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JAEA Reports

Proceedings of the 2022 Symposium on Nuclear Data; November 17-18, 2022, BLOSSOM CAF$'E$, Main Campus, Kindai University, Higashiosaka City, Osaka, Japan

Shigyo, Nobuhiro*; Kimura, Atsushi; Sano, Tadafumi*

JAEA-Conf 2023-001, 146 Pages, 2024/02

JAEA-Conf-2023-001.pdf:11.2MB

The 2022 Symposium on Nuclear Data was held at BLOSSOM CAF$'E$ in Main Campus of Kindai University on November 17-18, 2022. The symposium was organized by the Nuclear Data Division of the Atomic Energy Society of Japan (AESJ) in cooperation with Investigation Committee on Nuclear Data in AESJ, Nuclear Science and Engineering Center of Japan Atomic Energy Agency, and High Energy Accelerator Research Organization. In the symposium, tutorials "The Future of Nuclear Reactor Physics Experimental Research in Japan" was proposed and held. Two sessions of lectures and discussions were held: "Recent Topics on Nuclear Data". In addition, recent research progress on experiments, nuclear theory, evaluation, benchmark, and applications were presented in the poster session. The total number of participants was 76 participants. Each oral and poster presentation was followed by an active question and answer session. This report consists of a total of 22 papers including 4 oral and 18 poster presentations.

Journal Articles

Nuclear data as foundation of nuclear research and development

Fukahori, Tokio; Nakayama, Shinsuke; Katabuchi, Tatsuya*; Shigyo, Nobuhiro*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 65(12), p.726 - 727, 2023/12

The Investigative Committee on Nuclear Data investigates and observes global trends in nuclear research and development and conducts comprehensive examinations of Japanese nuclear data activities from a broader perspective, as well as cooperation with domestic and foreign academic institutions in a wide range of fields other than the Atomic Energy Society. We aim to establish a system for communication, information exchange, and interdisciplinary cooperation. In this report, we will report on three of the main activities for the 2021-2022 term: a request list site for nuclear data, human resource development, and roadmap production.

Journal Articles

Recent improvements of the Particle and Heavy Ion Transport code System; PHITS version 3.33

Sato, Tatsuhiko; Iwamoto, Yosuke; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuya, Yusuke; Matsuda, Norihiro; Hirata, Yuho; et al.

Journal of Nuclear Science and Technology, 9 Pages, 2023/00

The Particle and Heavy Ion Transport code System (PHITS) is a general-purpose Monte Carlo radiation transport code that can simulate the behavior of most particle species with energies up to 1 TeV (per nucleon for ions). Its new version, PHITS3.31, was recently developed and released to the public. In the new version, the compatibility with high-energy nuclear data libraries and the algorithm of the track-structure modes have been improved. In this paper, we summarize the upgraded features of PHITS3.31 with respect to the physics models, utility functions, and application software introduced since the release of PHITS3.02 in 2017.

Journal Articles

Nuclear data as foundation of nuclear research and development

Fukahori, Tokio; Nakayama, Shinsuke; Katabuchi, Tatsuya*; Shigyo, Nobuhiro*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 64(7), p.413 - 414, 2022/07

The Investigation Advisory Committee on Nuclear Data monitors global nuclear research and development trends, and conducts collaborative nuclear data activities with domestic and foreign academic institutions in a wide range of fields. The aims are to contact, to exchange information, and to build an interdisciplinary cooperation system. Reported are the activities on the request list site, human resources development, and roadmap creation regarding nuclear data directly related to future nuclear data research activities, among the main activities in the 2019-2020 period.

JAEA Reports

Proceedings of the 2019 Symposium on Nuclear Data; November 28-30, 2019, Kyushu University, Chikushi Campus, Fukuoka, Japan

