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Konno, Chikara; Ota, Masayuki*; Kwon, Saerom*; Onishi, Seiki*; Yamano, Naoki*; Sato, Satoshi*
Journal of Nuclear Science and Technology, 60(9), p.1046 - 1069, 2023/09
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)JENDL-5 was validated from a viewpoint of shielding applications under the Shielding Integral Test Working Group of the JENDL Committee. The following benchmark experiments were selected: JAEA/FNS in-situ experiments, Osaka Univ./OKTAVIAN TOF experiments, ORNL/JASPER sodium experiments, NIST iron experiment and QST/TIARA experiments. These experiments were analyzed with MCNP and nuclear data libraries (JENDL-5, JENDL-4.0 or JENDL-4.0/HE, ENDF/B-VIII.0 and JEFF-3.3). The analysis results demonstrate that JENDL-5 is comparable to or better than JENDL-4.0 or JENDL-4.0/HE, ENDF/B-VIII.0 and JEFF-3.3.
Tada, Kenichi; Nagaya, Yasunobu; Taninaka, Hiroshi; Yokoyama, Kenji; Okita, Shoichiro; Oizumi, Akito; Fukushima, Masahiro; Nakayama, Shinsuke
Journal of Nuclear Science and Technology, p.1 - 21, 2023/04
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)The new version of the Japanese evaluated nuclear data library, JENDL-5, was released in December 2021. This paper demonstrates the validation of JENDL-5 for fission reactor applications. Benchmark calculations are performed with the continuous-energy Monte Carlo codes MVP and MCNP and the deterministic code system MARBLE. The benchmark calculation results indicate that the performance of JENDL-5 for fission reactor applications is better than that of the former library JENDL-4.0.
Yokoyama, Kenji
EPJ Web of Conferences, 281, p.00004_1 - 00004_10, 2023/03
In Japan, development of adjusted nuclear data library for fast rector application based on the cross-section adjustment method has been conducted since the early 1990s. The adjusted library is called the unified cross-section set. The first version was developed in 1991 and is called ADJ91. Recently, the integral experimental data were further expanded to improve the design prediction accuracy of the core loaded with minor actinoids and/or degraded Pu. Using the additional integral experimental data, development of ADJ2017 was started in 2017. In 2022, the latest unified cross-section set AJD2017R was developed based on JENDL-4.0 by using 619 integral experimental data. An overview of the latest version with a review of previous ones will be shown. On the other hand, JENDL-5 was released in 2021. In the development of JENDL-5, some of the integral experimental data used in ADJ2017R were explicitly utilized in the nuclear data evaluation. However, this is not reflected in the covariance data. This situation needs to be considered when developing a unified cross-section set based on JENDL-5. Preliminary adjustment calculation based on JENDL-5 is performed using C/E (calculation/experiment) values simply evaluated by a sensitivity analysis. The preliminary results will be also discussed.
Yanagisawa, Hiroshi; Umeda, Miki; Motome, Yuiko; Murao, Hiroyuki
JAEA-Technology 2022-030, 80 Pages, 2023/02
JAEA-Technology-2022-030.pdf:2.57MB
Nuclear criticality benchmark analyses were carried out for TRIGA-type reactor systems in which uranium-zirconium hydride fuel rods are loaded by using the continuous-energy Monte Carlo code MVP with the evaluated nuclear data library JENDL-5. The analyses cover two sorts of benchmark data, the IEU-COMP-THERM-003 and IEU-COMP-THERM-013 in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook, and effective neutron multiplication factors, reactivity worths for control rods etc. were calculated by JENDL-5 in comparison with those by the previous version of JENDL. As the results, it was confirmed that the effective neutron multiplication factors obtained by JENDL-5 were 0.4 to 0.6% greater than those by JENDL-4.0, and that there were no significant differences in the calculated reactivity worths by between JENDL-5 and JENDL-4.0. Those results are considered to be helpful for the confirmation of calculation accuracy in the analyses on NSRR control rod worths, which are planned in the future.
