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Endo, Akira
Radiation Measurements, 45(10), p.1484 - 1490, 2010/12
Times Cited Count：2 Percentile：17.46(Nuclear Science & Technology)The present paper reviews dose assessment in the criticality accident occurred in September, 1999, at JCO, Tokai-mura, Japan. In the accident, almost all doses were brought by neutrons and 
-rays emitted from the precipitation tank. Dose assessment was performed for three workers at the accident spot, JCO employees, emergency workers and members of the public by experts at JAERI, JNC and NIRS. The assessment was carried out using records of dosimeters, radiation monitoring data in and around the site, analysis of biological specimens, and computer simulation technique. Based on the results of dose assessment, It was concluded that and concluded that deterministic effects are not expected except for the three overexposed workers and that the probability of stochastic effects is very small and will be undetectable.
Satoh, Daiki; Iwamoto, Yosuke; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Sato, Tatsuhiko; Endo, Akira; Sakamoto, Yukio; Nakane, Yoshihiro; Nakashima, Hiroshi; et al.
Radiation Measurements, 45(10), p.1159 - 1162, 2010/12
Times Cited Count：1 Percentile：9.99(Nuclear Science & Technology)Elastic neutron-scattering cross sections for carbon nucleus have been measured by using 134-MeV monoenergetic neutron beam in Research Center for Nuclear Physics (RCNP), Osaka University. The measured angles were set at 6
, 8, and 15 in laboratory system. The liquid organic scintillators, whose size is 12.7 cm in diameter and 12.7 cm in thickness, were mounted at each angle as neutron detector. In the off-line analysis, the events of elastic-neutron scattering were extracted on basis of the Time-of-Flight (TOF) information. The results were compared with the data measured by the groupe of U.C. Davis with a recoil proton spectrometer and the evaluations of the nuclear data libraries, JENDL/HE-2007 and ENDF/B-VII.0. Our results show a good agreement with the data of U.C. Davis. This indicates that our experimental method based on the TOF teqnique is appropriate to the measurement of elastic neutron-scattering cross section in this energy region. In addition, we exhibit that the data of ENDF/B-VII.0 represent the experimental data, but JENDL/HE-2007 underestimates about 30
in the forward angle region.
Li(p,n)Be reactionTanimura, Yoshihiko; Tsutsumi, Masahiro; Saegusa, Jun; Shikaze, Yoshiaki; Yoshizawa, Michio
Radiation Measurements, 45(10), p.1163 - 1166, 2010/12
Times Cited Count：4 Percentile：30.63(Nuclear Science & Technology)Mono-energetic neutron calibration fields have been developed at the Facility of Radiation Standards of Japan Atomic Energy Agency using a 4MV Pelletron accelerator. The fields of 8, 27, 144, 250, 565 keV and 1.2, 2.5, 5.0, 14.8 MeV neutrons were established using scandium, lithium, deuterium and tritium targets. The nuclear reactions between the accelerated particles and the target materials produce not only the mono-energetic neutrons but also unwanted photons. As the photons can affect the readings of dosemeters, their effects should be evaluated. In this work the photons in the 144, 250 and 565 keV neutron fields from a lithium fluoride target were measured using a cylindrical NaI(Tl) detector with 7.62 cm both in diameter and in length. The ambient dose equivalent H*(10) for the photons was evaluated by applying the "G(E) function" to the measured pulse height spectrum.
Takada, Masashi*; Yajima, Kazuaki*; Yasuda, Hiroshi*; Sato, Tatsuhiko; Nakamura, Takashi*
Radiation Measurements, 45(10), p.1297 - 1300, 2010/12
Times Cited Count：3 Percentile：24.08(Nuclear Science & Technology)In this study, we carried the phoswich-typed neutron detector on the business jet, and measured neutron energy spectrum above Japan.
Am-Li neutron field to simulate reactor spectraTsujimura, Norio; Yoshida, Tadayoshi
Radiation Measurements, 45(10), p.1359 - 1362, 2010/12
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)The neutron calibration field using Am-Li sources and a moderator was designed to simulate neutron fields found outside the reactor. The moderating assembly selected for the design calculation consists of a cube of graphite blocks with dimensions of 50 cm by 50 cm by 50 cm, in which Am-Li sources are placed. The depths of the source position were optimized to be 15 cm through Monte Carlo calculations. This moderated neutron source will provide a test field that has a large number of intermediate energy neutrons with a small portion of MeV component.
