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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 a compact vertical splitting system for the cold neutron beam at JRR-3

Tamura, Itaru; Maruyama, Ryuji; Yamazaki, Dai; Nakamura, Kiyoshi; Yamamoto, Kazuyoshi; Aizawa, Kazuya; Soyama, Kazuhiko

Journal of Physics; Conference Series, 528, p.012012_1 - 012012_7, 2014/07

 Times Cited Count:1 Percentile:52.39

To achieve efficient implementation of usage of neutron beam instruments, the instruments were rearranged at C2 cold neutron beam line at JRR-3 by using a newly developed compact vertical splitting system. The splitting system has two compact multi channel benders. The bender has been developed using Ni/Ti supermirrors coated on both sides of 0.2 mm thickness silicon substrates. The curvature radius of the bender is 938 mm and the length of the bender is 320 mm yielding deflection angles of 20$$^{circ}$$. Supermirrors with m=3 were deposited on both sides of silicon substrate by an ion beam sputtering apparatus in JAEA. Neutron flux at the end of the neutron guide that installed at the bender exit of which the deflection angle is 20$$^{circ}$$ was measured by the gold foil activation method. It was measured 1.58 $$times$$ 10$$^{7}$$ n/cm$$^{2}$$/s. The present study showed that the supermirrors coated on both sides with high reflectivity are suitable for the compact bender.

Journal Articles

Commentaries for third secondary national examination on fiscal 2010 for the professional engineer of nuclear and radiation; Commentaries (Part 1) including key point for elective examinations

Sasaki, Satoru; Suto, Toshiyuki; Harada, Akio; Kurihara, Ryoichi; Yamamoto, Kazuyoshi; Tsuchida, Noboru; Shimizu, Isamu; Nomura, Toshibumi

Genshiryoku eye, 57(1), p.66 - 75, 2011/01

no abstracts in English

JAEA Reports

Determination of boron concentration in whole blood by inductively coupled plasma atomic emission spectrometry for boron neutron capture therapy

Horiguchi, Hironori; Yamamoto, Kazuyoshi; Kishi, Toshiaki; Otake, Shinichi*; Kumada, Hiroaki*

JAEA-Research 2009-015, 38 Pages, 2009/07

JAEA-Research-2009-015.pdf:7.61MB

The boron neutron capture therapy (BNCT) has been conducted at JRR-4. There is an increased number of cases due to the expansion of application against head and neck cancer and skin cancer. Therefore, the BNCT requires the establishment of procedure to perform more cases in a day. The determination of boron concentration in blood is important to determine the prescribed dose given to a patient. Currently, prompt $$gamma$$ ray analysis (PGA) is applied to the determination of boron concentration. But the PGA is not applied to more than three times BNCT a day. Therefore, swiftness and precision method by inductively coupled plasma atomic emission spectrometry (ICP-AES) is studied. Using BSH for Boron standard of the ICP-AES, we enabled to analyze accurately without an intricate sample preparation. The measurement precision of the ICP-AES was within 5% by the correction factor based on the PGA. We established the method of swiftness determination of boron concentration in blood for BNCT.

Journal Articles

Conceptual design of experimental equipment for large-diameter NTD-Si

Yagi, Masahiro; Watanabe, Masanori; Oyama, Koji; Yamamoto, Kazuyoshi; Komeda, Masao; Kashima, Yoichi; Yamashita, Kiyonobu

Applied Radiation and Isotopes, 67(7-8), p.1225 - 1229, 2009/07

 Times Cited Count:11 Percentile:59.93(Chemistry, Inorganic & Nuclear)

Journal Articles

Performance measurement of the scintillator with optical fiber detector for boron neutron capture therapy

Komeda, Masao; Kumada, Hiroaki; Ishikawa, Masayori*; Nakamura, Takemi; Yamamoto, Kazuyoshi; Matsumura, Akira*

Applied Radiation and Isotopes, 67(7-8, Suppl.), p.S254 - S257, 2009/07

 Times Cited Count:5 Percentile:35.99(Chemistry, Inorganic & Nuclear)

Journal Articles

Performance measurement of the SOF detector for boron neutron capture therapy

Komeda, Masao; Kumada, Hiroaki; Ishikawa, Masayori*; Nakamura, Takemi; Yamamoto, Kazuyoshi; Matsumura, Akira*

