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Journal Articles

Validation of ATDMs at early after the lF accident using air dose rate estimated by airborne concentration and surface deposition density

Moriguchi, Yuichi*; Sato, Yosuke*; Morino, Yu*; Goto, Daisuke*; Sekiyama, Tsuyoshi*; Terada, Hiroaki; Takigawa, Masayuki*; Tsuruta, Haruo*; Yamazawa, Hiromi*

KEK Proceedings 2021-2, p.21 - 27, 2021/12

no abstracts in English

JAEA Reports

Re-examinations of MA fuel composition for accelerator-driven system and its heat removal

Sugawara, Takanori; Moriguchi, Daisuke*; Ban, Yasutoshi; Tsubata, Yasuhiro; Takano, Masahide; Nishihara, Kenji

JAEA-Research 2021-008, 63 Pages, 2021/10

JAEA-Research-2021-008.pdf:4.43MB

This study aims to perform the neutronics calculations for accelerator-driven system (ADS) with a new fuel composition based on the SELECT process developed by Japan Atomic Energy Agency because the previous studies had used the ideal MA (minor actinide) fuel composition without uranium and rare earth elements. Through the neutronics calculations, it is shown that two calculation cases, with/without neptunium, satisfy the design criteria. Although the new fuel composition includes uranium and rare earth elements, the ADS core with the new fuel composition is feasible and consistent with the partitioning and transmutation (P&T) cycle. Based on the new fuel composition, the heat removal during fuel powder storage and fuel assembly assembling is evaluated. For the fuel powder storage, it is found that a cylindrical tube container with a length of 500 [mm] and a diameter of 11 - 21 [mm] should be stored under water. For the fuel assembly assembling, CFD analysis indicates that the cladding tube temperature would satisfy the criterion if the inlet velocity of air is larger than 0.5 [m/s]. Through these studies, the new fuel composition which is consistent with the P&T cycle is obtained and the heat removal with the latest conditions is investigated. It is also shown that the new fuel composition can be practically handled with respect to heat generation, which is one of the most difficult points in handling MA fuel.

Journal Articles

Development and operation of an electrostatic time-of-flight detector for the Rare RI storage Ring

Nagae, Daisuke*; Abe, Yasushi*; Okada, Shunsuke*; Omika, Shuichiro*; Wakayama, Kiyoshi*; Hosoi, Shun*; Suzuki, Shinji*; Moriguchi, Tetsuro*; Amano, Masamichi*; Kamioka, Daiki*; et al.

Nuclear Instruments and Methods in Physics Research A, 986, p.164713_1 - 164713_7, 2021/01

 Times Cited Count:5 Percentile:65.59(Instruments & Instrumentation)

Journal Articles

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

Uozumi, Yusuke*; Shigyo, Nobuhiro*; Kajimoto, Tsuyoshi*; Moriguchi, Daisuke*; Ueyama, Masahiko*; Yoshioka, Masakatsu*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; et al.

HIMAC-136, p.248 - 249, 2011/11

no abstracts in English

Journal Articles

Neutron-production double-differential cross sections from heavy-ion interactions

Satoh, Daiki; Moriguchi, Daisuke*; Kajimoto, Tsuyoshi*; Koba, Yusuke*; Nakamura, Yasuhiro*; Shigyo, Nobuhiro*; Ueyama, Masahiko*; Uozumi, Yusuke*; Yoshioka, Masakatsu*; Matsufuji, Naruhiro*; et al.

Journal of the Korean Physical Society, 59(2), p.1741 - 1744, 2011/08

 Times Cited Count:3 Percentile:27.54(Physics, Multidisciplinary)

The data of neutron production from heavy-ion interactions are of great importance for the dose assessment in heavy-ion therapy. We have already evaluated the data of neutron production for thick targets, in which the incident heavy ions completely stop, by the measurements and the reevaluation of the existing data reported by Kurosawa et al. As a next step of the research, we plan to evaluate the neutron-production cross-section data for thin targets. These data are useful to understand the mechanism of heavy-ion interaction, and improve the reaction model in particle transport codes. The previously reported cross-section data by Iwata et al. were revised by using a new set of neutron-detection efficiency values calculated with SCINFUL-QMD code. While the original data gave the larger values than the predictions of particle transport codes above 200 MeV due to the underestimation of the efficiencies, it was improved by this revision. In addition, we have started the new cross-section measurements at HIMAC. All the data of neutron-production cross sections were compared with the predictions of particle transport codes.

