Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Neutronics and shielding simulation and evaluation of a second pool of a typical research reactor as spent fuel pool

Document Type : Research Paper

Authors

E. Boustani
M. Hasanzadeh

Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 14155-1339, Tehran - Iran

https://doi.org/10.24200/nst.2024.1641
Abstract
The design calculations of the spent fuel pool require the consideration of various parameters such as neutronic, thermal-hydraulic, safety, shielding, economic and operation. Considering the high cost of designing and building of a new spent fuel pool as well as the existence of empty spaces in the pool of some research reactors, neutronic and shielding calculations for the feasibility of using second pool of a typical research reactor as a spent fuel pool is done using ORIGEN2.1 and MCNP6 codes. The first step is the determination of the distance between fuels (grid pitch) in such a way that the effective multiplication factor for the worst possible case is less than 0.95, that 13 cm grid pitch fulfills this condition. Source term calculation for a fuel with the highest burnup (60%) is done as the most pessimistic condition. Continuous operation and 24 hours cooling are considered as the shortest possible time to transfer spent fuels to the storage rack in order to have the most pessimistic conditions in the design of spent fuel rack. For a rack with 100 spent fuels that is 87 cm away from the pool wall on each side, a 300 cm layer of water on top of the fuels and 85 cm thick concrete wall are enough for the possibility of using second pool as a spent fuel pool. It has been found that it meets the dose rate criteria of less than 1 and 10 μSv/h behind the wall and above the pool water level.

Highlights

  1. IAEA safety standards, Design of Fuel Handling and Storage Systems for Nuclear Power Plants, Specific Safety Guide No. SSG-63. 2020.

 

  1. Lebrun A, Bignan G. Nondestructive assay of nuclear low-enriched uranium spent fuels for burnup credit application. 2016.

 

  1. Robert K. Criticality Safety in the Waste Management of Spent Fuel from NPPs. 2011.

 

  1. Arndt B, Klaus R, Wasinger K. Advanced spent fuel storage pools. Storage of spent fuel from power reactors. Vienna. IAEA. 2003;130-141.

 

  1. Perschmann W.D, Fuchs H.P, Banck J. Impact of Extended Burnup of Spent Fuel on Backend of Fuel Cycle. German Perspective. IAEA. Vienna. 2002;8-11 July.

 

  1. IAEA-Nuclear Energy Series. No. NF-T-3.9. Research Reactor Spent fuel management Options and Support to Decision Making. VIENNA. 2021.

 

  1. Management and storage of Research Reactor Spent Nuclear Fuel, Proceedings of a Technical Meeting held in Thurso. United Kingdom. 2009;19–22 October.

 

  1. IAEA-TECDOC-1508. Spent fuel management options for research reactors in Latin America. VIENNA. 2006.

 

  1. Benz J.M, Smartt H.A. Maintaining Continuity of Knowledge of Spent Fuel Pools Tool Survey. the U.S. Department of Energy. 2016 August.

 

  1. Khan L.A, Ahmad N. Reactivity worth of the thermal column of a MTR type swimming pool research reactor using low enriched uranium fuel. Annals of Nuclear Energy. 2002 1 Jul;29(10):1253-9. Doi: 10.1016/S0306-4549(01)00108-6.

 

  1. Mahmood T, Bokhari I.H, Iqbal M, Mahmood T, Ahmed N, Israr M. Performance evaluation/analysis of Pakistan Research Reactor-1 (PARR-1) current core configuration. Progress in Nuclear Energy. 2011 1 Aug;53(6):729-35. Doi.org/10.1016/j.anucene. 2007.06.006.

 

  1. IAEA-Tecdoc-233. Research Reactor Core Conversion from The Use of Highly Enriched Uranium to The Use of Low Enriched Uranium Fuels Guidebook. 1980.

 

  1. Sallmann D.I, Moersch I.J, Vlaski D.I. Design of spent nuclear fuel storage facilities for the load cases earthquake and aircraft impact-technical specifications, methods and examples for wet and dry storage. Transactions of the Korean Nuclear Society Autumn Meeting Yeosu, Korea. 2018 25-26 October.

 

  1. Gol Narges S, Mousavian S.K. Thermal-hydraulic analysis of loss-of-cooling accident in spent fuel pool of Bushehr NPP using the RELAP5 and MELCOR. Journal of Nuclear Science and Technology. 2020 21 Nov;41(3):87-96 [In Persian].

 

  1. IAEA Safety Standards Series No. SSG-15. Storage of Spent Nuclear Fuel. Specific Safety guide. 2012.

 

  1. Mohammadi A, Hassanzadeh M, Omidvari N. Criticality safety analysis of TK-13 cask in Bushehr nuclear power plant. Kerntechnik. 2017;82:637–642. Doi.org/10.3139/124.110831.

