Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source

Oettingen, Mikołaj; Stanisz, Przemysław

doi:10.2478/nuka-2018-0011

Abstract

This paper describes the methodology developed for the numerical reconstruction and modelling of the thorium-lead (Th-Pb) assembly available at the Department of Nuclear Energy, Faculty of Energy and Fuels, AGH University, Krakow, Poland. This numerical study is the first step towards integral irradiation experiments in the Th-Pb environment. The continuous-energy Monte Carlo burnup (MCB) code available on supercomputer Prometheus of ACK Cyfronet AGH was applied for numerical modelling. The assembly consists of a hexagonal array of ThO₂ fuel rods and metallic Pb rods. The design allows for different arrangements of the rods for various types of irradiations and experimental measurements. The intensity of the fresh neutron source intended for integral experiments is about 10⁸ n/s, which corresponds to the mass of about 43 μg ²⁵²Cf. The source was modelled in the form of Cf₂O₃-Pd cermet wire embedded in two stainless steel capsules.

References

1. International Atomic Energy Agency. (2012). Role of thorium to supplement fuel cycles of future nuclear energy systems. Vienna: IAEA. (Nuclear Energy Series No. NF-T-2.4).
Search in Google Scholar Back to article
2. Serfontein, D. E., & Mulder, E. J. (2014). Thorium-based fuel cycles: Reassessment of fuel economics and proliferation risk. Nucl. Eng. Des., 271, 106–113.10.1016/j.nucengdes.2013.11.018
Search in Google Scholar Back to article
3. Vijayan, P., Shivakumar, V., Basu, S., & Sinha, R. (2017). Role of thorium in the Indian nuclear power programme. Prog. Nucl. Energy, 101(Pt A), 43–52.10.1016/j.pnucene.2017.02.005
Search in Google Scholar Back to article
4. Abdel-Khalik, S. I., Haldy, P. A., & Kumar, A. (1984). Blanket design and calculated performance for the Lotus Fusion-Fission Hybrid Experimental Devices Test Facility. Fusion Sci. Technol., 2, 189–208.10.13182/FST84-A23093
Open DOI Search in Google Scholar Back to article
5. Bhabha Atomic Research Centre. [access: 10.11.2017], www.barc.gov.in/randd/index.html.
Search in Google Scholar Back to article
6. Oettingen, M., Cetnar, J., & Mirowski, T. (2015). The MCB code for numerical modeling of fourth generation nuclear reactors. Computer Sci., 16(4), 329–350.10.7494/csci.2015.16.4.329
Search in Google Scholar Back to article
7. X-5 Monte Carlo Team. (2005). MCNP – A General Monte Carlo N-Particle Transport Code, Version 5. LANL. (Report LA-UR-03-1987).
Search in Google Scholar Back to article
8. Cetnar, J. (2006). Solution of Bateman equations for nuclear transmutations. Ann. Nucl. Energy, 33, 640–645.10.1016/j.anucene.2006.02.004
Search in Google Scholar Back to article
9. McConn, R. J. Jr, Gesh, C. J., Pagh, R. T., Rucker, R. A., & Williams III, R. G. (2011). Radiation portal monitor project, compendium of material composition data for radiation transport modeling. Revision 1. Pacific Northwest National Laboratory. (PIET-43741-TM-963, PNNL-15870).10.2172/1023125
Search in Google Scholar Back to article
10. Morss, L. R., Edelstein, N. M., & Fuger, J. (2010). The chemistry of the actinide and transactinide elements (4th ed.). Dordrecht: Springer.10.1007/978-94-007-0211-0
Search in Google Scholar Back to article
11. ACK Cyfronet AGH. [access: 10.11.2017], KDM. www.cyfronet.krakow.pl/portal/Prometheus.
Search in Google Scholar Back to article
12. Martin, R. C., Knauer, J. B., & Balo, P. A. (2000). Production, distribution and applications of californium-252 neutron sources. Appl. Radiat. Isot., 53, 785–792.10.1016/S0969-8043(00)00214-1
Search in Google Scholar Back to article
13. Liu, Z., Yang, C., Yang, Y., Zheng, L., & Rong, L. (2018). Measurement and analysis of ²³²Th(n,2n)²³¹Th reaction rate in the thorium oxide cylinder with a D-T neutron. Ann. Nucl. Energy, 111, 660–665.10.1016/j.anucene.2017.06.041
Search in Google Scholar Back to article
14. Mohapatra, D. K., Singh, S. S., Riyas, A., & Mohanakrishnan, P. (2013). Physics aspects of metal fuelled fast reactors with thorium blanket. Nucl. Eng. Des., 265, 1232–1237.10.1016/j.nucengdes.2013.09.002
Search in Google Scholar Back to article
15. Kooyman, T., & Buiron, L. (2016). Neutronic and fuel cycle comparison of uranium and thorium as matrix for minor actinides bearing-blankets. Ann. Nucl. Energy, 92, 61–71.10.1016/j.anucene.2016.01.020
Open DOI Search in Google Scholar Back to article

Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source

Abstract

Paradigm

My account