RADIONUCLIDE CHARACTERISTICS OF RDE SPENT FUELS

Authors

  • Ihda Husnayani Center for Nuclear Reactor Technology and Safety (PTKRN) - BATAN
  • Pande Made Udiyani Center for Nuclear Reactor Technology and Safety (PTKRN) - BATAN

DOI:

https://doi.org/10.17146/tdm.2018.20.2.4101

Keywords:

RDE, spent fuel, radionuclide activity, thermal power, neutron production, photon releaserates

Abstract

Reaktor Daya Eksperimental (RDE) is a 10 MWth pebble-bed High Temperature Gas-cooled Reactor that is planned to be constructed by National Nuclear Energy Agency of Indonesia (BATAN) in Puspiptek complex, Tangerang Selatan. RDE utilizes low enriched UO2 fuel coated by TRISO layers and loaded into the core by means of multipass loading scheme. Determination of radionuclide characteristics of RDE spent fuel; such as activity, thermal power, neutron and photon release rates; are very important because those characteristics are crucial to be used as a base for evaluating the safety of spent fuel handling system and storage tank. This study is aimed to investigate the radionuclide characteristics of RDE spent fuel at the end of cycle and during the first 5 years cooling time in spent fuel storage. The method used to investigate the radionuclide characteristics is burnup calculation using ORIGEN2.1 code. In performing the ORIGEN2.1 calculation, one pebble fuel was assumed to be irradiated in the core for 5 cycles and then decayed for 5 years. At the end of the fifth cycle, it is obtained that the total activity, thermal power, neutron production, and photon release rates from all radionuclides inside one spent fuel are approximately 105.68 curies, 0.41 watts, 2.65 x 103 neutrons/second, and 1.79 x 104 photons/second, respectively. The results for the radionuclides characteristics during the first 5 years cooling time in the spent fuel storage show that the radioactivity characteristics from all radionuclides are rapidly decreasing at the first year and then slowly decreasing at the second until the fifth year of cooling time. The results obtained in this study can provide data for safety evaluation of fuel handling and spent fuel storage, such as the calculation of sourceterm, radiation dose rate, and the determination of radiation shielding.

References

Tjahjono H. Investigation of RDE thermal parameters changes in response to long-term station black out. Tri Dasa Mega. 2017. 19(2):83-92.

https://doi.org/10.17146/tdm.2017.19.2.3258

Sabharwall P., Bragg-sitton S.M., Stoots C. Challenges in the development of high temperature reactors. Energy Convers. Manag. 2013. 74:574-81.

https://doi.org/10.1016/j.enconman.2013.02.021

Setiadipura T., Irwanto D. Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor. Atom Indonesia. 2015. 41(1):7-15.

https://doi.org/10.17146/aij.2015.350

Zhang Z., Yu S. Future HTGR developments in China after the criticality of the HTR-10. Nucl. Eng. Des. 2002. 218:249-57.

https://doi.org/10.1016/S0029-5493(02)00204-2

Palacio A. Design process for dual-purpose nuclear spent fuel casks. Energy Procedia. 2017. 127(2016):398-406.

https://doi.org/10.1016/j.egypro.2017.08.105

Kuntjoro S., Udiyani P.M. Analisis inventory Reaktor Daya Eksperimental Jenis Reaktor Gas Temperatur Tinggi. Urania. 2016. 22:53-64.

https://doi.org/10.17146/urania.2016.22.1.2745

Jeong H., Chang S.H. Development of a method of evaluating an inventory of fission products for a pebble bed reactor. Ann. Nucl. Energy. 2008. 35(12):2161-71.

https://doi.org/10.1016/j.anucene.2008.10.001

Johnson L., Poinssot C., Lovera P. Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal . Part I : Assessment of the instant release fraction. J. Nucl. Mater. 2005. 346:56-65.

https://doi.org/10.1016/j.jnucmat.2005.04.071

Fuls W.F., Mathews E.H. Passive cooling of the PBMR spent and used fuel tanks. Nucl. Eng. Des. 2007. 237:1354-62.

https://doi.org/10.1016/j.nucengdes.2006.10.013

Jin-hua W., Yi-fan H., Yong T., Bin W.U. Natural safety analysis of the spent fuel residual heat removal in loading and storage process of HTR-10. Energy Procedia. 2013. 39:227-39.

https://doi.org/10.1016/j.egypro.2013.07.209

Ko J., Park J., Jung I., Lee G., Baeg C., Kim T. Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions. Nucl. Eng. Technol. 2014. 46(4):547-56.

https://doi.org/10.5516/NET.08.2013.039

Mohammadi A., Hassanzadeh M., Gharib M. Shielding calculation and criticality safety analysis of spent fuel transportation cask in Reseacrh Reactors. Appl. Radiat. Isot. 2015.

https://doi.org/10.1016/j.apradiso.2015.12.045

Mertyurek U., Gauld I.C. Development of ORIGEN libraries for Mixed Oxide ( MOX ) fuel assembly designs. Nucl. Eng. Des. 2016. 297:220-30.

https://doi.org/10.1016/j.nucengdes.2015.11.027

Husnayani I., Kuntjoro S., Udiyani P.M. Fission products inventory analysis of HTGR fuel. in: Seminar Nasional Teknologi Energi Nuklir. Batam. 2016.

Diecker J. Development of a High Temperature Gas-Cooled Reactor TRISOcoated ….Massachusetts Institute of Technology; 2005.

Tang C., Fu X., Zhu J., Zhao H., Tang Y. Comparison of two irradiation testing results of HTR-10 fuel spheres. Nucl. Eng. Des. 2012. 251:453-8.

https://doi.org/10.1016/j.nucengdes.2011.09.047

Huang P., Liang X., Chen X. The operation characteristics of the fuel handling system of HTR-10. in: International Conference on Nuclear Engineering. China. 2010. pp. 1-7.

https://doi.org/10.1115/ICONE18-29095

Li H., Liu X., Xie F., Jia F. Experimental study on the content and distribution of key nuclides in an irradiated graphite sphere of HTR-10. Nucl. Eng. Des. 2017. 323(March):39-45.

https://doi.org/10.1016/j.nucengdes.2017.07.033

Fernando F., Simões L., Duarte A., Aguiar S., Marcelo C., Lapa F., et al. Advanced nuclear reactors and tritium impacts. Modeling the aquatic pathway. Prog. Nucl. Energy. 2013. 69:9-22.

https://doi.org/10.1016/j.pnucene.2013.02.002

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Published

2018-07-19

How to Cite

Husnayani, I., & Udiyani, P. M. (2018). RADIONUCLIDE CHARACTERISTICS OF RDE SPENT FUELS. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 20(2), 69–76. https://doi.org/10.17146/tdm.2018.20.2.4101