Watanabe, Yukinobu*; Shigyo, Nobuhiro*; Kin, Tadahiro*; Iwamoto, Osamu

JAEA-Conf 2020-001, 236 Pages, 2020/12

JAEA-Conf-2020-001.pdf:13.75MB

The 2019 Symposium on Nuclear Data was held at Chikushi Campus Cooperation Building (C-Cube), Kyushu University, on November 28 to 30, 2019. The symposium was organized by the Nuclear Data Division of the Atomic Energy Society of Japan (AESJ) in cooperation with Sigma Investigative Advisory Committee of AESJ, Nuclear Science and Engineering Center of Japan Atomic Energy Agency, Kyushu Branch of AESJ, and Center for Accelerator and Beam Applied Science of Kyushu University. In the symposium, there were one tutorial, "From the resonance theory to statistical model", and five sessions, "Study on Nuclear Data and related topics", "Reactor physics", "International Cooperation", "Nuclear Physics", and "High Energy Nuclear Data and their Application". In addition, recent research progress on experiments, nuclear theory, evaluation, benchmark and applications was presented in the poster session. Among 85 participants, all presentations and following discussions were very active and fruitful. This report consists of total 42 papers including 13 oral and 29 poster presentations.

Journal Articles

Features of particle and heavy ion transport code system (PHITS) version 3.02

Sato, Tatsuhiko; Iwamoto, Yosuke; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Tsai, P.-E.; Matsuda, Norihiro; Iwase, Hiroshi*; et al.

Journal of Nuclear Science and Technology, 55(6), p.684 - 690, 2018/06

 Times Cited Count:652 Percentile:100(Nuclear Science & Technology)

We have upgraded many features of the Particle and Heavy Ion Transport code System (PHITS) and released the new version as PHITS3.02. The accuracy and the applicable energy ranges of the code were greatly improved and extended, respectively, owing to the revisions to the nuclear reaction models and the incorporation of new atomic interaction models. In addition, several user-supportive functions were developed, such as new tallies to efficiently obtain statistically better results, radioisotope source-generation function, and software tools useful for applying PHITS to medical physics. In this paper, we summarize the basic features of PHITS3.02, especially those of the physics models and the functions implemented after the release of PHITS2.52 in 2013.

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 7; Challenge to high energy area

Shigyo, Nobuhiro*; Iwase, Hiroshi*; Iwamoto, Yosuke; Sato, Tatsuhiko

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 60(5), p.294 - 298, 2018/05

For calculations of neutron productions and radiation damages in nuclear design of Accelerator Driven System (ADS) and exposure doses in radiation cancer therapy, radiation transport simulations with the high-energy nuclear data library evaluated with experimental data play an important role. Experimental data are needed for validation of nuclear reaction models in calculation codes. In this paper, we explain examples of nuclear data measurements in high energy region and the progress of the Particle and Heavy-Ion Transport code System (PHITS) developed in Japan.

Journal Articles

Measurement of neutron production double-differential cross-sections on carbon bombarded with 430 MeV/nucleon carbon ions

Itashiki, Yutaro*; Imabayashi, Yoichi*; Shigyo, Nobuhiro*; Uozumi, Yusuke*; Satoh, Daiki; Kajimoto, Tsuyoshi*; Sanami, Toshiya*; Koba, Yusuke*; Matsufuji, Naruhiro*

Journal of Radiation Protection and Research, 41(4), p.344 - 349, 2016/12

Carbon ion therapy has achieved satisfactory results because of high curability and minimally invasiveness. However, patients have a risk to get a secondary cancer. In order to estimate the risk, it is essential to understand particle transportation and nuclear reactions in the patient's body. The particle transport Monte Carlo simulation code is a useful tool to understand them. Since the code validation for heavy ion incident reactions is not enough, the experimental data of the elementary reaction processes is needed. We measured neutron production double-differential cross-sections (DDXs) on a carbon bombarded with 430 MeV/nucleon carbon beam which is a possible candidate of future therapy beam. The experiment was performed at PH2 beam line of the HIMAC of National Institute of Radiological Sciences. The 430 MeV/nucleon carbon beam was irradiated on a 5 cm $${times}$$ 5 cm $${times}$$ 1 cm graphite target rotated 45$$^{circ}$$ to the beam axis. The beam intensity was set to 10$$^{5}$$ particles / spill. A 0.5 mm thick NE102A plastic scintillator was placed to monitor the beam intensity. Neutrons produced in the target were measured with two sizes of NE213 liquid organic scintillators located at six angles of 15, 30, 45, 60, 75, and 90$$^{circ}$$. The 5.08 cm long one was used to obtain the neutron spectra from 1 MeV to 10 MeV and the 12.7 cm long one was used above 5 MeV. The 2 mm thick NE102A plastic scintillators to discriminate charged particles were set in front of the neutron detectors. The kinetic energies of neutrons were determined by the time-of-flight (TOF) method. Background neutrons were estimated by a measurement with iron shadow bars between the target and each neutron detector. An electronic circuit for data acquisition consisted of NIM and CAMAC modules. The experimental data was compared with calculated results obtained by Monte Carlo simulation codes as PHITS. The PHITS code reproduced the experimental data well.

