Effect of Geometric Changes in of WWER-1000 Reactor’s Fuel Assemblies on their Fuel Burnup Parameter

Document Type : Research Paper

Authors

1 Department of Nuclear Physics, Faculty of Sciences, University of Mazandaran

2 Department of Nuclear Physics, Faculty of Science, University of Mazandaran, Babolsar, Iran

Abstract

The prediction of fuel burnup of fuel assemblies in nuclear reactors is one of the most important issues in nuclear engineering and reactor physics. Currently, many researchers in different countries are working on improving fuel burnup in nuclear reactors and increasing their economic and safety indicators. The DRAGON4 code is a cell and fuel burnup calculation code which was developed at Montreal Polytechnic University of Canada. In this study, at first, the DRAGON4 code was verified for a fuel assembly of Bushehr nuclear power plant and then, the fuel burnup changes due to geometric changes in the mentioned fuel assembly have been investigated. Results of this simulation prove the validity of fuel rod pitch with consideration of safety and economy aspects in Bushehr nuclear power plant fuel assemblies.

Keywords

References

[1] Rowayda F. et al. “Burnup credit in criticality safety of PWR spent fuel”. Nuclear Engineering and Design. 280. 628–633. 2014.
[2] IAEA-TECDOC-1547. “Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage”. Reprocessing and Disposition. IAEA, VIENNA. 2007.
[3] Oberle, Ph, Broeders C. H. M., and Dagan R. “Comparison of PWR–burnup calculations with SCALE 5.0/TRITON other burnup codes and experimental results”. PHYSOR-2006, Advances in Nuclear Analysis and Simulation. Vancouver, BC, Canada. 2006.
[4] Oggianu S., Kazimi M. Analysis of Burnup and Economic Potential of Alternative Fuel Materials in Thermal Reactors. Nuclear Technology. Vol. 143. 256-269. 2003.
[5] Hadad K., Yousefnia M. “Burnup and Neutronic Analysis of VVER-1000 Nuclear Reactor”. Proceedings of 2010 LWR Fuel Performance, Orlando, Florida, USA, September. 26-29. 2010.
[6] Taheranpour N., Talaei A. “Development of practical method using a Monte Carlo code for evaluation of optimum fuel pitch in a typical VVER-1000 core”. Annals of Nuclear Energy. 54.  129-133. 2013.
[7] Mozafari M.A., Faghihi F.. “Design of annular fuels for a typical VVER-1000 core: Neutronic investigation, pitch optimization and MDNBR calculation”. Annals of Nuclear Energy. 60. 226-234. 2013.
[8] Marleau G., Roy R. “User Guide for DRAGON Version4”. 2013.
[9] Calic D., Trkov A., and Kromar M. “Use of Lattice code DRAGON in reactor calculations”. Proceedings of the 22nd International Conference Nuclear Energy for New Europe, September. 2013.
[10] ZAO ASE. Final Safety Analysis Report of Bushehr NPP Unit 1. Chapter 4. Revision1.  2014.
[11] José J. Herrero et al. “Review calculations for the OECD/NEA Burnup Credit Criticality Safety Benchmark”. Annals of Nuclear Energy. 87. 48–57. 2016.
[12] Wang D. “Optimization of a seed and blanket thorium-uranium fuel cycle for pressurized water reactors”. Massachusetts Institute of Technology. 2003.
[13] Rahgoshay M., Hashemi-Tilehnoee M. “Calculating the inventory of heavy metals in the fuel assemblies of VVER-1000 during the first cycle”. Annals of Nuclear Energy. 58. 33-35. 2013.
[14] Gauld I.C., Radulescu G., Ilas G., Murphy B.D., Williams M.L., Wiarda D. “Isotopic depletion and decay methods and analysis capabilities in SCALE”. Nuclear Technology. 174. 169-195. 2011.
[15] Ohashi H., Sato H., Tachibana Y., Kunitomi K., Ogawa M.. “Concept of an inherently-safe high temperature gas-cooled reactor”. AIP Conference Proceedings, American Institute of Physics. 50-58. 2012.
[16] Qvist S., Greenspan E. “Inherent Safety of Minimum Burnup Breed-and-Burn Reactors”. Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP’12), June 24–28, 2012, American Nuclear Society Chicago, Illinois, 24-28. 2012.
[17] Scaglione J.M., Mueller D.E., Wagner J.C. “An approach for validating actinide and fission product burnup credit criticality safety analyses: criticality (keff) predictions”, Nuclear Technology, 188. 266-279. 2014.
[18] Averyanova S., Dubov A., Kosourov K., Filimonov P. “Temperature regulation and maneuverability of VER-1000”. Atomic energy.109. 2011.

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History

  • Receive Date: 02 November 2019
  • Revise Date: 09 February 2020
  • Accept Date: 07 March 2020

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