عنوان مقاله [English]
نویسندگان [English]چکیده [English]
The management of waste produced in the reactor is an essential aspect of the nuclear fuel cycle. In this research, it has been tried to reduce the amount of reactor waste at the end of the cycle without substantial changes in the fuel dimension and the core structure of the research reactor. Minimized the heat generation. The MCNPX2.6 code is used to calculate the fuel consumption and neutronic parameters of the reactor core. The results show that without any significant change in the structure of the reference core, the amount of waste decreases only by increasing the fuel enrichment and reducing the reactor power. In this study, two core models are proposed and investigated. The waste activity at the end of the cycle in the converted reactor cores reaches 15% -19% of its original value in the reference core. Moreover, fuel burn- up has increased up to 32% -40% relative to the reference core.
1. M. Massie, A generalized optimization methodology for isotope management, Master of Science, MIT, (2010).
2. D. Serfontein, et al, Optimization of deep burn incineration of reactor waete plotunium in a PBMR DPP-400 core, Nuclear Engineering and Design, 271, 99-105 (2014).
3. A. Acir, H. Coskun, Monte Carlo calculations on transmutation of plutonium and minor actinides of pebble bed high temperature reactor, Progress in Nuclear Energy, 48, 45–50 (2013).
4. C.S. Gil, et al, Review of Integral Experiments for Minor Actinide Management, NEA No. 7222, (2015).
5. A. Griffin-Chahid, et al, Physics and Safety of Transmutation Systems, NEA No. 6090 (2006).
6. A. Acir, H. Coskun, Neutronic analysis of the PBMR-400 full core using thorium fuel mixed with plutonium or minor actinides, Annals of Nuclear Energy, (2012).
7. S. Sahin, Power flattening in a hybrid blanket using nuclear waste actinides, Kerntechnik, 53, 285-290 (1989).
8. S. Sahin, et al, Criticality and burnup evolutions of the fixed bed nuclear reactor with alternative fuels, Energy Conversion and Mamagment, 51, 1781-1787 (2010).
9. F. Faghihi, et al, Level-1 Probability Safety Assessment of the Iranian Heavy Water Reactor Using SAPHIRE Software, Reliability Engineering and System Safety, 93, 1377-1409 (2008).
10. D.B. Pelowitz, MCNPXTM user’s manual, Los Alamos National Laboratory, (2008).
11. I. Bratton, Modeling and Validation of the Fuel Depletion and Burn up of the OSU Research Reactor Using MCNPX/CINDER’90, MS thesis in Nuclear Engineering, Ohio State University, (2012).
12. F. Mansourzadeh, F. Khoshahval, J. Safdari, A conceptual design for a generic heavy water research reactor to a more proliferation-resistant reactor, Annals of Nuclear Energy, 112, 418-430 (2018).
13. E3/EU+3, Joint Comprehensive Plan of Action, Vienna, (2015).
14. M. Benedict, T.H. Pigford, H. Wolfganglevi, Nuclear Chemical Engineering, New York: McGraw-Hill book Co., (1981).