Proceedings of 13th International Congress on Neutron Capture Therapy (ICNCT-13) (CD-ROM), 3 Pages, 2008/11

In this report, deterioration of a SOF detector that can measure thermal neutron in real time was investigated in irradiation experiments. Sensitivity of a SOF detector decreased by 2.0% after an irradiation of about 4 hours. Then thermal neutron fluence was approximately 2.0$$times$$10$$^{13}$$ (n/cm$$^{2}$$). And after the SOF detector was used for about 2 months, sensitivity decreased to 42%. Then thermal neutron fluence was approximately 6.4$$times$$10$$^{14}$$ (n/cm$$^{2}$$). Supposing that thermal neutron fluence is 2$$times$$10$$^{12}$$ (n/cm$$^{2}$$) on the surface of a patient at a BNCT, sensitivity of a SOF detector is considered to be decreased by approximately 0.3% at a BNCT. Therefore it is considered that countermeasure against deterioration is necessary for using a SOF detector at BNCT in the future.

JAEA Reports

Investigation of the irradiation method for 12 inch NTD silicon in JRR-3 (Contract research)

Komeda, Masao; Yamamoto, Kazuyoshi; Yagi, Masahiro; Sagawa, Hisashi

JAEA-Technology 2008-064, 77 Pages, 2008/10

JAEA-Technology-2008-064.pdf:6.7MB

We investigated the irradiation method to irradiate 12 inch NTD silicon uniformly in JRR-3, where 6 inch NTD silicon is being irradiated at present, by using MVP of the Monte Carlo calculation code. In the case of irradiating 12 inch NTD silicon, the deviation of the doping distribution in the radial direction becomes 1.17 by the same irradiation method of 6 inch NTD silicon. Therefore the thermal neutron filter was introduced for uniform doping (the deviation is less than 1.10) in the radial direction and the effect was analyzed. As the result, it was indicated that the deviation of the doping distribution in the radial direction became less than 1.1 by using the neutron filter, which was made from aluminum alloy of 2 mm thickness including natural boron of 1%.

Journal Articles

Full core burn-up calculation at JRR-3 with MVP-BURN

Komeda, Masao; Yamamoto, Kazuyoshi; Kusunoki, Tsuyoshi

Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 7 Pages, 2008/09

Research reactors use a burnable poison to suppress an excess reactivity in the beginning of reactor lifetime. The JRR-3 (Japan Research Reactor No.3) has used cadmium wires of radius 0.02cm as a burnable poison. This report describes burn-up calculations of plate fuel models and full core models with MVP-BURN, which is a burn-up calculation code using Monte Carlo method and has been developed in JAEA (Japan Atomic Energy Agency). As the results of calculations of plate models, between a model composed of one burn-up region along the radius direction and a model composed of a few burn-up regions along the radius direction, the effective absorption cross section of $$^{113}$$Cd has had different tendency on reaching approximate 40th day (10000 MWd/t). And as results of calculations of full core model, it has been indicated that k$$_{eff}$$ is almost same till approximate 80th day (22000 MWd/t) between a model composed of one burn-up region along the vertical direction and a model composed of a few burn-up regions along the vertical direction. However difference of $$^{113}$$Cd burn-up becomes pronounced and each k$$_{eff}$$ makes a difference after 80th day.

JAEA Reports

Characterization measurement of JRR-4 utilization facility

Kishi, Toshiaki; Motohashi, Jun; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya

JAEA-Technology 2008-054, 99 Pages, 2008/08

JAEA-Technology-2008-054.pdf:3.22MB

JRR-4 had carried out modification works for the purpose of reducing the enrichment level of fuel. About utilization facilities, followings were installed new neutron beam facility, renewal irradiation facility that was modified pneumatic irradiation facility for activation analysis of short-lived nuclides. This report describes the characteristic measurement by initial core and equilibrium core in 2001 by renewal JRR-4. Utilization facilities had been identified equal performance before modify about neutron flux and cadmium ratio on 1998 and 2001. And we have achieved less than 5% of irradiation uniformity at N-pipe. The maximum neutron flux is about 2.2$$times$$10$$^{13}$$m$$^{-2}$$$$cdot$$s$$^{-1}$$ at the New neutron beam facility and the maximum neutron flux is about 1$$times$$10$$^{11}$$m$$^{-2}$$$$cdot$$s$$^{-1}$$ at the prompt $$gamma$$-ray analysis facility got good quality performance for medical irradiation and fundamental examination of it.

