Study on the Ability of PCMSR to Produce Valuable Isotopes as a By Product of Energy Generation
DOI:
https://doi.org/10.24246/ijpna.v3i1.7-14Keywords:
PCMSR, fission product, valuable nuclidesAbstract
PCMSR (Passive Compact Molten Salt Reactor) is a variant of MSR (Molten Salt Reactor) type reactors. The MSR is one type of the Advanced Nuclear Reactor types. PCMSR uses mixtures of fluoride salt if the liquid form is in a high temperature operation. The use of liquid salt fuel allows the application of on line fuel processing system. The on line fuel processing system allows extraction of several valuable fission product isotopes such as Mo-99, Cs-137, Sr-89 etc. The capability of MSR to produce several valuable isotopes has been studied. This study is based on a denaturized breeder MSR design with 920 MWth of thermal power and 500 MWe of electrical output power with the thermal efficiency of 55 %. The initial composition of fuel salt is 70 % of a mole of LiF, 24 % of a mole of 232ThF4, 6 % of a mole of UF4. The enrichment level of U is 20 % of a mole of U-235. The study is performed by a numerical calculation to solve a set of differential equations of fission product balance. This calculation calculates fission product generation due to fission reaction, precursor decay, and fission product annihilation due to decay, neutron absorption, and extraction. The calculation result shows that in quasi equilibrium conditions, the reactor can produce several valuable isotopes in substantially sufficient quantities, those are Sr-89 (0.3 kCi/MWth/day, Sr-90 (1,91 Ci/MWth/day), Mo-99 (1.7 kCi/MWth/day), I-131 (0.42 kCi/MWth/day), I-132 (0.782 kCi/MWth/day), I-133 (1.12 kCi/MWth/day), Xe-133 (11.8 Ci/MWth/day), Cs-134 (39.3 mCi/MWth/day), Cs-137 (2.32 Ci/MWth/day) and La-140 (1.05 kCi/MWth/day).
Downloads
References
World Energy Resources and Consumption – Wikipedia, free encyclopedia, Chapter 1. Consumption
IAEA and OECD-NEA (2014) Uranium 2014: Resources, Production and Demand, A Joint Report by OECD Nuclear Energy Agency and the International Atomic Energy Agency, Paris,p.20.
IAEA (2015) Nuclear Power Reactors in the World, Reference Data Series No. 2, 2015 ed.,International Atomic Energy Agency, Vienna, pp.11–20
Zittel, W. and Schindler, J (2006) Uranium Resources and Nuclear Energy, EWG Paper No 1-06, Energy Watch Group, Berlin
IAEA, 2008, Homogeneous Aqueous Solution Nuclear Reactors for the Production of Mo-99 and Other Short Lived Radioisotopes, IAEA Tecdoc 1601, IAEA, Vienna, 2008
Luccote, E.M., Heuer, D., Allibert, M., Ghetta, V., Le Burn, C., Brissot, R., Liatard, E., Mathieu, M., 2007, the thorium molten salt reactor: Launching the thorium cycle while closing the current fuel cycle, HAL archives.
Harto. A., 2015, Sustainable Criticality Analysis Of PCMSR Fuel Using Thorium As Sustainable Fuel And Low Enrich Uranium As Starting Fuel, International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 9, No. 3 (2015) pp. 224 - 237.
Benes, O., Cabet, C., Delpech, S., Hosnedl, P., Ignatiev, P., Konings, R., Lecarpentier, D., Matal, O., Merle-Lucotte, E., Renault, C., Uhlir, J., 2009, Aseessment of Liquid salts for Innovative Application ALISIA Deliverable (D-50), Review Report on Liquid Salts for Various Applications
Forsbeg, C. W., Peterson, P. F., Zhao, H.H., 2004, An Advanced Molten Salt Reactor Using High Temperature Reactor Technology, ICAPP.2004.MSR.Paper, 2004 International Congress on Advanced in Nuclear Power Plants (ICAPP’04) Embedded International Topical Meeting, 2004 American Nuclear Society Annual Meeting, Pittsburgh, Pennsylvania
Parrish Staples, 2010, Global Threat Reduction Initiative, IAEA Consultancy Meeting on Conversion Planning for Mo-99 Production Facilities from HEU to LEU
Downloads
Published
How to Cite
Issue
Section
License
Indonesian Journal of Physics and Nuclear Applications is licensed under a Creative Commons Attribution 4.0 International License.
