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Journal Articles

FENDL: A Library for fusion research and applications

Schnabel, G.*; Kunieda, Satoshi; Konno, Chikara; Nakayama, Shinsuke; 27 of others*

Nuclear Data Sheets, 193, p.1 - 78, 2024/02

Fusion Evaluated Nuclear Data Library (FENDL), which has been coordinated by International Atomic Energy Agency (IAEA), was updated for the neutronics analysis on the fusion reactors and related applications. The main sources of data files are the national nuclear data libraries such as ENDF, JEFF and JENDL, where the best data was selected for each isotope through comparisons of the evaluated cross-sections and a number of benchmark analyses. Large differences from the previous library (FENDL-2.1) are extension of the upper energy limit from 20 MeV to 200 MeV and inclusion of the charged-particle reaction data, which had been requested by accelerator-based studies on structural materials for the fusion reactors. This paper gives a comprehensive description on the latest version FENDL-3.2b. A number of validations on the neutronics analysis show that the performance of FENDL-3.2b is better than FENDL-2.1.

Journal Articles

JENDL-5 benchmark test for shielding applications

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:98.49(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.

Journal Articles

General-purpose nuclear data library JENDL-5 and to the next

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Nagaya, Yasunobu; Tada, Kenichi; et al.

EPJ Web of Conferences, 284, p.14001_1 - 14001_7, 2023/05

Journal Articles

Estimation of double-differential cross-sections of $$^9$$Be(p,xn) reaction for new nuclear data library JENDL-5

Kunieda, Satoshi; Yamamoto, Kazuyoshi; Konno, Chikara; Iwamoto, Yosuke; Iwamoto, Osamu; Wakabayashi, Yasuo*; Ikeda, Yujiro*

Journal of Neutron Research, 24(3-4), p.329 - 335, 2023/01

We have evaluated double-differential cross-sections (DDX) of the $$^9$$Be(p,xn) reaction based on the function proposed by Wakabayashi et al. up to 12 MeV. Through compilation in the ENDF-6 format file, data processing, and neutronics analysis with MC simulation codes MCNP and PHITS to thick target yield (TTY) measurements, the function was re-confirmed to give more reasonable DDX data than those in our previous library JENDL-4.0/HE and ENDF/B-VIII.0. We finally decided to reduce the absolute cross-sections by 15% for our new nuclear data library JENDL-5 since the prediction ability of neutronics simulation was much better than that based on the original function. Through comprehensive comparisons of the simulation results on TTY at different proton energies and neutron emission angles, we conclude that JENDL-5 gives the best estimation in the world.

Journal Articles

Japanese Evaluated Nuclear Data Library version 5; JENDL-5

Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Abe, Yutaka*; Tsubakihara, Kosuke*; Okumura, Shin*; Ishizuka, Chikako*; Yoshida, Tadashi*; et al.

Journal of Nuclear Science and Technology, 60(1), p.1 - 60, 2023/01

 Times Cited Count:17 Percentile:99.99(Nuclear Science & Technology)

Journal Articles

Development of nuclear data processing code FRENDY version 2

Tada, Kenichi; Yamamoto, Akio*; Kunieda, Satoshi; Konno, Chikara; Kondo, Ryoichi; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*

Journal of Nuclear Science and Technology, 10 Pages, 2023/00

Nuclear data processing code is important to connect evaluated nuclear data libraries and radiation transport codes. The nuclear data processing code FRENDY version 1 was released in 2019 to generate ACE formatted cross section files with simple input data. After we released FRENDY version 1, many functions were developed, e.g., neutron multi-group cross section generation, explicit consideration of the resonance interference effect among different nuclides in a material, consideration of the resonance upscattering, ACE file perturbation, and modification of ENDF-6 formatted file. FRENDY version 2 was released including these new functions. It generates GENDF and MATXS formatted neutron multi-group cross section files from an ACE formatted cross section file or an evaluated nuclear data file. This paper explains the features of the new functions implemented in FRENDY version 2 and the verification of the neutron multigroup cross section generation function of this code.