JAEA Reports

Conceptual design of irradiation experimental device for 12 inch NTD-Si ingot in JRR-4 (Contract research)

Yagi, Masahiro; Watanabe, Masanori; Oyama, Koji; Komeda, Masao; Yamamoto, Kazuyoshi; Kashima, Yoichi

JAEA-Technology 2008-015, 91 Pages, 2008/03

JAEA-Technology-2008-015.pdf:22.92MB

The irradiation experimental device is designed by surveying analytically an irradiation condition to improve the neutron flux distribution of the radial direction on NTD-Si by using neutron transportation calculation Monte Carlo calculation code MCNP5 in order to develop neutron irradiation technology for the large-diameter silicon to 12 inches diameter at the maximum and an irradiation experiment will be performed in JRR-4. Thus the validity of the design technique of the irradiation device will be confirmed by this experiment. The irradiation experimental device is installed in the side of the core tank outer wall. A 12 inches silicon ingot of 60cm in height is irradiated in a reflector cover which surrounds the silicon ingot for increasing the flux. The silicon ingot is rotated during irradiation in order to require the condition of uniformly distributed thermal neutron flux over whole circumferences. A uniform irradiation condition was achieved by the pass-through core method, in which silicon ingot moved up and down with rotating. The condition was satisfied when silicon was covered with the thermal neutron filter, which is made from aluminum alloy of thickness of 2mm with natural boron element ratio of 1.5%, and was moved in the range from -42mm to 22mm for the center of the reactor core. The deviation of the Si-30 neutron absorption reaction rate was range from -3.2% to +5.3% in the intermediate volume of 40cm height and the neutron absorption reaction ratio of the circumference to the center was within 1.09 in the volume.

JAEA Reports

Guidance of operation practice and nuclear physics experiments using JRR-4

Yokoo, Kenji; Horiguchi, Hironori; Yagi, Masahiro; Nagadomi, Hideki; Yamamoto, Kazuyoshi; Sasajima, Fumio; Oyama, Koji; Ishikuro, Yasuhiro; Sasaki, Tsutomu; Hirane, Nobuhiko; et al.

JAEA-Technology 2007-018, 104 Pages, 2007/03

JAEA-Technology-2007-018.pdf:5.92MB

Reactor operation training using JRR-4 (Japan Research Reactor No.4) was started in FY 1969, one of the curriculums of Nuclear Technology and Education Center (NuTEC). After that, the program was updated and carried out for reactor operation training, control rod calibration, and measurement of various kind of characteristics. JRR-4 has been contributed for nuclear engineer training that is over 1,700 trainees from bother domestic and foreign countries. JRR-4 can be used for experiment from zero power to 3500kW, and the trainees can make experience to operate the reactor from start up to shut down, not only zero-power experiments (critical approach, control rod calibration, reactivity measurement, etc.) but also other experiments under high power operation (xenon effect, temperature effects, reactor power calibration, etc.). This report is based on various kinds of guidance texts using for training, and collected for operation and experiments for reactor physics.

Journal Articles

Development of JCDS, a computational dosimetry system at JAEA for boron neutron capture therapy

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Matsumura, Akira*; Yamamoto, Tetsuya*; Nakagawa, Yoshinobu*

Journal of Physics; Conference Series, 74, p.021010_1 - 021010_7, 2007/00

no abstracts in English

JAEA Reports

Experiments of JRR-4 low-enriched-uranium-silicied fuel core

Hirane, Nobuhiko; Ishikuro, Yasuhiro; Nagadomi, Hideki; Yokoo, Kenji; Horiguchi, Hironori; Nemoto, Takumi; Yamamoto, Kazuyoshi; Yagi, Masahiro; Arai, Nobuyoshi; Watanabe, Shukichi; et al.

