Analysis of the Reactivity Coefficient of the PWR Thorium Fuel
Keywords:
Reactivity coefficient, PWR, Moderator, Thorium fuel, WIMSD-5BAbstract
In design, control, and safety, especially in Pressurized Water Reactors, the Reactivity Coefficient parameter is crucial. The validation of every new library for an accurate parameter prediction is then crucial. The purpose of this work is to determine the value of the reactivity coefficient at the Beginning of the Cycle (BOC) and End of the Cycle (EOC) using the WIMSD code based on ENDF/B-VIII.0 nuclear data files. The PWR-1175 MWe experiment critical reactors, which use Th-UO2 fuel pellets, are a set of light water-moderated lattice experiments that were used for this purpose. The study applied the new cross-section libraries for WIMSD-5B with ENDF/B-VIII.0 lattice code. The results showed that the fuel temperature reactivity coefficients for the PWR reactor at BOC and EOC using new libraries are –4.07 pcm/K and –2.72 pcm/K, respectively. Moderator Temperature Reactivity Coefficient at BOC and EOC are -1.8E-03 pcm/K and 3.73 pcm/K, respectively. Compared to the experimental data of the reactor core, the difference is in the range of 5.0%. It can be concluded that for the PWR using thorium fuel as a model, all reactivity coefficients are negative and it is a good design for the safety of operation.
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 (RSGGAS) Research Reactor at Serpong. J. Penelit. Fis. dan Apl. 2019. 9(1):78-91.
3. Liem P.H., Surbakti T., Hartanto D. Kinetics Parameters Evaluation on the First Core of the RSG GAS (MPR-30) using Continuous Energy Monte Carlo Method. Prog. Nucl. Energy. 2018. 109(June):196–203.
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 on 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. Surbakti T., Pinem S., Sembiring T.M., Subekti M., Sunaryo G.R. Preliminary Study for Alternative Conceptual Core Design of the MTR Research Reactor. J. Phys. Conf. Ser. 2018. 962(1).
10. Hedayat A. Benchmarking Verification of the Control Rod Effects on the MTR Core Parameters using the MTR-PC and MCNP Codes throughout 3D Core Modeling and Rod-drop Experiment. Prog. Nucl. Energy. 2016. 88:183-190.
11. Liu Z., Smith K., Forget B. Calculation of Multi-group Migration Areas in Deterministic Transport Simulations. Ann. Nucl. Energy. 2020. 140:107-110.
12. Wang C., Liu L., Liu M., Zhang D., Tian W., Qiu S., et al. Conceptual Design and Analysis of Heat Pipe Cooled Silo Cooling System for the Transportable Fluoride-salt-cooled High-temperature Reactor. Ann. Nucl. Energy. 2017. 109.
13. Pinem S., Liem P.H., Sembiring T.M., Surbakti T. Fuel Element Burnup Measurements for the Equilibrium LEU Silicide RSG GAS (MPR-30) Core under a New Fuel Management Strategy. Ann. Nucl. Energy. 2016. 98.
14. Villarino E.A., Mochi I. Thermal-hydraulic Models for Neutronic and thermal-hydraulic Feedback in Citvap Code. 2014. 23:23-36.
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. 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.
17. Valtavirta V., Leppänen J., Viitanen T. Coupled Neutronics–fuel Behavior Calculations in Steady State using the Serpent 2 Monte Carlo Code. Ann. Nucl. Energy. 2017. 100.
