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Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*; Matsuda, Norihiro; Hashimoto, Shintaro; Furuta, Takuya; Noda, Shusaku; Ogawa, Tatsuhiko; Iwase, Hiroshi*; Nakashima, Hiroshi; et al.
JAEA-Conf 2014-002, p.69 - 74, 2015/02
A general purpose Monte Carlo Particle and Heavy Ion Transport code System, PHITS, is being developed through the collaboration of several institutes in Japan and Europe. PHITS can deal with the transport of nearly all particles, including neutrons, protons, heavy ions, photons, and electrons, over wide energy ranges using various nuclear reaction models and data libraries. All components of PHITS such as its source, executable and data-library files are assembled in one package and then distributed to many countries. More than 1,000 researchers apply the code to various research and development fields such as nuclear technology, accelerator design, medical physics, and cosmic-ray research. This presentation briefly summarizes the physics models implemented in PHITS, and introduces some important functions for specific applications, such as an event generator mode and a radiation damage calculation function.
) reactions with the ANNRI-Cluster Ge detectors at J-PARCHara, Kaoru; Goko, Shinji*; Harada, Hideo; Hirose, Kentaro; Kimura, Atsushi; Kin, Tadahiro*; Kitatani, Fumito; Koizumi, Mitsuo; Nakamura, Shoji; Toh, Yosuke; et al.
JAEA-Conf 2014-002, p.88 - 92, 2015/02
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.
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.
Iwamoto, Nobuyuki
JAEA-Conf 2014-002, p.110 - 116, 2015/02
Neutron nuclear data on Rh isotope in the energy region above resolved resonances were not revised in the latest version of JENDL-4.0. Radioactive nuclides, which could become important to nuclear medicine, are produced by nuclear reaction on stable Rh isotope. In this work neutron induced reaction cross sections on 
Rh were evaluated by using nuclear reaction calculation code CCONE. The incident energy range was considered from 1keV to 20 MeV. The evaluation was made by comparing the calculated results with available experimental data of the total, elastic scattering, capture, (
,2), (,
), (,
) reaction cross sections, angular distributions of elastically scattered neutrons and -ray emission spectra. The present results well explain the experimental data.
Konno, Chikara; Ota, Masayuki; Asahara, Hiroo; Ochiai, Kentaro; Sato, Satoshi
JAEA-Conf 2014-002, p.160 - 166, 2015/02
IAEA released a new version of Evaluated Nuclear Data Library (FENDL), FENDL-3.0 in 2012 in order to extend the neutron energy range of neutron-induced reactions from 20 MeV to more than 60 MeV and to include general purpose and activation data libraries for proton- and deuteron-induced reactions up to more than 60 MeV. We already reported the benchmark tests of the general purpose data library for neutron-induced reactions below 20 MeV in FENDL-3.0. Now we present the benchmark tests of the general purpose data library for neutron-induced reactions in FENDL-3.0 by using iron and concrete shielding experiments with the 40 and 65 MeV neutron sources at TIARA in JAEA. As a result, it is found out that the calculations with FENDL-3.0 agree with the measured ones for the iron experiment well, while they overestimate the measured ones for the concrete experiment more for the thicker assemblies.
Hazama, Taira
JAEA-Conf 2014-002, p.26 - 31, 2015/02
Various nuclear data have been applied to the reactor physics test analyses in Monju. Good accuracy is confirmed with JENDL-3.3 for the analysis of reactor physics tests performed in 1994-1995. On the other hand, a clear discrepancy is observed for the reactivity loss caused by the 
Pu decay from 1994 to 2010. The discrepancy is resolved with JEDNL-4.0, where the revision of the Pu fission cross section and Am capture cross section contributes. Use of covariance data is promising application in the future design calculation. Based on the reactor physics test analyses, the reliability of the covariance data is investigated and covariance data that needs improvement are extracted. It is suggested that data on the average cosine of the scattering angle of 
Na need to be improved.
-rayKitatani, Fumito; Harada, Hideo; Goko, Shinji*; Utsunomiya, Hiroaki*; Akimune, Hidetoshi*; Toyokawa, Hiroyuki*; Yamada, Kawakatsu*
JAEA-Conf 2014-002, p.57 - 62, 2015/02
Ota, Masayuki; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi; Konno, Chikara
no journal, ,
Titanium is contained in lithium titanate, which is a tritium breeding material candidate. In the nuclear design, accurate nuclear data are needed. However, few benchmark experiments had been performed for titanium. Thus we performed a benchmark experiment with a titanium assembly and a DT neutron source at JAEA/FNS. The assembly was a titanium slab of 45 cm
45 cm40 cm covered with 5 or 10 cm thick Li
O blocks. Dosimetry reaction rates were measured by the foil activation method of niobium, indium and gold inside the assembly. And fission rate of U-235 was measured by using micro fission chambers. This experiment was analyzed by using Monte Carlo neutron transport code MCNP5-1.40 with recent nuclear data libraries of ENDF/B-VII.0, ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0 and JENDL-4.0u1. The calculation results were compared with the measured one in order to validate nuclear data libraries of titanium.
