prog. Nucl. Energy 138 (2021), 103803. 
  11. S. Jae, N. Choi, H.G. Joo, Implementation and Verification of Explicit Treatment of Neutron/Photon Heating in nTRACER[J] (2020). 
  12. W. Haeck, J.L. Conlin, A.P. McCartney, et al., NJOY2016 Updates for ENDF/B-VIII. 0[R]. Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2018. 
  13. K. Hu, X. Ma, T. Zhang, et al., MGGC2. 0: A Preprocessing Code for the Multi-Group Cross Section of the Fast Reactor with Ultrafine Group library[J], Nuclear Engineering and Technology, 2023. 
  14. K.S. Kim, S.G. Hong, Gamma transport and diffusion calculation capability coupled with neutron transport simulation in KARMA 1.2[J], Ann. Nucl. Energy 57 (2013) 59-67.  https://doi.org/10.1016/j.anucene.2013.01.047
  15. A. Luthi, Development and Validation of Gamma-Heating Calculational Methods for Plutonium-Burning Fast reactors[R], EPFL, 1999. 
  16. H. Park, W.S. Yang, M.A. Smith, et al., Verification and Validation Tests of the Gamma Library of the ARC Software Package (Rev. 1)[R], Argonne National Lab. (ANL), Argonne, IL (United States), 2022. 
  17. R.D. O'Dell, Standard Interface Files and Procedures for Reactor Physics Codes. Version IV[R], Los Alamos Scientific Lab., N. Mex.(USA), 1977. 
  18. M.A. Smith, C.H. Lee, R.N. Hill, GAMSOR: Gamma Source Preparation and DIF3D Flux Solution, Revision 2[R], Argonne National Lab.(ANL), Argonne, IL (United States), 2022. 
  19. T. Goorley, M. James, T. Booth, et al., Initial MCNP6 release overview[J], Nucl. Technol. 180 (3) (2012) 298-315.  https://doi.org/10.13182/NT11-135
  20. M. Salvatores, G. Palmiotti, G. Aliberti, et al., Methods and issues for the combined use of integral experiments and covariance data: results of a NEA international collaborative study[J], Nucl. Data Sheets 118 (2014) 38-71.  https://doi.org/10.1016/j.nds.2014.04.005
  21. A. Talamo, A. Bergeron, S. Mohanty, et al., Serpent and MCNP calculations of the energy deposition in the transformational challenge reactor[J], Nucl. Sci. Eng. 196 (12) (2022) 1464-1475.  https://doi.org/10.1080/00295639.2021.1977078
  22. K. Mikityuk, A. Vasiliev, P. Fomichenko, et al., RBEC-M lead-bismuth cooled fast reactor: Optimization of conceptual decisions[C]//International Conference on, Nucl. Eng. 35960 (2002) 701-709. 
  23. R. Qiu, X. Ma, Q. Xu, et al., Development and verification of multi-group cross section process code TXMAT for fast reactor RBEC-M analysis[C]//International conference on nuclear engineering, Am. Soc. Mech. Eng. 57816 (2017). V003T02A015.