2020, 4 (37)

Operation of nuclear industry facilities

Article NameMolten Salt Reactors with Thermal and Fast Spectrum for Minor Actinides Transmutation
AuthorsO. Ashraf*,**1, G.V. Tikhomirov*2
Address

* Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI, Moscow, Russia

** Department of Physics, Faculty of Education, Ain Shams University, Cairo, Egypt

ORCID iD: 0000-0002-9442-102X

WoS Researcher ID: V-1340-2018

email: osama.ashraf@edu.asu.edu.eg

ORCID iD: 0000-0002-5332-7272

WoS Researcher ID: B-7860-2013

email: gvtikhomirov@mephi.ru

 

AbstractLong-lived minor actinides (MA) like, Neptunium, Americium, and Curium are the major burden of nuclear power. Long-lived MAs have not yet been burned as nuclear fuel. Therefore, the transmutation of long-lived MAs is introduced as an alternative to direct final disposal. In current work, we compare the performance of MA transmutation in a critical Single-fluid Double-zone Thorium-based Molten Salt Reactor (SD-TMSR) and a Small Molten Salt Fast Reactor (SMSFR). We study the dynamic of Keff and core reactivity with different MA loads, shift of the neutron spectrum, time evolution of MA and basic nuclide inventory, as well as the transmutation coefficient (TC). The TC of long-lived MA is calculated using the Monte Carlo code SERPENT-2. The total neutron flux in SD-TMSR and SMSFR can reach 4.1x1014 and 1.8x1015 n/cm2s, respectively. The results show that SD-TMSR consumes about 50% of the generated Pu isotopes in the fuel salt, however, SMSFR consumes about 86.5% of the generated Pu isotopes. During burnup, we apply online reprocessing and refueling, so the core remains critical, and the total mass of fuel in the core and in the blanket is practically constant. The results show that both reactors efficiently transmute 237Np, 241Am, 243Am and 243Cm, while SMSFR has a higher TC than SD-TMSR. TC of total MA reaches 54.84% and 87.97% in SD-TMSR and SMSFR, respectively
Keywordsmolten salt reactor, transmutation, on-line-reprocessing, minor actinides, SERPENT, code Monte-Carlo, transmutation coefficient
LanguageRussian
References
  1. Liu B., Jia R., Han R., Lyu X., Han J., Li W. Minor Actinide Transmutation Characteristics in AP1000 // Annals of Nuclear Energy. 2018. Vol. 115. P. 116-125.
  2. Ramirez J.R., Enriquez P., Castillo R., Alonso G. MOX Fuel Use in a BWR with Extended Power Up-Rate // Annals of Nuclear Energy. 2012. Vol. 50. P. 63-70.
  3. Liu, B., Hu, W., Wang, K., Huang, L., Ouyang, X., Tu, J., Zhu, Y. Transmutation of MA in the High Flux Thermal Reactor // Journal of Nuclear Materials. 2013. Vol. 437. P. 95-101.
  4. Salvatores, M., Slessarev, I., Uematsu, M. A Global Physics Approach to Transmutation of Radioactive Nuclei // Nuclear Science and Engineering. 1994. Vol. 116. P. 1-18.
  5. DoE, U.S. A Technology Roadmap for Generation IV Nuclear Energy Systems. 2002. URL: http://gif. inel. gov/roadmap/pdfs/gen_iv_roadmap. pdf.
  6. Leppänen, J., Pusa, M., Viitanen, T., Valtavirta, V., Kaltiaisenaho, T. The Serpent Monte Carlo code: Status, development and applications in 2013 // Annals of Nuclear Energy. 2014. Vol. 82.
    P. 142-150.
  7. Li, G.C., Cong, P., Yu, C.G., Zou, Y., Sun, J.Y., Chen, J.G., Xu, H.J. Optimization of Th-U Fuel Breeding Based on a Single-Fluid Double-Zone Thorium Molten Salt Reactor // Progress in Nuclear Energy. 2018. Vol. 108. P. 144-151.
  8. Robertson, R.C. CONCEPTUAL DESIGN STUDY OF A SINGLE-FLUID MOLTEN-SALT BREEDER REACTOR. (No. ORNL-4541). comp.; Oak Ridge National Lab., Tenn. 1971.
  9. Nuttin, A., Heuer, D., Billebaud, A., Brissot, R., Le Brun, C., Liatard, E., Loiseaux, J.M., Mathieu, L., Meplan, O., Merle-Lucotte, E., Nifenecker, H. Potential of Thorium Molten Salt Reactorsdetailed Calculations and Concept Evolution with a View to Large Scale Energy Production // Progress in Nuclear Energy. 2005. Vol. 46. P. 77-99.
  10. Mukaiyama, T., Yoshida, H., Ogawa, T. Minor Actinide Transmutation in Fission Reactors and Fuel Cycle Considerations. «Use of Fast Reactors for Actiniae Transmutation. Proceedings of a Specialists Meeting held in Obninsk, Russian Federation, 22-24 September 1992». Vienna. 1993.
  11. Ashraf, O., Rykhlevskii, A., Tikhomirov, G.V., Huff, K.D. Whole Core Analysis of the Single-Fluid Double-Zone Thorium Molten Salt Reactor (SD-TMSR) // Annals of Nuclear Energy. 2020. Vol. 137. P. 107115.
  12. Yu, C., Li, X., Cai, X., Zou, C., Ma, Y., Han, J., Chen, J. Analysis of Minor Actinides Transmutation for a Molten Salt Fast Reactor // Annals of Nuclear Energy. 2015. Vol. 85. P. 597-604.
  13. Ashraf, O., Rykhlevskii, A., Tikhomirov, G.V., Huff, K.D. Strategies for Thorium Fuel Cycle Transition in the SD-TMSR // Annals of Nuclear Energy. 2020. Vol. 148. P. 107656.
Papers68 - 81
URL ArticleURL Article
 Open Article