ANALYSIS OF THORIUM PIN CELL BURN UP OF THE PWR USING WIMS CODE
DOI: http://dx.doi.org/10.17146/tdm.2022.24.2.6626
Abstract
A thorium-fueled benchmark comparison was made in this study between state-of-the-art codes, WIMSD-5B code to MOCUP (MCNP4B + ORIGEN2), and CASMO-4 for burnup calculations as part of efforts to examine the possible benefits of using thorium in PWR fuel. WIMSD-5B calculations employ the same model as a reference, MOCUP, and CASMO, however, there are some variances in methodology and cross-section libraries. On a PWR pin cell model, eigenvalue and isotope concentrations were examined up to high burnup. The eigenvalue comparison as a function of burnup is good, with a maximum difference of less than 5% and an average absolute difference of less than 1%. The isotope concentration comparisons outperform a set of ThO2-UO2 fuel benchmarks and are comparable to a set of uranium fuel benchmarks previously published in the literature. As a function, the eigenvalue comparison The actinide and fission product data sources for a typical thorium fuel are reported in the WIMSD-5B burnup calculations. The reasons for discrepancies in coding are examined and explored.
Keywords: Thorium, PWR Fuel, Burn up, Pin Cell, WIMSD-5B
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- Pinem S., Sembiring T.M., Surbakti T. Core Conversion Design Study of TRIGA Mark 2000 Bandung using MTR Plate Type Fuel Element. Int. J. Nucl. Energy Sci. Technol. 2018. 12(3):222-238.
- Surbakti T., Purwadi P. Analysis of Neutronic Safety Parameters of the Multi-Purpose Reactor–Gerrit Augustinus Siwabessy (RSG-GAS) Research Reactor at Serpong. J. Penelit. Fis. dan Apl. 2019. 9(1):78-91.
- Surian P., Tagor M. S., Tukiran S. Verifikasi Program PWR-fuel Dalam Manajemen Bahan Bakar PWR. JSTNI. 2015. 16(1): 53-62.
- Dawahra S., Khattab K., Saba G. Extending the Maximum Operation Time of the MNSR Reactor. Appl. Radiat. Isot. 2016. 115:256-261.
- Dawahra S., Khattab K., Saba G. Calculation and Comparison of Xenon and Samarium Reactivities of the HEU, LEU Core in the Low Power Research Reactor. Appl. Radiat. Isot. 2015. 101:27–32.
- Surbakti T., Pinem S., Suparlina L. Dynamic Analysis of the Safety Criteria of the Conceptual Core Design in MTR-type Research Reactor. Atom Indonesia. 2018. 44(2):89-97.
- Surbakti T., Pinem S., Sembiring T.M., Hamzah A., Nabeshima K. Calculation of Control Rods Reactivity Worth of RSG-GAS First Core using Deterministic and Monte Carlo Methods. Atom Indonesia. 2019. 45(2):69–79.
- Pinem S., Sembiring T.M., Liem P.H. Neutronic and Thermal-hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor. 2016. 42(3):123–128.
- Iman K., Surian P., Tagor M.S., and Tukiran S. Evaluation of Fuel Loading Pattern of PWR Core Using PWR-FUEL Code. : AIP Conference Proceedings. 2019. 2180,020007.
- Hend S., Moustafa A., Riham R., Hesham M. Core Neutronic Characterization of Advanced Pressurized Water Reactor. Journal of Nuclear and Particle Physics. 2021. 11(1): 7-14.
- Zakir, M., Sarkar M., and Hossain A. Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR). World Journal of Nuclear Science and Technology. 2019. 9: 74-83.
- Nicholas R.B., Hans L., Arnold A., Gilad R., Michael T. Neutronic Evaluation of a PWR with Fully Ceramic Microencapsulated Fuel. Part II: Nodal Core Calculations and Preliminary Study of Thermal-Hydraulic Feedback. Annals of Nuclear Energy. 2013. 62: 548-557.
- Pinem S., et al. PWR Fuel Macroscopic Cross Section Analysis for Calculation Core Fuel Management Benchmark. 2019. J. Phys.: Conf. Ser. 1198 022065.
- Surian Pinem et al. Reactivity Coefficient Calculation for AP1000 Reactor Using the NODAL3 Code. 2018. J. Phys.: Conf. Ser. 962 012057.
- Surbakti T., Imron M. Fuel Burn-up Calculation for Working Core of the RSG-GAS Research Reactor at Batan Serpong. J. Penelit. Fis. dan Apl. 2017. 7(2):89-101.
- Michael A.P., Sen R. S., Abderrafi M.O., Gilles Y., Brian B. Neutronic Analysis of the Burning of Transuranics in Fully Ceramic Micro-encapsulated Tri-isotropic Particle-fuel in a PWR. Nuclear Engineering and Design. 2012. 252: 215-225.
- Pinem S., Surbakti T., Sembiring T., et al. Optimization of Radioisotope Production at RSG-GAS Reactor using Deterministic Method. Journal Teknologi Indonesia. 2016. 1 (2):12-18.
- Tukiran S, Surian P, Farisy Y. Calculation of PWR Thorium Pin Cell Burnup and Isotope Prediction Using WIMSD-5B Code. Journal of Physics: Conference Series 1811. 2021. 012047