Journal Articles

Problems on neutron production data of Be-9 in TENDL-2017 and -2019 deuteron sub-libraries

Kwon, Saerom*; Konno, Chikara; Ota, Masayuki*; Sato, Satoshi*

Annals of Nuclear Energy, 169, p.108932_1 - 108932_7, 2022/05

 Times Cited Count:2 Percentile:56.43(Nuclear Science & Technology)

Recently, it was reported that one of three ENDF files of Be-9 in the TENDL-2017 alpha sub-library included strange neutron production data. Thus we have tested three ENDF files of Be-9 in the TENDL-2017 deuterium sub-library for nuclear designs of a new fusion neutron source A-FNS. As a result, we found out that neutron production cross sections and secondary neutron spectra were different among three ENDF files and specified reasons. We confirmed that the latest TENDL, TENDL-2019, still had some of the issues.

Journal Articles

Anomalous small-angle X-ray scattering (ASAXS) study of irradiation-induced nanostructure change in Fe-ion beam irradiated oxide dispersion-strengthened (ODS) steel

Kumada, Takayuki; Oba, Yojiro; Motokawa, Ryuhei; Morooka, Satoshi; Tominaga, Aki; Tanida, Hajime; Shobu, Takahisa; Konno, Azusa; Owada, Kenji*; Ono, Naoko*; et al.

Journal of Nuclear Materials, 528, p.151890_1 - 151890_7, 2020/01

 Times Cited Count:1 Percentile:12.47(Materials Science, Multidisciplinary)

We have developed an anomalous small-angle X-ray scattering (ASAXS) diffractometer in SPring-8 to investigate irradiation-induced nanostructural change in ion-beam irradiated stainless steel. A thermally-aged MA956 stainless steel sample displays power-law scattering that follows the Porod law at the magnitude of scattering vector, Q, below 0.5 nm$$^-1$$ and an overlapped shoulder around 0.7 nm$$^-1$$. After the ion-beam irradiation, the intensity of the shoulder remained unchanged, whereas that of the power-law scattering nearly doubled. This result indicates that none of the structural parameters of the Cr-rich nanoprecipitates, such as the number density, size, and interface roughness, were changed by the irradiation.

Journal Articles

IRDFF-II; A New neutron metrology library

Trkov, A.*; Griffin, P. J.*; Simakov, S. P.*; Greenwood, L. R.*; Zolotarev, K. I.*; Capote, R.*; Aldama, D. L.*; Chechev, V.*; Destouches, C.*; Kahler, A. C.*; et al.

Nuclear Data Sheets, 163, p.1 - 108, 2020/01

 Times Cited Count:71 Percentile:99.77(Physics, Nuclear)

The version II of the International Reactor Dosimetry and Fusion File (IRDFF-II) has been released as a consistent set of nuclear data for fission and fusion neutron metrology applications up to 60 MeV neutron energy. The library is intended to support: (a) applications in research reactors; (b) safety and regulatory applications in the nuclear power generation in commercial fission reactors; and c) material damage studies in support of the research and development of advanced fusion concepts. The paper describes the contents of the library, documents the thorough verification process used in its preparation, and provides an extensive set of validation data gathered from a wide range of neutron benchmark fields. The new library is expected to become the international reference in neutron metrology for multiple applications.

Journal Articles

TENDL-2017 benchmark test with iron shielding experiment at QST/TIARA

Kwon, Saerom*; Konno, Chikara; Ota, Masayuki*; Ochiai, Kentaro*; Sato, Satoshi*; Kasugai, Atsushi*

Fusion Engineering and Design, 144, p.209 - 214, 2019/07

 Times Cited Count:3 Percentile:32.21(Nuclear Science & Technology)

We performed a TENDL-2017 benchmark test with iron shielding experiments by using 40 and 65 MeV neutrons, in order to verify a nuclear data library above 20 MeV for neutronics analyses of A-FNS. We found out that the calculated neutron spectra with TENDL-2017 unnaturally increased near 30 MeV. We figured out that incorrect secondary neutron spectrum data in $$^{54}$$Fe, $$^{56}$$Fe and $$^{58}$$Fe at 30 MeV caused the increase of the neutron flux. Similar problems occurred in a lot of nuclei of TENDL-2017, TENDL-2015 and FENDL-3.1d from TENDL-2010 and TENDL-2011.

