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Nakamura, Takemi; Horiguchi, Hironori; Kishi, Toshiaki; Motohashi, Jun; Sasajima, Fumio; Kumada, Hiroaki*
Proceedings of 14th International Congress on Neutron Capture Therapy (ICNCT-14) (CD-ROM), p.379 - 382, 2010/10
The clinical trials of BNCT have been conducted using JRR-4. The JRR-4 stopped in January 2008, because the graphite reflector was considerably damaged. For this reason, the specifications of graphite reflectors were renewal. All existing graphite reflectors of JRR-4 were changed by new graphite reflectors. The resumption of JRR-4 was carried out with new graphite reflectors in February 2010. We measured the characteristics of neutron beam at the JRR-4 Neutron Beam Facility. A cylindrical water phantom was put the gap for 1cm from the beam port. TLD and gold wire were inserted within the phantom when the phantom was irradiated. The results of the measured thermal neutron flux and the 
dose in water were compared with MCNP calculations. The calculated results showed the same tendency with the experimental results. These results are proceeding well and will be reported in full paper at July 2010.
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 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.
Kishi, Toshiaki; Ichimura, Shigeju; Kinase, Masami; Wada, Shigeru
JAEA-Conf 2008-010, p.146 - 158, 2008/12
The Department of Research Reactor and Tandem Accelerator operates three research reactors, JRR-3, JRR-4 and NSRR. JRR-3 was operated for 180 days in Japanese Fiscal Year 2007. The neutron bender system was installed on the cold neutron guide tube. As a result, the cold beam intensity has increased by about 10 times. JRR-4 was operated for 93 days in Japanese Fiscal Year 2007. Boron neutron capture therapy was carried out 25 times. The trouble of reflector occurred in December 2007. At present, the reactor has stopped to replace the reflectors. NSRR has been built for the investigation of light water reactor fuel behavior during off-normal conditions such as reactivity-initiated accident. Recently the investigation is performed for the behavior of high burnup fuel and mixed oxide fuel. At present, the NSRR experiments with the new capsule are continuing for high burnup fuels of 59, 67 and 71 GWd/t.
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
10
m
s
at the New neutron beam facility and the maximum neutron flux is about 110
ms at the prompt -ray analysis facility got good quality performance for medical irradiation and fundamental examination of it.
Nakamura, Takemi; Kumada, Hiroaki; Kishi, Toshiaki
Proceedings of 12th International Congress on Neutron Capture Therapy (ICNCT-12), p.535 - 538, 2006/10
no abstracts in English
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%.
Yamamoto, Tetsuya*; Matsumura, Akira*; Nakai, Kei*; Shibata, Yasushi*; Endo, Kiyoshi*; Sakurai, Fumio; Kishi, Toshiaki; Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya
Applied Radiation and Isotopes, 61(5), p.1089 - 1093, 2004/11
Times Cited Count：56 Percentile：94.75(Chemistry, Inorganic & Nuclear)no abstracts in English
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Sakurai, Yoshinori*; Kobayashi, Toru*
Proceedings of 11th World Congress on Neutron Capture Therapy (ISNCT-11) (CD-ROM), 15 Pages, 2004/10
To carry out the boron neutron capture therapy (BNCT) using the epithermal neutron, the epithermal neutron beam intensity was measured by using 
Au reaction rate activated on the resonance absorption peak (4.9eV). Two scaling factors, which are the reactor power calibration factor and the calculation/experiment (C/E) scaling factor, are necessary in order to correct with the simulation and actual irradiation experiment. First, an optimum detector position was investigated using MCNP code. The result of MCNP calculation showed that the influence of subject placed at the collimator was below 1% when the detector was placed in the distance of over 20cm from the collimator. Therefore we installed the monitor holders near the bismuth block in order to set three gold wire monitors. The factors were determined in the calibration experiments that measure the thermal neutron flux in the phantom and reaction rate of the gold wire monitors. The monitoring technique to measure epithermal neutron beam intensity was applied to clinical irradiation with the epithermal neutron beam.
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Endo, Kiyoshi*; Yamamoto, Tetsuya*; Matsumura, Akira*; Uchiyama, Junzo; Nose, Tadao*
JAERI-Tech 2002-092, 23 Pages, 2002/12
JAERI-Tech-2002-092.pdf:5.22MB
Thermal neutron flux is determined using the gold wires in current BNCT irradiation, so evaluation of arbitrary points after the irradiation is limited in the quantity of these detectors. In order to make up for the weakness, dose estimation of a patient is simulated by a computational dose calculation supporting system. In another way without computer simulation, a medical irradiation condition can be replicate experimentally using of realistic phantom which was produced from CT images by rapid prototyping technique. This phantom was irradiated at a same JRR-4 neutron beam as clinical irradiation condition of the patient and the thermal neutron distribution on the brain surface was measured in detail. This experimental evaluation technique using a realistic phantom is applicable to in vitro cell irradiation experiments for radiation biological effects as well as in-phantom experiments for dosimetry under the nearly medical irradiation condition of patient.