Watanabe, Tomoaki; Tada, Kenichi; Endo, Tomohiro*; Yamamoto, Akio*
Journal of Nuclear Science and Technology, 11 Pages, 2023/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)The burnup calculations for estimating the nuclide composition of the spent fuel are highly dependent on nuclear data. Many nuclides in the latest version of the Japanese Evaluated Nuclear Data Library JENDL-5 were modified from JENDL-4.0 and the modification affects the burnup calculations. This study confirmed the validity of JENDL-5 in the burnup calculations. The PIE data of Takahama-3 was used for the validation. The effect of modifications of the parameters, e.g., cross sections and fission yields, from JENDL-4.0 to JENDL-5 on the nuclide compositions was quantitatively investigated. The calculation results showed that JENDL-5 has a similar performance to JENDL-4.0. The calculation results also revealed that the modifications of the cross sections of actinide nuclides, fission yields, and thermal scattering low data of hydrogen in H
O affected the nuclide compositions of PWR spent fuels.
Nakayama, Shinsuke
Journal of Nuclear Science and Technology, p.1 - 7, 2023/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)The d+Be neutron source is a candidate for transportable neutron source for on-site nondestructive inspection of infrastructure facilities such as bridges, tunnels and so on. The applicability of the d+Be neutron source to a transportable fast neutron source is explored by Monte Carlo particle transport simulations with PHITS and JENDL-5. The simulation results show that by increasing the shielding thickness by about 1.5 times, it is possible to realize the d+Be neutron source with the comparable performance to another candidate, the 2.5-MeV p+Li neutron source, at lower beam energy.
Nagaya, Yasunobu; Yokoyama, Kenji; Tada, Kenichi; Konno, Chikara
no journal, ,
The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, is planned to be released in 2021. To this end, we have performed integral tests of preliminary versions of JENDL-5 since 2018. In this presentation, we show the integral test results of JENDL-5 beta 3 update 1 for critical and shielding experiments. The critical test calculations have been done for experiments mainly in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook and conducted at JAEA. The shielding benchmark tests have been done mainly for FNS experiments at JAEA and OKTAVIAN experiments. We have confirmed that JENDL-5 beta 3 update 1 gives better than or the same prediction accuracy as the previous version of JENDL-4.0 in many test cases for the critical and shielding experiments.
Nakayama, Shinsuke
no journal, ,
JENDL-5 includes several sublibraries to contribute to various applications. The deuteron reaction sublibrary developed mainly for the design of accelerator neutron sources and the alpha-particle reaction one developed mainly for use in the nuclear backend field will be outlined. As for the deuteron reaction sublibrary, the data for Li-6,7, Be-9, and C-12,13 of JENDL/DEU-2020 were partially modified and adopted. The data for Al-27, Cu-63,65, and Nb-93 important as accelerator structural materials were newly evaluated based on the calculated values with the DEURACS code. As for the alpha-particle reaction sublibrary, the evaluated values based on the CCONE calculations were replaced only with respect to the neutron production cross-sections by the data of JENDL/AN-2005 and were adopted. As a result, the accuracy of the energy and angular distribution of the outgoing neutrons was improved while maintaining the accuracy of the neutron production cross-sections. In addition, the completeness of data other than neutron production such as gamma-ray production was improved.
Tada, Kenichi
no journal, ,
The burn-up calculations using JENDL-5 for LWR are carried out and the calculation results are compared to the other nuclear data libraries. The calculation results indicate that the differences of Pu-239, Gd-155, and Gd-157 affect the burn-up calculations. This presentation explains the differences in the burn-up calculations and the cause of the differences.
Yamaguchi, Hibiki*; Endo, Tomohiro*; Yamamoto, Akio*; Tada, Kenichi
no journal, ,
The numerical solution of the alpha eigenvalue is obtained by the inverse power iteration method. This method requires a large number of iterations to calculate the alpha eigenvalue. This study developed the acceleration method using the DMD method to reduce the calculation time of the alpha eigenvalue calculation and validated the developed method.
Nagaya, Yasunobu; Tada, Kenichi
no journal, ,
The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, was released in December of 2021. To investigate the prediction accuracy of JENDL-5 for criticality of reactor cores, we performed benchmark tests by using the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook. Judging from the overall results, we confirmed that JENDL-5 gives the better results than JENDL-4.0.
