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

Calculations of fuel burn up for HTR-10 graphite-gas reactor with UO2 fuel and ThO2-PuO2 combined fuel

Document Type : Research Paper

Authors

A. Kolali
D. Naghavi Dizaji
I. Ramezani
N. Vosoughi

Department of Energy Engineering, Sharif University of Technology, P.O.BOX: 14565-1114, Tehran - Iran

https://doi.org/10.24200/nst.2020.504.1342
Abstract
In this study, the graphite-gas reactor HTR-10 is simulated using the MCNPx Monte Carlo code, considering the random placement of the fuel and moderator pebbles. Core neutronic parameters are calculated and compared with IAEA documents. Burn up calculations are performed for uranium oxide fuel and combined thorium-plutonium oxide fuel. The results show that the combined fuel has a longer cycle length about 28 percent more than the uranium oxide fuel. It is also better used in relation to nuclear safeguards.

Highlights

  1. Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10. L.BREY, Ed. IAEA-TECDOC- 1382. International Atomic Energy Agency. 2003.

 

  1. Abedi A, Vosoughi N. Neutronic simulation of a pebble bed reactor considering its double heterogeneous nature. Department of Energy Engineering. Sharif University of Technology. Tehran. Iran. 2012.

 

  1. Bakhshayesh K.M, Vosoughi N. A simulation of a pebble bed reactor core by the MCNP-4C computer code. Nuclear Technology and Radiation Protection. 2009;24(3):177-182.

 

  1. Liu S, Li Z. Random geometry capability in RMC code for explicit analysis of polytype particle/pebble and applications to HTR-10 benchmark. Department of Nuclear Engineering Physics. Tsinghua University. China. 2018.

 

  1. Seker V. HTR-10 full core first criticality analysis with MCNP. Department of Nuclear Engineering Hacettepe University. Ankara, Turkey. 2003.

 

  1. Alzamly M.A, Aziz M, Badawi A.A, Gabal H.A, Gadallah A.R.A. Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide. Nuclear Engineering and Technology. 2019.

 

  1. Wu S.C, Sheu R.J, Peir J.J, Liang J.H. Burnup computation for HTR-10 using layer-to-layer movement. In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers Digital Collection. 2013.

Keywords

Burn up
Uranium oxide
Thorium-plutonium oxide
HTR-10
MCNPx
  1. Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10. L.BREY, Ed. IAEA-TECDOC- 1382. International Atomic Energy Agency. 2003.

 

  1. Abedi A, Vosoughi N. Neutronic simulation of a pebble bed reactor considering its double heterogeneous nature. Department of Energy Engineering. Sharif University of Technology. Tehran. Iran. 2012.

 

  1. Bakhshayesh K.M, Vosoughi N. A simulation of a pebble bed reactor core by the MCNP-4C computer code. Nuclear Technology and Radiation Protection. 2009;24(3):177-182.

 

  1. Liu S, Li Z. Random geometry capability in RMC code for explicit analysis of polytype particle/pebble and applications to HTR-10 benchmark. Department of Nuclear Engineering Physics. Tsinghua University. China. 2018.

 

  1. Seker V. HTR-10 full core first criticality analysis with MCNP. Department of Nuclear Engineering Hacettepe University. Ankara, Turkey. 2003.

 

  1. Alzamly M.A, Aziz M, Badawi A.A, Gabal H.A, Gadallah A.R.A. Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide. Nuclear Engineering and Technology. 2019.

 

  1. Wu S.C, Sheu R.J, Peir J.J, Liang J.H. Burnup computation for HTR-10 using layer-to-layer movement. In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers Digital Collection. 2013.

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