Journal Articles

ACE library of JENDL-4.0/HE

Matsuda, Norihiro; Kunieda, Satoshi; Okamoto, Tsutomu*; Tada, Kenichi; Konno, Chikara

Progress in Nuclear Science and Technology (Internet), 6, p.225 - 229, 2019/01

Journal Articles

Shielding performance of newly developed boron-loaded concrete for DT neutrons

Sato, Satoshi*; Konno, Chikara; Nakashima, Hiroshi; Shionaga, Ryosuke*; Nose, Hiroyuki*; Ito, Yuji*; Hashimoto, Hirohide*

Journal of Nuclear Science and Technology, 55(4), p.410 - 417, 2018/04

 Times Cited Count:1 Percentile:11.6(Nuclear Science & Technology)

In order to enhance the neutron shielding performance, we developed concrete with boron of more than 10 wt%. We performed a neutron shielding experiment using the mockup of the newly developed boron-loaded concrete and DT neutrons at FNS in JAEA, and measured the reaction rates of the $$^{93}$$Nb(n,2n)$$^{92m}$$Nb and $$^{197}$$Au(n,$$gamma$$)$$^{198}$$Au reactions in the mockup. The calculations were conducted by using MCNP-5.14 and FENDL-2.1. The calculation results agreed well with the measured ones, and we confirmed that the accuracy was very good on the atomic composition data of the boron-loaded concrete and their nuclear data. In addition, we calculated effective dose rates and reaction rates of the $$^{59}$$Co(n,$$gamma$$)$$^{60}$$Co and $$^{151}$$Eu(n,$$gamma$$)$$^{152}$$Eu reactions in the boron-loaded concrete and other concretes. It is concluded that the boron-loaded concrete has much better shielding performance for DT neutrons than other concretes.

Journal Articles

FENDL-3.1b test

Konno, Chikara; Kwon, Saerom*; Ota, Masayuki*; Sato, Satoshi*

JAEA-Conf 2017-001, p.117 - 122, 2018/01

The revised version of FENDL-3, FENDL-3.1b was released in October, 2015. Thus we have tested FENDL-3.1b neutron sub-library for the problems we reported to IAEA before. Most of the MATXS files above 20 MeV had no scattering matrix data of non-elastic scattering, but this problem was fixed by re-processing FENDL-3 with NJOY2012.50. As for the problem on KERMA factors and DPA data, IAEA revised the wrong Q value of the capture reaction in $$^{15}$$N and re-calculated KERMA factors and DPA data with NJOY2012.50. It was confirmed that most of the KERMA factors and DPA data were revised correctly except for huge gas production cross-section data. However a new problem on NJOY processing of gas production data was found out. It was pointed out that this problem was due to a bug of NJOY. Additionally we investigated a trouble on $$^{116}$$Sn and $$^{117}$$Sn NJOY processing at IAEA and specified that one of NJOY patches caused this trouble.

