ANALYSIS OF THORIUM PIN CELL BURN UP OF THE PWR USING WIMS CODE

Jonny Haratua Panggabean, Santo Paulus Rajagukguk, Syaiful Bakhri

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  

 


Full Text:

PDF

References


  1. 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.
  2. 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.
  3. Surian P., Tagor M. S., Tukiran S. Verifikasi Program PWR-fuel Dalam Manajemen Bahan Bakar PWR. JSTNI. 2015. 16(1): 53-62.
  4. Dawahra S., Khattab K., Saba G. Extending the Maximum Operation Time of the MNSR Reactor. Appl. Radiat. Isot. 2016. 115:256-261.
  5. 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.
  6. 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.
  7. 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.
  8. 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.
  9. 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.
  10. 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.
  11. 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.
  12. 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.
  13. Pinem S., et al. PWR Fuel Macroscopic Cross Section Analysis for Calculation Core Fuel Management Benchmark. 2019. J. Phys.: Conf. Ser. 1198 022065.
  14. Surian Pinem et al. Reactivity Coefficient Calculation for AP1000 Reactor Using the NODAL3 Code. 2018. J. Phys.: Conf. Ser. 962 012057.
  15. 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.
  16. 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.
  17. 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.
  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


Refbacks



PTKRN Digital Library Mendeley
slot gacor slot