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

Simulation of the HTR-10 reactor core with spherical fuel to obtain the minimum height to access reactor criticality

Document Type : Scientific Note

Authors

K. Abbasi 1
M.H. Nayyeri 2

1 Department of Physics, College of Sciences, Yasuj University, P.O.Box: 7591874831, Yasuj – Iran

2 Department of Nuclear Engineering, Islamic Azad University of Arsanjan Branch, P.O.Box: 7376153161, Arsanjan – Iran

https://doi.org/10.24200/nst.2024.1527.1996
Abstract
The HTR-10 reactor is an experimental Pebble Bed Reactor (PBR), where simulating the neutron flux is crucial due to the reactor's multiple advantages, including safety, high efficiency, and modularity. As a result, studying and researching such reactors is a significant focus for countries with nuclear technology, especially for commercialization. Since both the fuel and moderator are in the form of spherical pebbles and are randomly distributed in the core, accurately evaluating the neutron flux is vital. This evaluation involves calculating the minimum height required for the reactor’s criticality, based on the specific arrangement of fuel and moderator. In this study, a new method for arranging the fuel and moderator pellets, while maintaining a ratio of 43:57, has been proposed. The calculations were performed using the MCNP code. Helium gas was chosen as the coolant, and changes in reactivity due to the insertion of control rods were also calculated.

Highlights

  1. TECDOC-1645. High Temperature Gas Cooled Reactor Fuels and Materials. International Atomic Energy Agency (IAEA), Vienna, Austria. 2010.

 

  1. Halla-aho L. Development of an HTR-10 model in the Serpent reactor physics code. Lappeenranta University of Technology. 2014.

 

  1. Tang Y, Zhang L, Guo Q, Xia B, Yin Z, Cao J. Analysis of the pebble burnup profile in a pebble-bed nuclear reactor. Nuclear Engineering and Design. 2019;345(15):233-251.

 

  1. Abedi A, Vosoughi N. An exact MCNP modeling of pebble bed reactors. 2011 International Nuclear Atlantic Conference-INAC. 2011.

 

  1. Beck J.M, Pincock L.F. High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant. INL/EXT-10-19329. Idaho National Laboratory. 2011.

 

  1. Li W, Yu G, Wei C. Research on benchmark calculation and analysis of HTR-10 with RMC code. 2014.

 

  1. Kim H.C, Kim S.H, Kim J.K. A new strategy to simulate a random geometry in a pebble-bed core with theMonte Carlo code MCNP. 2011.

 

  1. Lebenhaft J.R. MCNP4B modeling of pebble-bed reactors. 2001.

 

  1. Çolak Ü, Seker V. Monte Carlo Criticality Calculations for a Pebble Bed Reactor with MCNP. 2005.

 

  1. Rosales J, Muñoz A, García C, García L, Brayner C, Pérez J, Abánades A. Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX. International Journal of Nuclear Energy. 2014.

 

  1. Hosseini S.A, Athari-Allaf M. Synthesis of spherical bed type reactors with MCNP code. Physics Research Journal, 2012;NO. 2.

 

  1. Kolali A, Noorghasemi Gharghechi H, Ramazani I. Vosoughi N. Simulation and neutronic calculations of HTR10 reactor using SUPER MC and MCNPx2.7 nuclear calculation codes. 25th Iran Nuclear Conference. 2017 March.

 

  1. Zuhair, Suwoto, Setiadipura T, Kuijper J.C. The effects of fuel type on control rod reactivity of pebble-bed reactor. Nukleonika. 2019;64(4):131-138.

 

  1. Wu Z, Lin D, Zhong D. The design features of the HTR-10. Nuclear Engineering and Design. 2002;218:25-32.

 

  1. Suikkanen H, Ritvanen J, Jalali P, Kyrki-Rajamäki R. Discrete element modelling of pebble packing in pebble bed reactors. Nuclear Engineering and Design. 2014 July 1;273:24-32.

Keywords

Pebble bed reactor
Criticality height
Neutron flux
MCNP code
  1. TECDOC-1645. High Temperature Gas Cooled Reactor Fuels and Materials. International Atomic Energy Agency (IAEA), Vienna, Austria. 2010.

 

  1. Halla-aho L. Development of an HTR-10 model in the Serpent reactor physics code. Lappeenranta University of Technology. 2014.

 

  1. Tang Y, Zhang L, Guo Q, Xia B, Yin Z, Cao J. Analysis of the pebble burnup profile in a pebble-bed nuclear reactor. Nuclear Engineering and Design. 2019;345(15):233-251.

 

  1. Abedi A, Vosoughi N. An exact MCNP modeling of pebble bed reactors. 2011 International Nuclear Atlantic Conference-INAC. 2011.

 

  1. Beck J.M, Pincock L.F. High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant. INL/EXT-10-19329. Idaho National Laboratory. 2011.

 

  1. Li W, Yu G, Wei C. Research on benchmark calculation and analysis of HTR-10 with RMC code. 2014.

 

  1. Kim H.C, Kim S.H, Kim J.K. A new strategy to simulate a random geometry in a pebble-bed core with theMonte Carlo code MCNP. 2011.

 

  1. Lebenhaft J.R. MCNP4B modeling of pebble-bed reactors. 2001.

 

  1. Çolak Ü, Seker V. Monte Carlo Criticality Calculations for a Pebble Bed Reactor with MCNP. 2005.

 

  1. Rosales J, Muñoz A, García C, García L, Brayner C, Pérez J, Abánades A. Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX. International Journal of Nuclear Energy. 2014.

 

  1. Hosseini S.A, Athari-Allaf M. Synthesis of spherical bed type reactors with MCNP code. Physics Research Journal, 2012;NO. 2.

 

  1. Kolali A, Noorghasemi Gharghechi H, Ramazani I. Vosoughi N. Simulation and neutronic calculations of HTR10 reactor using SUPER MC and MCNPx2.7 nuclear calculation codes. 25th Iran Nuclear Conference. 2017 March.

 

  1. Zuhair, Suwoto, Setiadipura T, Kuijper J.C. The effects of fuel type on control rod reactivity of pebble-bed reactor. Nukleonika. 2019;64(4):131-138.

 

  1. Wu Z, Lin D, Zhong D. The design features of the HTR-10. Nuclear Engineering and Design. 2002;218:25-32.

 

  1. Suikkanen H, Ritvanen J, Jalali P, Kyrki-Rajamäki R. Discrete element modelling of pebble packing in pebble bed reactors. Nuclear Engineering and Design. 2014 July 1;273:24-32.

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