Journal Articles

ENDF/B-VIII$$beta$$2 benchmark test with shielding experiments at QST/TIARA

Kwon, Saerom*; Konno, Chikara; Ota, Masayuki*; Sato, Satoshi*; Ochiai, Kentaro*

JAEA-Conf 2017-001, p.123 - 128, 2018/01

The $$beta$$-version of ENDF/B-VIII, ENDF/B-VIII$$beta$$2, was released in August, 2016. Thus we studied whether the overestimation problems due to the $$^{16}$$O and $$^{56}$$Fe data of ENDF/B-VII.1 were corrected in the iron and concrete shielding experiments with 40 and 65 MeV neutrons at TIARA. We produced the ACE files of ENDF/B-VIII$$beta$$2 with the NJOY2012.50 code and used the MCNP-5 code for this analysis. The nuclear data libraries, ENDF/B-VII.1, FENDL-3.1b and JENDL-4.0/HE, were also used for comparison. The following results were obtained; (1) the drastic overestimation of around 40 MeV due to the 5$$^{56}$$Fe data was improved, (2) the overestimation for around 65 MeV due to the $$^{56}$$Fe data was also slightly improved, though it was worse than that with FENDL-3.1b, (3) the drastic overestimation due to the $$^{16}$$O data was not improved. The final version of ENDF/B-VIII should also be modified based on these results.

Journal Articles

Benchmark experiment on copper with graphite by using DT neutrons at JAEA/FNS

Kwon, Saerom*; Ota, Masayuki*; Sato, Satoshi*; Konno, Chikara; Ochiai, Kentaro*

Fusion Engineering and Design, 124, p.1161 - 1164, 2017/11

 Times Cited Count:2 Percentile:19.91(Nuclear Science & Technology)

Copper is used as a material for superconducting coil in magnetic confinement fusion reactor and for accelerator-driven neutron source such as IFMIF. In our previous copper benchmark experiment, we had pointed out that the elastic scattering and capture reaction data of the copper had included some problems in the resonance region, which had caused a large underestimation of reaction rates of non-threshold reactions. In order to corroborate this issue, we carried out a new benchmark experiment on copper with graphite in the neutron field with more low energy neutrons. We measured reaction rates using the activation foils. We analyzed the experiment with MCNP code and the latest nuclear data libraries. As a result, the calculated reaction rates related to low energy neutrons, still excessively underestimated the measured ones as in the previous benchmark experiment. We also tested the nuclear data of copper modified in the previous study, where the elastic scattering and capture reaction cross section of copper. Then the calculated reaction rates with the modified copper nuclear data reproduced the measured ones well. It was revealed that the modification of the specific cross sections had been sufficient in the neutron field with more low energy neutrons.

Journal Articles

Lead benchmark experiment with DT neutrons at JAEA/FNS

Kwon, Saerom*; Ota, Masayuki*; Sato, Satoshi*; Konno, Chikara; Ochiai, Kentaro*

Fusion Science and Technology, 72(3), p.362 - 367, 2017/10

 Times Cited Count:4 Percentile:44.94(Nuclear Science & Technology)

Lead is a candidate material as a neutron multiplier, a tritium breeder and a coolant in nuclear fusion reactor system, and a $$gamma$$ ray shielding for beam dump or shielding of components in accelerator-driven neutron source such as IFMIF. A benchmark experiment on lead with DT neutrons had been performed at JAEA/FNS seven, where the reaction rates related to neutrons below a few keV had included background neutrons scattered in concrete walls of the experiment room. Thus, we designed and carried out a new benchmark experiment with a lead assembly covered with Li$$_{2}$$O blocks absorbing background neutrons. We successfully measured reaction rates of the non-threshold reactions with the activation foil method. The experiment was analyzed with MCNP code and the latest nuclear data libraries. All the calculated reaction rates (C) tended to underestimate the experimental ones (E) with the depth of the lead assembly. Although reasons of the underestimation have not been specified yet, we discovered that there are remarkable different tendencies of C/Es each reaction rate among the nuclear data libraries.

Journal Articles

Important comments on KERMA factors and DPA cross-section data in ACE files of JENDL-4.0, JEFF-3.2 and ENDF/B-VII.1