Journal Articles

Measurement of deuteron induced thick target neutron yields at 9 MeV

Shigyo, Nobuhiro*; Hidaka, Kosuke*; Hirabayashi, Keiichi*; Nakamura, Yasuhiro*; Moriguchi, Daisuke*; Kumabe, Masahiro*; Hirano, Hidetaka*; Hirayama, Shusuke*; Naito, Yuki*; Motooka, Chikahide*; et al.

Journal of the Korean Physical Society, 59(2), p.1725 - 1728, 2011/08

Journal Articles

Measurement of neutron-production double-differential cross-sections on carbon bombarded with 290-MeV/nucleon carbon and oxygen ions

Satoh, Daiki; Moriguchi, Daisuke*; Kajimoto, Tsuyoshi*; Uehara, Haruhiko*; Shigyo, Nobuhiro*; Ueyama, Masahiko*; Yoshioka, Masakatsu*; Uozumi, Yusuke*; Sanami, Toshiya*; Koba, Yusuke*; et al.

Nuclear Instruments and Methods in Physics Research A, 644(1), p.59 - 67, 2011/07

 Times Cited Count:18 Percentile:77.43(Instruments & Instrumentation)

Neutron-production double-differential cross sections on carbon-carbon and oxygen-carbon reactions with incident heavy-ion energy of 290 MeV/nucleon were measured by time-of-flight method using liquid organic scintillators. By use of a detection system specialized for low-energy neutrons, the cross sections were obtained in a wide energy region from several hundred MeV down to 0.6 MeV for the oxygen-ion incidences. The experimental data were compared with the calculation results using the Monte-Carlo simulation code, PHITS. The PHITS results gave an overall agreement with the measured data within a factor of two.

Oral presentation

Study for neutron production cross sections by heavy ion interactions, 2; Evaluation of cross sections, and comparison with predictions of Monte Carlo codes

Satoh, Daiki; Moriguchi, Daisuke*; Nakamura, Yasuhiro*; Kajimoto, Tsuyoshi*; Ueyama, Masahiko*; Yoshioka, Masakatsu*; Koba, Yusuke*; Shigyo, Nobuhiro*; Uozumi, Yusuke*; Matsufuji, Naruhiro*; et al.

no journal, , 

Neutron production double differential cross sections have been measured at HIMAC in National Institute of Radiological Sciences. The cross sections were obtained in the energy region from a few MeV to several hundred MeV. In addition, we got the systematic cross section data by revising the detection efficiencies in the existing data. All the data were compared with the predictions of Monte Carlo simulation codes. While the codes show a good agreement in the backward angular region, they can not reproduce the peak structure observed in the forward angular region. This indicates that the nucleus-nucleus reaction model in the simulation codes must be revised.

Oral presentation

Measurement of neutron thick target yields for 9 MeV deuteron incidence on Cu and Ti

Shigyo, Nobuhiro*; Hidaka, Kosuke*; Hirabayashi, Keiichi*; Nakamura, Yasuhiro*; Moriguchi, Daisuke*; Hirano, Hidetaka*; Hirayama, Shusuke*; Naito, Yuki*; Watanabe, Yukinobu*; Sagara, Kenshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Measurements of neutron yields for 9 MeV deuteron-incidence on Cu

Hirabayashi, Keiichi*; Hirano, Hidetaka*; Hidaka, Kosuke*; Moriguchi, Daisuke*; Nakamura, Yasuhiro*; Shigyo, Nobuhiro*; Hirayama, Shusuke*; Naito, Yuki*; Watanabe, Yukinobu*; Takahashi, Hiroki; et al.