Taninaka, Hiroshi; Yokoyama, Kenji; Oki, Shigeo
no journal, ,
no abstracts in English
Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi; Iwamoto, Osamu
no journal, ,
The EOLE criticality experiment is analyzed by using the newly released evaluated nuclear data library JENDL-5 for the validation. This presentation reports the impact of the Am-241 modification on the neutronics calculation.
Tojo, Masayuki*; Ono, Michitaka*; Tada, Kenichi; Iwamoto, Osamu
no journal, ,
Analysis of the KRITZ-2 criticality experiment and calculation of the effective resonance integral measured by Hellstrand are performed by using the newly released evaluated nuclear data library JENDL-5 for the validation under hot conditions.
Yokoyama, Kenji; Taninaka, Hiroshi
no journal, ,
The latest version of Japanese evaluated nuclear data library, JENDL-5, was released in December 2021. In order to confirm the applicability of JENDL-5 to the fast reactor system, we conducted a set of benchmark analysis using the integral experiment data included in the fast reactor nuclear design database which is being developed by JAEA. With respect to major nuclear characteristics in the standard fast reactor system, it was confirmed that the ratios of analysis result and experimental result (C/E values) based on JENDL-5 were almost the same as those of JENDL-4.0. However, sensitivity analysis revealed that nuclide-and-reaction-wise contributions were canceled out. On the other hand, it was confirmed that C/E values in some of nuclear characteristics related to minor actinides were significantly improved compared to JENDL-4.0. Sensitivity analysis revealed that revisions to the fission cross sections of Pu-242 and Cm-244 and revisions to the capture cross sections of Cm-245 and Cm-246 improved the results.
Tada, Kenichi
no journal, ,
The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, was released in December of 2021. To investigate the prediction accuracy of JENDL-5 for criticality of reactor cores, we performed benchmark tests by using the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook. Judging from the overall results, we confirmed that JENDL-5 gave the better results than JENDL-4.0. The burn-up calculations using JENDL-5 for LWR pin cell and assembly geometries were also carried out and the calculation results were compared to the other nuclear data libraries. The calculation results indicate that the differences of Pu-239, Gd-155, and Gd-157 affect the burn-up calculations.
Konno, Chikara
no journal, ,
The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, was released at the end of 2021. The Monte Carlo transport codes PHITS and MCNP require ACE files of JENDL-5. The FRENDY code can produce ACE files without heating numbers and damage cross sections of the JENDL-5 neutron sub-library, but it cannot treat the JENDL-5 charged particle and photo-atomic sub-libraries. Thus I modified NJOY2016.65 in order to generate ACE files with heating numbers and damage cross sections of the JENDL-5 neutron, charged particle and photo-atomic sub-libraries.
Konno, Chikara
no journal, ,
The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, was released at the end of 2021. It is essential to validate JENDL-5 with benchmark experiments for JENDL-5 popularization. I introduce the overview of JENDL-5 and present analysis results of benchmark experiments at QST/TIARA, JAEA/FNS, Osaka Univ./OKTAVIAN, etc. as shielding benchmark tests of JENDL-5.
Watanabe, Tomoaki; Suyama, Kenya; Tada, Kenichi; Ferrer, R.*; Hykes, J.*
no journal, ,
The CASMO5 neutron data library based on JENDL-5 is generated and validated by comparison with the conventional ENDF/B-VII.1 library analyzing TCA criticality experiments and Takahama-3 PIE data. In the present library, such data as cross section, decay data, fission yield, etc based on ENDF/B-VII.1 are replaced by those of JENDL-5 as much as possible. As a result of the TCA experiment analysis, k
with the JENDL-5 library is slightly greater than those with the ENDF/B-VII.1 library for all cases analyzed. This tendency is also observed by same analysis using MVP3.0. For the PIE analysis, C/E values of nuclide inventory are almost comparable to those with the ENDF/B-VII.1 library and improved for a few nuclides such as Cs.
Sugawara, Takanori; Kunieda, Satoshi
no journal, ,
no abstracts in English
