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Journal Articles

Cross section measurement of $$^{117}$$Sn$$(n,gamma)$$ using ANNRI-NaI(Tl) spectrometer at J-PARC

Hirose, Kentaro; Furutaka, Kazuyoshi; Hara, Kaoru; Harada, Hideo; Kimura, Atsushi; Kitatani, Fumito; Koizumi, Mitsuo; Nakamura, Shoji; Oshima, Masumi; Toh, Yosuke; et al.

JAEA-Conf 2013-002, p.173 - 178, 2013/10

Journal Articles

Measurement of 100 MeV/u carbon incident neutron production cross sections on a carbon target

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*

JAEA-Conf 2013-002, p.137 - 142, 2013/10

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and $$gamma$$-ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of double differential cross sections of secondary neutron is important to risk assessment of extra dose to organs in the vicinity of the irradiated tumor. Accurate data in neutron energy around 1 MeV is required because neutron in the energy region has large relative biological effectiveness. Neutron double differential cross sections by inducing 290 MeV/u carbon ion to bio-elements have been obtained experimentally. In order to have knowledge of neutron production by deceleration carbon in a human body, we measured the neutron yields from carbon ion incidence on a carbon target of neutron energy below 1 MeV in wide angular range from 15$$^{circ}$$ to 90$$^{circ}$$ with 100 MeV/u.

Journal Articles

GEANT4 simulation study of a $$gamma$$-ray detector for neutron resonance densitometry

Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Takamine, Jun; Kureta, Masatoshi; Iimura, Hideki

JAEA-Conf 2013-002, p.119 - 124, 2013/10

We have proposed a system to quantify nuclear materials in melted fuels in the reactors of the Fukushima Daiichi Nuclear Power Plant. The system utilizes non destructive techniques combining neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA). This is because the melted fuels are though to involve not only nuclear materials but also impurities such as ${it e.g.}$ Hydrogen, Boron, Zirconium, and Iron. Using the combined system, we would be able to identify those non-nuclear materials by NRCA and accurately measure nuclear materials by NRTA. A $$gamma$$-ray detector for NRCA consists of a cylindrical LaBr$$_{3}$$ scintillation counter and a well-type LaBr$$_{3}$$ one. The well-type counter is served as a back-catcher detector and individual signals recorded in the two counters are summed to aim at reducing the Compton edge originating from $$^{137}$$Cs that generate intense background for the NRCA measurement. According to GEANT4 simulation, It can be seen that the Compton edge is suppressed by the well-type counter. For example, thanks to the well-type counter, a count at an energy of $$^{10}$$B-derived $$gamma$$-rays (478 keV) is reduced by $$sim$$0.15. In this presentation, we show performance of the $$gamma$$-ray detector using GEANT4 simulation. In addition, comparing results based on evaluated cross sections of ENDF-VII.0 with those based on JENDL-4.0, we discuss differences in performance expected for the $$gamma$$-ray detector.

Journal Articles

Measurements and simulations of the responses of the cluster Ge detectors to $$gamma$$ rays

Hara, Kaoru; Goko, Shinji*; Harada, Hideo; Hirose, Kentaro; Kimura, Atsushi; Kin, Tadahiro*; Kitatani, Fumito; Koizumi, Mitsuo; Nakamura, Shoji; Toh, Yosuke

JAEA-Conf 2013-002, p.161 - 166, 2013/10

Journal Articles

Journal Articles

Evaluation of neutron induced reaction cross sections on Re isotopes

Iwamoto, Nobuyuki

JAEA-Conf 2013-002, p.143 - 148, 2013/10

Neutron nuclear data on Re isotopes are not included in the latest version of JENDL-4.0. Radioactive nuclides, which could become important to nuclear medicine, were produced by nuclear reaction on stable Re isotopes. In this work neutron induced reaction cross sections on Re isotopes ($$^{185,186,187}$$Re) were evaluated by using nuclear reaction calculation code CCONE. The incident energy range was considered from 10$$^{-5}$$ eV to 20 MeV, whose range included the resolved resonance region. The evaluation was made by comparing the calculated results with available experimental data of the total, elastic scattering, capture, (n,2n), (n,p), (n,$$alpha$$) reaction cross sections on $$^{185,187}$$Re and elemental Re. The present results well explain the experimental data. The capture cross sections on Re isotopes are important to consider the Re-Os cosmochronology. Maxwellian averaged capture cross sections were also derived and compared with the data of KADoNiS database.

Journal Articles

Evaluation of covariance data of JENDL

Iwamoto, Osamu

JAEA-Conf 2013-002, p.41 - 46, 2013/10

One of the main topics of JENDL-4.0, was the enhancement of covariance data. Especially for actinides, they were evaluated and adopted to the all data of resonance parameters, reaction cross sections, fission neutron spectra, and the number of fission neutrons. The covariance matrices were evaluated based on experimental data and evaluation methodology of the evaluated data. The fission cross sections, for which experimental data were abundant, were evaluated using least-square method resulting in the most probable value as well as a covariance matrix. For the cross sections that were evaluated using nuclear model calculations, the covariance matrices were obtained using model parameter sensitivities. The methods and results of the covariance evaluations in JENDL-4.0 will be presented with recent progress of ongoing efforts on the covariance evaluation of non-actinides of JENDL-4.0.

Journal Articles

Nuclear data for severe accident analysis and decommissioning of nuclear power plant

Okumura, Keisuke; Kojima, Kensuke; Okamoto, Tsutomu; Hagura, Hiroyuki; Suyama, Kenya

JAEA-Conf 2013-002, p.15 - 20, 2013/10

Three-dimensional nuclide inventory and decay heat analysis were performed for the Fukushima Dai-ichi Power Plants (1F1, 1F2, 1F3) by using MOSRA system with JENDL-4.0 library. In the analysis, nuclide inventory for approximately 1400 nuclides were estimated in consideration of radial and axial burn-up and void distributions. Total decay heat and its distribution in each plant were estimated by the sum of all nuclide contributions. The obtained decay heat was compared with the results of simple evaluation formulas used in severe accident analyses. The results of the simple evaluation formulas agree with our results within 20%. For future decommissioning of commercial nuclear power plants, new activation cross-sections library for ORIGEN-S is also under development in the cooperative study program between JAEA and JAPCO. The present status and future plan are shown from view points of nuclear data and method.

Journal Articles

Activation analyses of air in the accelerator vault of LIPAc building by deuteron beam at 5 MeV and 9 MeV

Takahashi, Hiroki; Maebara, Sunao; Sakaki, Hironao; Suzuki, Hiromitsu; Sugimoto, Masayoshi

JAEA-Conf 2013-002, p.109 - 112, 2013/10

Journal Articles

Uncertainty evaluation for $$^{244}$$Cm production in spent fuel of light water reactor by using burnup sensitivity analysis

Oizumi, Akito; Yokoyama, Kenji; Ishikawa, Makoto; Kugo, Teruhiko

JAEA-Conf 2013-002, p.59 - 64, 2013/10

Journal Articles

Application of the cross section covariance data to fast reactor core design

Sugino, Kazuteru

JAEA-Conf 2013-002, p.53 - 58, 2013/10

In order to contribute the validation of the cross-section covariance data, an equality was investigated between uncertainties of core characteristics evaluated by the conventional mock-up experimental approach and the current uncertainty quantification one.

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