no journal, , 

no abstracts in English

Oral presentation

Study for neutron production cross sections by heavy ion interactions, 3; Neutron production double differential cross sections of oxygen upon 290 MeV/u carbon ion incidences

Satoh, Daiki; Shigyo, Nobuhiro*; Uozumi, Yusuke*; Moriguchi, Daisuke*; Kajimoto, Tsuyoshi*; Yoshioka, Masakatsu*; Ueyama, Masahiko*; Sanami, Toshiya*; Koba, Yusuke*; Matsufuji, Naruhiro*; et al.

no journal, , 

Neutron-production double-differential cross sections from heavy-ion interactions have been measured at Heavy-Ion Medical Accelerator in Chiba (HIMAC) of National Institute of Radiological Sciences (NIRS), Japan. 290-MeV/u O ions were bombarded upon a carbon target. The outgoing neutrons from the target were measured by a detection system that consist of two sizes of liquid organic scintillators with Time-of-Flight (TOF) technique in order to obtain a wide range of neutron spectrum from sub MeV to several hundred MeV. We have successfully measured the cross sections with a good precision.

Oral presentation

Measurement of carbon ion incident neutron production double differential cross sections for carbon target

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Kajimoto, Tsuyoshi*; Moriguchi, Daisuke*; Ueyama, Masahiko*; Yoshioka, Masakatsu*; Koba, Yusuke*; Nakamura, Yasuhiro*; Satoh, Daiki; Sanami, Toshiya*; et al.

no journal, , 

Radiation dose by neutrons produced by proton and heavy ion induced nuclear reactions around tumor is essential for dose assessment in proton and heavy ion radiotherapies. Double differential cross section (DDX) of neutron production is one of important physical quantities for dose estimation by radiation transport codes. Some experimental data of neutron production DDXs have been reported above 5 MeV of neutron energy for heavy ion incident reactions. Neutron production DDX for carbon ion incidence on carbon target was measured at the Heavy Ion Medical Accelerator in Chiba (HIMAC) including low neutron energy region for validation of radiation transport codes. Incident carbon energy was 290 MeV/u. NE213 liquid organic scintillators were deployed as neutron detectors and placed at 15$$^{circ}$$, 30$$^{circ}$$ 45$$^{circ}$$, 60$$^{circ}$$, 75$$^{circ}$$ and 90$$^{circ}$$. Neutron energies were determined by the time-of-flight methods. Neutron detection efficiency was calculated by the SCINFUL-QMD code. The obtained minimum neutron energy was about 2.8 MeV. The experimental data of neutron production DDX was compared with that by one of radiation transport codes, PHITS.

Oral presentation

Improvement of assessment methods for atmospheric behavior of accidentally discharged hazardous materials by comprehensively analyzing nuclear accident data

Yamazawa, Hiromi*; Oura, Yasuji*; Moriguchi, Yuichi*; Terada, Hiroaki; Sekiyama, Tsuyoshi*; Goto, Daisuke*; Tsuruta, Haruo*

no journal, , 

no abstracts in English

Oral presentation

Sophistication of dynamics evaluation method for harmful substances in the atmosphere

Yamazawa, Hiromi*; Sato, Yosuke*; Oura, Yasuji*; Moriguchi, Yuichi*; Terada, Hiroaki; Furuno, Akiko; Tsuzuki, Katsunori; Kadowaki, Masanao; Sekiyama, Tsuyoshi*; Adachi, Koji*; et al.

no journal, , 

no abstracts in English

Oral presentation

Evaluation of atmospheric dispersion models using the environmental data on the nuclear accident and their application to nuclear emergency, 3; Usage of atmospheric dispersion models in the nuclear emergency scheme

Yamazawa, Hiromi*; Oura, Yasuji*; Moriguchi, Yuichi*; Terada, Hiroaki; Sekiyama, Tsuyoshi*; Goto, Daisuke*; Tsuruta, Haruo*; Sato, Yosuke*

no journal, , 

no abstracts in English

15 (Records 1-15 displayed on this page)
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