Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor

Open access


The paper presents a neutronic analysis of the battery-type 20 MWth high-temperature gas cooled reactor. The developed reactor model is based on the publicly available data being an ‘early design’ variant of the U-battery. The investigated core is a battery type small modular reactor, graphite moderated, uranium fueled, prismatic, helium cooled high-temperature gas cooled reactor with graphite reflector. The two core alternative designs were investigated. The first has a central reflector and 30×4 prismatic fuel blocks and the second has no central reflector and 37×4 blocks. The SERPENT Monte Carlo reactor physics computer code, with ENDF and JEFF nuclear data libraries, was applied. Several nuclear design static criticality calculations were performed and compared with available reference results. The analysis covered the single assembly models and full core simulations for two geometry models: homogenous and heterogenous (explicit). A sensitivity analysis of the reflector graphite density was performed. An acceptable agreement between calculations and reference design was obtained. All calculations were performed for the fresh core state.

[1] World Nuclear Association: (accessed 5 Oct. 2017).

[2] Nuclear Energy Institute: (accessed 05 Oct. 2017).

[3] International Nuclear Energy Agency: Advances in smal l modular reactor technology developments. IAEA, Vienna 2014.

[4] International Nuclear Energy Agency: Approaches for Assessing the Economic Competitiveness of Smal l and Medium Sized Reactors. IAEA Nuclear Energy Ser. NPT-3.7, 2013.

[5] Rowiński M.K., White T.J., Zhao J.: Smal l and medium sized reactors (SMR): A review of technology. Renewable and Sustainable Energy Rev. 44(2015), 643-656.

[6] NNL: Smal l Modular Reactors (SMR) Feasibility Study. National Nuclear Laboratory Rep., Dec. 2014.

[7] Ding M., Kloosterman J.L., Kooijman T., Linssen R., Abram T., Marsden B., Wickham T.: Design of U-Battery. Delft, 2011.

[8] World Nuclear Association: (accessed 05 Oct. 2017).

[9] Ding M., Kloosterman J.L.: Neutronic feasibility design of a smal l long-life HTR. Nucl. Eng. Des. 241(2011), 12, 5093-5103.

[10] Ding M., Kloosterman J.L.: Thermal-hydraulic design and transient evaluation of a smal l long-life HTR. Nucl. Eng. Des. 255(2013), 347-358.

[11] High temperature Gas Cooled Reactor Fuels and Material. IAEA, 2010.

[12] Gas turbine-modular helium reactor (GT-MHR) conceptual design description report.Tech. Rep., General Atomics, 1996.

[13] Zwaan S.J. de: Feasibility Study of the U-Battery, PNR-131-2007-004, 2007.

[14] History and Evolution of the HTGR. General Atomic, 2007.

[15] IAEA Current status and future development of modular high temperature gas cooled reactor technology. IAEA, 2001.

[16] Prismatic coupled neutronic/thermal fluids transient benchmark of the MHTGR MW core design, Benchmark definition 2011.

[17] Ortensi J., Cogliati J.J., Pope M.A., Bess J.D., Ferrer R.M., Bingham A.A., Ougouag A.M.: Deterministic Modeling of the High Temperature Test Reactor. INL Rep., 2010.

[18] Leppänen J.: Serpent - A Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code, Manual, 2015.

[19] Kaltiaisenaho T.: Statistical Tests and the Underestimation of Variance in Serpent 2, Res. Rep., 2014.

[20] Samul K., Strupczewski A., Wrochna G.: Smal l Modular Reactors (SMR). Rap. National Centre for Nuclear Research, Świerk 2013.

[21] National Centre for Nuclear Research: (accessed 05 Oct. 2017).

[22] Leppänen J.: Development of a New Monte Carlo Reactor Physics Code. D.Sc. Thesis, VTT Publication 640, Helsinki University of Technology, 2007.

[23] SERPENT Monte Carlo Code Development Status: (accessed 30 Aug. 2017).

[24] Stanisz P., Malicki M., Kopeć M.: Validation of VHTRC calculation benchmark of critical experiment using the MCB code. SEED 2016 Conf., E3S Web of Conf. 10, 00123, 2016.

[25] Brown F.B., MatrinW.R., JeiW., Conlin J.L., Lee J.C.: Stochastic Geometry and HTGR Modeling with MCNP5. Los Alamos National Laboratory Rep. LA-UR-04-8668, 2005.

[26] Brown F.B.: A Review of Best Practices for Monte Carlo Criticality Calculations. Los Alamos National Laboratory Rep. LA-UR-09-03134, 2009.

Archives of Thermodynamics

The Journal of Committee on Thermodynamics and Combustion of Polish Academy of Sciences

Journal Information

CiteScore 2016: 0.54

SCImago Journal Rank (SJR) 2016: 0.319
Source Normalized Impact per Paper (SNIP) 2016: 0.598


All Time Past Year Past 30 Days
Abstract Views 0 0 0
Full Text Views 399 344 29
PDF Downloads 150 140 11