Journal Articles

Distributions of neutron yields and doses around a water phantom bombarded with 290-MeV/nucleon and 430-MeV/nucleon carbon ions

Satoh, Daiki; Kajimoto, Tsuyoshi*; Shigyo, Nobuhiro*; Itashiki, Yutaro*; Imabayashi, Yoichi*; Koba, Yusuke*; Matsufuji, Naruhiro*; Sanami, Toshiya*; Nakao, Noriaki*; Uozumi, Yusuke*

Nuclear Instruments and Methods in Physics Research B, 387, p.10 - 19, 2016/11

 Times Cited Count:3 Percentile:28.38(Instruments & Instrumentation)

Double-differential neutron yields from a water phantom bombarded with 290-MeV/nucleon and 430-MeV/nucleon carbon ions were measured at emission angles of 15$$^{circ}$$, 30$$^{circ}$$, 45$$^{circ}$$, 60$$^{circ}$$, 75$$^{circ}$$, and 90$$^{circ}$$ using the neutron-detection system constituting of liquid organic scintillators. The angular distributions of neutron yields and effective doses around the phantom were obtained by integrating the double-differential neutron yields and applying the fluence-to-effective dose conversion coefficients. The experimental data were compared with results of the Monte-Carlo simulation code PHITS. The PHITS results showed good agreement with the measured data. From the results, we concluded that the PHITS simulation is applicable to the dose estimation at carbon-therapy facilities.

Journal Articles

Overview of JENDL-4.0/HE and benchmark calculations

Kunieda, Satoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Minato, Futoshi; Okamoto, Tsutomu; Sato, Tatsuhiko; Nakashima, Hiroshi; Iwamoto, Yosuke; Iwamoto, Hiroki; Kitatani, Fumito; et al.

JAEA-Conf 2016-004, p.41 - 46, 2016/09

Neutron- and proton-induced cross-section data are required in a wide energy range beyond 20 MeV, for the design of accelerator applications. New evaluations are performed with recent knowledge in the optical and pre-equilibrium model calculations. We also evaluated cross-sections for p+$$^{6,7}$$Li and p+$$^{9}$$Be which have been highly requested from a medical field. The present high-energy nuclear data library, JENDL-4.0/HE, includes evaluated cross-sections for incident neutrons and protons up to 200 MeV (for about 130 nuclei). We overview substantial features of the library, i.e., (1) systematic evaluation with CCONE code, (2) challenges for evaluations of light nuclei and (3) inheritance of JENDL-4.0 and JENDL/HE-2007. In this talk, we also focus on the results of benchmark calculation for neutronics to show performance of the present library.

Journal Articles

Evaluation of neutron nuclear data on xenon isotopes

Rashid, M. M.*; Shigyo, Nobuhiro*; Ishibashi, Kenji*; Iwamoto, Nobuyuki; Iwamoto, Osamu

Journal of Nuclear Science and Technology, 53(9), p.1310 - 1320, 2016/09

 Times Cited Count:2 Percentile:28.38(Nuclear Science & Technology)

The neutron cross sections for stable Xe isotopes were calculated by nuclear reaction model code, CCONE and then compared with experimental information. The evaluation was made in the energy region from 1 keV to 20 MeV. The coupled-channels optical model was used to calculate the total cross section. The contributions of preequilibrium and direct processes in the statistical model calculations were considered to obtain reaction cross sections, $$gamma$$-ray and particle emission spectra. The present evaluation can reasonably explain the experimental data of total, capture, ($$n,2n$$), ($$n,p$$) and ($$n,alpha$$) reactions. The obtained capture cross sections for $$^{124,126}$$Xe are smaller than the data of JENDL-3.2 in the energy region where the neutron spectrum of YAYOI has a large contribution. Hence, these results could improve the overestimation of C/E values found by the YAYOI experiment. The evaluated total ($$n,2n$$) reaction cross section of $$^{136}$$Xe is in good agreement with experimental data. Therefore, the present data of $$^{136}$$Xe could provide relevant ones for KamLAND-Zen and EXO experiments.