Konno, Chikara; Tada, Kenichi; Kwon, Saerom*; Ota, Masayuki*; Sato, Satoshi*

EPJ Web of Conferences, 146, p.02040_1 - 02040_4, 2017/09

 Times Cited Count:4 Percentile:90.94

So far we pointed out that KERMA factors and DPA cross-section data of a lot of nuclei in the official ACE file were different among nuclear data libraries for the following reasons; (1) incorrect nuclear data, (2) NJOY bugs, (3) huge helium production cross section data, (4) mf6 mt102 data, (5) no secondary particle data (energy-angular distribution data). Now we compare the KERMA factors and DPA cross section data included in the official ACE files of JENDL-4.0, ENDF/B-VII.1 and JEFF-3.2 in more detail. As a result, we find out new reasons of differences among the KERMA factors and DPA cross section data in the three nuclear data libraries. The reasons are categorized to no secondary charged particle data, no secondary $$gamma$$ data, wrong secondary $$gamma$$ spectra, wrong production yields and mf12-15 mt3 data for the capture reaction, some of which seem to be unsupported with NJOY. The ACE files of JENDL-4.0, ENDF/B-VII.1 and JEFF-3.2 with these problems should be revised based on this study.

Journal Articles

JENDL-4.0/HE benchmark test with concrete and iron shielding experiments at JAEA/TIARA

Konno, Chikara; Matsuda, Norihiro; Kwon, Saerom*; Ota, Masayuki*; Sato, Satoshi*

EPJ Web of Conferences, 153, p.01024_1 - 01024_6, 2017/09

 Times Cited Count:3 Percentile:86.61

As a benchmark test of JENDL-4.0/HE released in 2015, we have analyzed concrete and iron shielding experiments with the 40 and 65 MeV neutron sources at TIARA in JAEA by using MCNP5 and ACE files processed from JENDL-4.0/HE with NJOY2012. As a result, it was found out that the calculation results with JENDL-4.0/HE agreed with the measured ones in the concrete experiment well, while they underestimated the measured ones in the iron experiment more for the thicker assemblies. We examined JENDL-4.0/HE in detail and it was considered that the larger non-elastic scattering cross sections of $$^{56}$$Fe caused the underestimation in the calculation with JENDL-4.0/HE for the iron experiment.

Journal Articles

Benchmark experiment on molybdenum with graphite by using DT neutrons at JAEA/FNS

Ota, Masayuki*; Kwon, Saerom*; Sato, Satoshi*; Konno, Chikara; Ochiai, Kentaro*

Fusion Engineering and Design, 114, p.127 - 130, 2017/01

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

A new fusion neutron source is now under consideration in Japan. Type 316L stainless steel (SUS316L) which is a structural material of the target-system contains a few percent of molybdenum. In our previous benchmark experiment on molybdenum at JAEA/FNS, we found problems of the cross section data above a few hundred eV in Mo. We perform a new benchmark experiment on Mo with graphite in order to validate the Mo data in the lower energy region. Several dosimetry reaction rates and fission rates are measured in the assembly and compared with the calculated values with the Monte-Carlo transport code MCNP5-1.40 and the recent nuclear data libraries. It is suggested that the (n,$$gamma$$) cross section of $$^{95}$$Mo is underestimated in the tail region below the large resonance at 45 eV in the recent nuclear data libraries.

Journal Articles

New remarks on KERMA factors and DPA cross section data in ACE files

Konno, Chikara; Sato, Satoshi; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro

Fusion Engineering and Design, 109-111(Part B), p.1649 - 1652, 2016/11

 Times Cited Count:7 Percentile:55.37(Nuclear Science & Technology)

Recently we have examined KERMA factors and DPA cross section data in the latest official ACE files of JENDL-4.0, ENDF/B-VII.1, JEFF-3.2 and FENDL-3.0 in more detail and we found out the following new problems on the KERMA factors and DPA cross section data. (1) NJOY bugs and incorrect nuclear data generated KERMA factors and DPA cross section data of no increase with decreasing neutron energy in low neutron energy. (2) Huge helium production data caused drastically large KERMA factors and DPA cross section data in low neutron energy. (3) It seemed that NJOY could not adequately process capture cross section data in File 6, not File 12-15. (4) KERMA factors with the kinematics method are not correct for nuclear data libraries without detailed secondary particle data (energy-angular distribution data). These problems should be resolved based on our study.

164 (Records 1-20 displayed on this page)