Kumada, Hiroaki; Kishi, Toshiaki; Hori, Naohiko; Yamamoto, Kazuyoshi; Torii, Yoshiya
Research and Development in Neutron Capture Therapy, p.115 - 119, 2002/09
no abstracts in English
-ray dose using low neutron-sensitive TLD (UD-170LS) for Intra-Operative Boron Neutron Capture Therapy (IOBNCT)Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Kishi, Toshiaki; Yamamoto, Tetsuya*; Matsumura, Akira*
Research and Development in Neutron Capture Therapy, p.499 - 503, 2002/09
In order to estimate the maximum gamma-ray dose in the brain in Intra-Operative Boron Neutron Capture Therapy (IOBNCT), this study was conducted for (1) the development of low neutron-sensitive TLD (UD-170LS-T2), (2) the correlation of capture gamma-ray dose profile in a phantom for various collimator sizes, and (3) the formula for simple estimation of maximum gamma-ray dose on IOBNCT. The sensitivity of TLD, as 
Co -ray equivalent, for thermal neutron was 5.1
0.810
(Co-Gycm
)The average relative deviations between predicted and measured -ray dose for the mixed epithermal-thermal neutron beam in the phantom were 8.5%. The accuracy of the -ray dose determination in the clinical BNCT may be improved by this simple method.
Endo, Kiyoshi*; Matsumura, Akira*; Yamamoto, Tetsuya*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Kashimura, Takanori*; Otake, Shinichi*
Research and Development in Neutron Capture Therapy, p.425 - 430, 2002/09
Using the Rapid Prototyping Technique, we produced a realistic phantom as a formative model of a patient head. This realistic phantom will contribute to verification of our planning system. However, cross-correlation among the calculations using the JAERI Computational Dosimetry System (JCDS), the realistic phantom, and the in vivo measurements were not fully completed because of the difficulty involved in modeling a post-surgical brain and a thermal neutron shield. The experimental simulation technique using the realistic phantom is a useful tool for more reliable dose planning for the intraoperative BNCT.
biological effectiveness of JRR-4 epithermal neutron beam; Experiment under free air beam and in water phantom (Cooperative research)Yamamoto, Tetsuya*; Yamamoto, Kazuyoshi; Matsumura, Akira*; Kumada, Hiroaki; Kishi, Toshiaki; Hori, Naohiko; Torii, Yoshiya; Horiguchi, Yoji; Nose, Tadao*
JAERI-Research 2002-011, 56 Pages, 2002/05
JAERI-Research-2002-011.pdf:3.17MB
The surviving curve and RBE of dose components generated in boron neutron capture therapy (BNCT) were separately determined in neutron beams at JRR-4. Surviving fraction of V79 cell with or without 
B was obtained using an epithermal neutron beam (ENB), a mixed thermal-epithermal neutron beam (TNB-1), and a thermal neutron beam(TNB-2), which were used or planned to use for clinical trial. The cell killing effect of these beams depended highly on the neutron beam used, according to the epithermal and fast neutron content in the beam. RBE of the boron capture were 3.990.24, 3.040.19 and 1.430.08, RBE of the high-LET dose components based were 2.500.32, 2.340.30 and 2.170.28 for ENB, TNB-1 and TNB-2, respectively. The experimental determination of biological effectiveness factor outlined in this paper is applicable to the dose calculation for each dose component of the neutron beams and contribute to an accurate RBE as comparison with a neutron beam at a different facility employed in ongoing and planned BNCT clinical trials.
Yamamoto, Kazuyoshi; Yamamoto, Tetsuya*; Kumada, Hiroaki; Torii, Yoshiya; Kishi, Toshiaki; Matsumura, Akira*; Nose, Tadao*; Horiguchi, Yoji
JAERI-Tech 2001-017, 38 Pages, 2001/03
no abstracts in English
-ray analysis of JRR-4Yamamoto, Kazuyoshi; Kishi, Toshiaki; Hori, Naohiko; Kumada, Hiroaki; Torii, Yoshiya; Horiguchi, Yoji
JAERI-Tech 2001-016, 34 Pages, 2001/03
JAERI-Tech-2001-016.pdf:1.56MB
no abstracts in English
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Kishi, Toshiaki; Horiguchi, Yoji
JAERI-Tech 2001-015, 43 Pages, 2001/03
JAERI-Tech-2001-015.pdf:4.95MB
no abstracts in English
-ray analysis device at JRR-4Hori, Naohiko; Yamamoto, Tetsuya*; Matsumura, Akira*; Torii, Yoshiya; Yamamoto, Kazuyoshi; Kishi, Toshiaki; Takada, Juntaro*
Proceedings of 9th International Symposium on Neutron Capture Therapy for Cancer, p.263 - 264, 2000/10
no abstracts in English
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Hori, Naohiko; Kishi, Toshiaki; Takada, Juntaro*; Otake, S.*
Proceedings of 9th International Symposium on Neutron Capture Therapy for Cancer, p.243 - 244, 2000/10
no abstracts in English
Torii, Yoshiya; Yamamoto, Kazuyoshi; Kishi, Toshiaki*; Hori, Naohiko; Kumada, Hiroaki; Horiguchi, Yoji
Proceedings of 9th International Symposium on Neutron Capture Therapy for Cancer, p.241 - 242, 2000/10
no abstracts in English
Endo, Kiyoshi*; Nakai, Kei*; Yoshida, Fumiyo*; Shirakawa, Shin*; Yamamoto, Tetsuya*; Matsumura, Akira*; Sawahata, Hiroyuki*; Kawate, Minoru*; Saito, Kimiaki; Kumada, Hiroaki; et al.
no journal, ,
no abstracts in English