Journal Articles

Evaluation of neutron nuclear data on krypton isotopes

Rashid, M. M.*; Shigyo, Nobuhiro*; Ishibashi, Kenji*; Iwamoto, Nobuyuki; Iwamoto, Osamu

JAEA-Conf 2015-003, p.319 - 324, 2016/03

Neutron nuclear data of krypton isotopes have been evaluated in the incident neutron energy range from 1 keV to 20 MeV by using theoretical nuclear reaction model code CCONE. The phenomenological optical model potential was employed to calculate total reaction cross section for natural krypton. This calculation is based on the coupled channel method. However, optical potential parameters were obtained by best fitting the calculation result with experimental total cross section of natural krypton. The transmission coefficients were calculated which was used for getting the cross sections in outgoing reaction channels. Compound, pre-equilibrium, and direct reaction processes were taken into consideration for cross section calculation. The present calculation results were compared with the experimental data and major evaluated nuclear data libraries. It is observed that the present evaluation can explain the experimental data reasonably well.

Journal Articles

Measurement of neutron production cross sections from heavy ion induced reaction

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Imabayashi, Yoichi*; Itashiki, Yutaro*; Satoh, Daiki; Kajimoto, Tsuyoshi*; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*; et al.

JAEA-Conf 2014-002, p.81 - 87, 2015/02

Cancer therapy using heavy ion beam has been adopted as highly advanced medical treatment by reason of its clinical advantages. It has become more important to estimate the risk of secondary cancer from recent survey. During treatment, secondary particles such as neutrons and -rays are producedby heavy ion induced nuclear reactions in a patient body as well as beam delivery apparatuses. For the risk assessment of secondary cancer, it is essential to know contribution of secondary neutrons by extra dose to organs in the vicinity of the irradiated tumor because the secondary neutron has a long flight path length and gives undesired dose to normal tissues in a wide volume. The experimental data of neutron energy spectra are required for dose estimations with high accuracy. Especially, precise data around neutron energy of 1 MeV is required because neutron of the energy region has a large relative biological eectiveness. Estimation of the secondary neutron yield data is important for estimation of radiation safety on both of workers and public in treatment facilities.

Journal Articles

Measurement of proton, deuteron, and triton production double differential cross sections on carbon by 290 MeV/nucleon Ar ions

Kajimoto, Tsuyoshi*; Hashiguchi, Taro*; Shigyo, Nobuhiro*; Satoh, Daiki; Uozumi, Yusuke*; Song, T. Y.*; Lee, C. W.*; Kim, J. W.*; Yang, S. C.*; Koba, Yusuke*; et al.

JAEA-Conf 2014-002, p.127 - 132, 2015/02

Particle transport Monte Carlo codes such as PHITS, FLUKA and so on are used for radiation safety design of high energy accelerators. The validity of code is confirmed by comparison with many experimental data. In this study, we report proton, deuteron, and triton production double differential cross sections (DDXs) from a graphite target by 290 MeV/nucleon Ar ions. The measured spectra are compared with those calculated by PHITS and FLUKA codes.

Journal Articles

Measurements and parameterization of neutron energy spectra from targets bombarded with 120 GeV protons

Kajimoto, Tsuyoshi*; Shigyo, Nobuhiro*; Sanami, Toshiya*; Iwamoto, Yosuke; Hagiwara, Masayuki*; Lee, H. S.*; Soha, A.*; Ramberg, E.*; Coleman, R.*; Jensen, D.*; et al.

Nuclear Instruments and Methods in Physics Research B, 337, p.68 - 77, 2014/10

 Times Cited Count:4 Percentile:38.2(Instruments & Instrumentation)

The energy spectra of neutrons were measured by a time-of-flight method for 120 GeV protons on thick graphite, aluminum, copper, and tungsten targets with an NE213 scintillator at the Fermilab Test Beam Facility. Neutron energy spectra were obtained between 25 and 3000 MeV at emission angles of 30, 45, 120, and 150$$^{circ}$$. The spectra were parameterized as neutron emissions from three moving sources and then compared with theoretical spectra calculated by PHITS and FLUKA codes. The yields of the theoretical spectra were substantially underestimated compared with the yields of measured spectra. The integrated neutron yields from 25 to 3000 MeV calculated with PHITS code were 16-36% of the experimental yields and those calculated with FLUKA code were 26-57% of the experimental yields for all targets and emission angles.