JAEA-Technology 2006-028, 115 Pages, 2006/03

JAEA-Technology-2006-028.pdf:7.96MB

JRR-4, a light-water-moderated and cooled, swimming pool type research reactor using high-enriched uranium plate-type fuels had been operated from 1965 to 1996. In order to convert to low-enriched-uranium-silicied fuels, modification work had been carried out for 2 years, from 1996 to 1998. After the modification, start-up experiments were carried out to obtain characteristics of the low-enriched-uranium-silicied fuel core. The measured excess reactivity, reactor shutdown margin and the maximum reactivity addition rate satisfied the nuclear limitation of the safety report for licensing. It was confirmed that conversion to low-enriched-uranium-silicied fuels was carried out properly. Besides, the necessary data for reactor operation were obtained, such as nuclear, thermal hydraulic and reactor control characteristics. This report describes the results of start-up experiments and burnup experiments. The first criticality of low-enriched-uranium-silicied core was achieved on 14th July 1998, and the operation for joint-use has been carried out since 6th October 1998.

Journal Articles

Development of computational dosimetry system "JCDS" for neutron capture therapy

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Matsumura, Akira*; Nakagawa, Yoshinobu*

Hoshasen, 31(4), p.287 - 297, 2005/10

no abstracts in English

Journal Articles

Development of a wide-range paired scintillator with optical fiber neutron monitor for BNCT irradiation field study

Ishikawa, Masayori*; Kumada, Hiroaki; Yamamoto, Kazuyoshi; Kaneko, Junichi*; Bengua, G.*; Unesaki, Hironobu*; Sakurai, Yoshinori*; Tanaka, Kenichi*; Kosako, Toshiso*

Nuclear Instruments and Methods in Physics Research A, 551(2-3), p.448 - 457, 2005/10

 Times Cited Count:11 Percentile:61.73(Instruments & Instrumentation)

A wide range thermal neutron detector was developed based on the Scintillator with Optical Fiber (SOF) detector which has been previously used for thermal neutron monitoring during boron neutron capture therapy irradiation. With this new detector system we intended to address the issues of real-time thermal neutron flux measurement and the simultaneous measurement of a wide range of thermal neutron flux in a BNCT irradiation field which were difficult to implement with the gold wire activation method. A good agreement between the thermal neutron flux measured by the gold wire activation method and the paired SOF detector system was observed. However, measurements which would normally take a few days to perform with the gold wire activation method were obtained in just about 15 min using the SOF detector system. We also confirmed the dynamic range of linearity for the SOF detector system to be in the order of magnitude of 1e-4.

JAEA Reports

Estimation methods of blood boron concentration and error evaluation during boron neutron capture therapy for malignant brain tumor

Shibata, Yasushi*; Yamamoto, Kazuyoshi; Matsumura, Akira*; Yamamoto, Tetsuya*; Hori, Naohiko; Kishi, Toshiaki; Kumada, Hiroaki; Akutsu, Hiroyoshi*; Yasuda, Susumu*; Nakai, Kei*; et al.

JAERI-Research 2005-009, 41 Pages, 2005/03

JAERI-Research-2005-009.pdf:1.99MB

The measurement of neutron flux and boron concentration in the blood during medical irradiation is indispensable in order to evaluate the radiation in boron neutron capture therapy. It is, however, difficult to measure the blood boron concentration during neutron irradiation because access to the patient is limited. Therefore we prospectively investigated the predictability of blood boron concentrations using the data obtained at the first craniotomy after infusion of a low dosage of BSH. When the test could not be carried out, the blood boron concentration during irradiation was also predicted by using the 2-compartment model. If the final boron concentration after the end of the infusion is within 95% confidence interval of the prediction, direct prediction from biexponential fit will reduce the error of blood boron concentrations during irradiation to around 6%. If the final boron concentration at 6 or 9 hours after the end of infusion is out of 95% confidence interval of the prediction, proportional adjustment will reduce error and expected error after adjustment to around 12%.

Journal Articles

Combination of boron and gadolinium compounds for neutron capture therapy; An $$in Vitro$$ study

Matsumura, Akira*; Zhang, T.*; Nakai, Kei*; Endo, Kiyoshi*; Kumada, Hiroaki; Yamamoto, Tetsuya*; Yoshida, Fumiyo*; Sakurai, Yoshinori*; Yamamoto, Kazuyoshi; Nose, Tadao*

Journal of Experimental and Clinical Cancer Research, 24(1), p.93 - 98, 2005/03

no abstracts in English

112 (Records 1-20 displayed on this page)