Whole core analysis of BEAVRS benchmark for hot zero Power condition using MVP3 with JENDL-5

Abstract

ABSTRACTWith the release of the latest Japanese evaluated nuclear data library JENDL-5, the prediction accuracy of JENDL-5 for neutronics parameters of the BEAVRS benchmark for the hot zero power condition was evaluated in this study. The criticality, control rod bank worth (CRW), isothermal temperature coefficient (ITC), and in-core detector signals were calculated and compared with the measured data for evaluation. For the criticality, the calculation-to-measurement (C/E) values varied between 1.0001 and 1.0045. Sensitivity analysis by replacing cross section data from the JENDL-4.0u1 with JENDL-5 revealed that 1H, 235U, 238U, and 16O significantly affected the criticality. The individual CRW agreed within 50 pcm, and total CRW also agreed within 100 pcm from the measured values. The ITC results calculated with a temperature deviation of 5.56 K case were negatively overestimated comparing with the measured values; whereas those of with 2.78 K were improved and agreed with the measured values within a standard deviation. The axial detector signals indicated a maximum relative error of 4.46% and the root mean squared error (RMSE) of 2.13%. The differences between the previous version of JENDL-4.0u1 and JENDL-5 were also investigated.DisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. AcknowledgementsThe authors thank Dr. Kenichi Tada of JAEA for the support in the handling FRENDY code, such as formatted cross section generation and plotting.Figure 1. Fuel assembly (Asm.), burnable absorber, and control rod bank layout (quarter rotational symmetry) [Citation28].Display full sizeFigure 2. Instrument tube positions [Citation28].Display full sizeFigure 3. Whole core calculation model of the horizontal plane at the axial mid-plane.Display full sizeFigure 4. Whole core calculation model of the vertical plane at the core center.Display full sizeFigure 5. Comparison of criticality between JENDL-4.0u1 and JENDL-5 for six cases with different boron concentrations and control rod bank conditions.Display full sizeFigure 6. Comparison of neutron spectra between JENDL-4.0u1 and JENDL-5 in ARO (D = 213 steps) case.Display full sizeFigure 7. Nuclide Substitution Reactivity of JENDL-4.0u1 with JENDL-5.Display full sizeFigure 8. Comparison of scattering cross sections of TSL data for 1H in H2O between JENDL-4.0u1 and JENDL-5.Display full sizeFigure 9. Comparison of capture cross sections of 16O between JENDL-4.0u1 and JENDL-5.Display full sizeFigure 10. Comparison of fission and capture cross sections of 235U between JENDL-4.0u1 and JENDL-5.Display full sizeFigure 11. Comparison of fission and capture cross sections of 238U between JENDL-4.0u1 and JENDL-5.Display full sizeFigure 12. Comparison of fission and capture reaction rates of 235U between JENDL-4.0u1 and JENDL-5.Display full sizeFigure 13. Comparison of fission and capture reaction rates of 238U between JENDL-4.0u1 and JENDL-5.Display full sizeFigure 14. Reactivity difference between the calculated and measured values for each control rod bank.Display full sizeFigure 15. Comparison of ITC between calculated and measured values for each control rod bank insertion condition.Display full sizeFigure 16. Comparison of axially integrated detector signals between the calculated results of JENDL-4.0u1 and measured values.Display full sizeFigure 17. Comparison of axially integrated detector signals between the calculated results of JENDL-5 and measured values.Display full sizeFigure 18. Comparison of detector signal axial distribution between the calculated results and measured values in fuel assembly g8 (original assembly j8).Display full sizeFigure 19. Comparison of detector signal axial distribution between the calculated results and measured values in fuel assembly e13 (original assembly c5).Display full sizeTable 6. Comparison of control rod bank worth between calculation results and measurement data.Download CSVDisplay TableTable 7. Comparison of ITC between calculation results and measurement data.Download CSVDisplay TableTable 8. Comparison of ITC, MTC, and FTC of JENDL-4.0u1 and JENDL-5 in control rod bank C and D insertion case.Download CSVDisplay Table