Journal Articles

Measurement of 100- and 290-MeV/A carbon incident neutron production cross sections for carbon, nitrogen and oxygen

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Takamiya, Masanori*; Hashiguchi, Taro*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; et al.

Nuclear Data Sheets, 119, p.303 - 306, 2014/05

 Times Cited Count:0 Percentile:0.02(Physics, Nuclear)

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and $$gamma$$-ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of the secondary neutrons yields data is essential for assessment of radiation safety on both of workers and public in treatment facilities. We have measured the neutron yields from carbon ion incidence on carbon, nitrogen and oxygen targets in wide angular range from 15$$^{circ}$$ to 90$$^{circ}$$ with 100- and 290-MeV/u.

Journal Articles

Measurement of neutron yields from a water phantom bombarded by 290 MeV/u carbon ions

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Hirabayashi, Keiichi*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*

Progress in Nuclear Science and Technology (Internet), 4, p.709 - 712, 2014/04

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and $$gamma$$-ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of the secondary neutrons yields data is essential for assessment of radiation safety on both of workers and public in treatment facilities. Neutron energy spectra from a water phantom simulating the patient body were obtained at GSI only for forward directions. We measured the neutron yields from carbon ion incident on a water phantom in wide angular range from 15$$^{circ}$$ to 90$$^{circ}$$ with the therapeutic ion energy.

Journal Articles

Measurement of 100 MeV/u carbon incident neutron production cross sections on a carbon target

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*

JAEA-Conf 2013-002, p.137 - 142, 2013/10

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and $$gamma$$-ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of double differential cross sections of secondary neutron is important to risk assessment of extra dose to organs in the vicinity of the irradiated tumor. Accurate data in neutron energy around 1 MeV is required because neutron in the energy region has large relative biological effectiveness. Neutron double differential cross sections by inducing 290 MeV/u carbon ion to bio-elements have been obtained experimentally. In order to have knowledge of neutron production by deceleration carbon in a human body, we measured the neutron yields from carbon ion incidence on a carbon target of neutron energy below 1 MeV in wide angular range from 15$$^{circ}$$ to 90$$^{circ}$$ with 100 MeV/u.

Journal Articles

Measurement of neutron- and photon-production cross sections from heavy-ion reactions on tissue equivalent elements

Uozumi, Yusuke*; Shigyo, Nobuhiro*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*; et al.

HIMAC-140, p.234 - 235, 2013/08

In the heavy-ion radiotherapy, considerable discussion has been attracted regarding the potential for second cancer induction by secondary neutrons produced from the primary heavy-ion fragmentation. We have started new measurements at 100 MeV/u to investigate the neutron production by heavy ions decelerating in a patient body.

Journal Articles

Measurement of thick target neutron energy spectra at 15$$^{circ}$$ and 90$$^{circ}$$ bombarded with 120-GeV protons

Iwamoto, Yosuke; Sanami, Toshiya*; Kajimoto, Tsuyoshi*; Shigyo, Nobuhiro*; Hagiwara, Masayuki*; Lee, H. S.*; Soha, A.*; Ramberg, E.*; Coleman, R.*; Jensen, D.*; et al.

Progress in Nuclear Science and Technology (Internet), 3, p.65 - 68, 2012/10

Neutron energy spectra at 15$$^{circ}$$ and 90$$^{circ}$$ produced from carbon, aluminum, copper and tungsten targets bombarded with 120-GeV protons were measured at Fermilab Test Beam Facility (FTBF) for the validation of simulation codes. The target thicknesses were 60 cm for graphite, 50 cm for aluminum, 20, 40, and 60 cm for copper and 10 cm for tungsten, respectively. The neutron time-of-flight measurements were performed using an NE213 organic liquid scintillator at 5.2 m for 90$$^{circ}$$ and 8.0 m for 15$$^{circ}$$ measuring from the center of the target to the surface of the detector. The raw signals (waveforms) obtained from photomultiplier tubes were recorded using the 10 bit digitizer (Agilent-acqiris DC282) with 0.5 ns sampling and 500 ns duration. To compare the experimental results, Monte Carlo calculations with the PHITS, MARS and FLUKA codes were performed. It was found that these calculated results underestimate the experimental results in the whole energy range.

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