 

  1. Safety Analysis Report for Tehran Research Reactor. Atomic Energy Organization of Iran. 2009.

 

  1. Safety Analysis Report for Australian Nuclear Science and Technology Organization. 2004.

 

  1. Pelowitz D.B. MCNP6TM User’s Manual. Version 1.0, Los Alamos National Laboratory report LA-CP-13-00634. 2013.

 

  1. Crofft A.G. A User’s Manual for the ORIGEN 2.1 Computer Code. Rep. ORNL/TM-7175 Oak Ridge National Laboratory. 2000.

 

  1. Lamarsh J.R. Introduction to Nuclear Engineering. Addision- Wesely Publishing Company. 1975.

Keywords

Neutronic
Shielding
Research reactor
Spent fuel
MCNP6 code
  1. IAEA safety standards, Design of Fuel Handling and Storage Systems for Nuclear Power Plants, Specific Safety Guide No. SSG-63. 2020.

 

  1. Lebrun A, Bignan G. Nondestructive assay of nuclear low-enriched uranium spent fuels for burnup credit application. 2016.

 

  1. Robert K. Criticality Safety in the Waste Management of Spent Fuel from NPPs. 2011.

 

  1. Arndt B, Klaus R, Wasinger K. Advanced spent fuel storage pools. Storage of spent fuel from power reactors. Vienna. IAEA. 2003;130-141.

 

  1. Perschmann W.D, Fuchs H.P, Banck J. Impact of Extended Burnup of Spent Fuel on Backend of Fuel Cycle. German Perspective. IAEA. Vienna. 2002;8-11 July.

 

  1. IAEA-Nuclear Energy Series. No. NF-T-3.9. Research Reactor Spent fuel management Options and Support to Decision Making. VIENNA. 2021.

 

  1. Management and storage of Research Reactor Spent Nuclear Fuel, Proceedings of a Technical Meeting held in Thurso. United Kingdom. 2009;19–22 October.

 

  1. IAEA-TECDOC-1508. Spent fuel management options for research reactors in Latin America. VIENNA. 2006.

 

  1. Benz J.M, Smartt H.A. Maintaining Continuity of Knowledge of Spent Fuel Pools Tool Survey. the U.S. Department of Energy. 2016 August.

 

  1. Khan L.A, Ahmad N. Reactivity worth of the thermal column of a MTR type swimming pool research reactor using low enriched uranium fuel. Annals of Nuclear Energy. 2002 1 Jul;29(10):1253-9. Doi: 10.1016/S0306-4549(01)00108-6.

 

  1. Mahmood T, Bokhari I.H, Iqbal M, Mahmood T, Ahmed N, Israr M. Performance evaluation/analysis of Pakistan Research Reactor-1 (PARR-1) current core configuration. Progress in Nuclear Energy. 2011 1 Aug;53(6):729-35. Doi.org/10.1016/j.anucene. 2007.06.006.

 

  1. IAEA-Tecdoc-233. Research Reactor Core Conversion from The Use of Highly Enriched Uranium to The Use of Low Enriched Uranium Fuels Guidebook. 1980.

 

  1. Sallmann D.I, Moersch I.J, Vlaski D.I. Design of spent nuclear fuel storage facilities for the load cases earthquake and aircraft impact-technical specifications, methods and examples for wet and dry storage. Transactions of the Korean Nuclear Society Autumn Meeting Yeosu, Korea. 2018 25-26 October.

 

  1. Gol Narges S, Mousavian S.K. Thermal-hydraulic analysis of loss-of-cooling accident in spent fuel pool of Bushehr NPP using the RELAP5 and MELCOR. Journal of Nuclear Science and Technology. 2020 21 Nov;41(3):87-96 [In Persian].

 

  1. IAEA Safety Standards Series No. SSG-15. Storage of Spent Nuclear Fuel. Specific Safety guide. 2012.

 

  1. Mohammadi A, Hassanzadeh M, Omidvari N. Criticality safety analysis of TK-13 cask in Bushehr nuclear power plant. Kerntechnik. 2017;82:637–642. Doi.org/10.3139/124.110831.

 

  1. Safety Analysis Report for Tehran Research Reactor. Atomic Energy Organization of Iran. 2009.

 

  1. Safety Analysis Report for Australian Nuclear Science and Technology Organization. 2004.

 

  1. Pelowitz D.B. MCNP6TM User’s Manual. Version 1.0, Los Alamos National Laboratory report LA-CP-13-00634. 2013.

 

  1. Crofft A.G. A User’s Manual for the ORIGEN 2.1 Computer Code. Rep. ORNL/TM-7175 Oak Ridge National Laboratory. 2000.

 

  1. Lamarsh J.R. Introduction to Nuclear Engineering. Addision- Wesely Publishing Company. 1975.

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