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Nakao, Taro; Nakamura, Shoji; Terada, Kazushi; Kimura, Atsushi; Harada, Hideo; Igashira, Masayuki*; Katabuchi, Tatsuya*; Hori, Junichi*
JAEA-Conf 2015-003, p.303 - 306, 2016/03
In spite of that the precise information of the total amount of the measurement sample is required for the neutron capture cross-section determination, it is not always performed in sufficient accuracy. Therefore, it is necessary to determine the absolute amount of samples accurately with non-destructively. This presentation will report on the future plan about the heat deposit measurement from minor actinides samples in order to determine the absolute amount of samples non-destructively, especially about the radiation shielding which is a unique problem of RI sample case. Also report about the result of the benchmark test measurement using 
Am 
-ray standard source. Present study includes the result of "Research and Development for accuracy improvement of neutron nuclear data on minor actinides" entrusted to the Japan Atomic Energy Agency by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).
-ray strength function based on measured neutron capture -ray spectraIwamoto, Nobuyuki
JAEA-Conf 2015-003, p.119 - 124, 2016/03
Gamma-ray Strength Function (GSF) is one of the important ingredients to describe -ray emissions in nuclear reaction. In order to fix the GSF, it is valuable to measure photoneutron cross sections and neutron capture -ray spectra. The latter has been systematically measured at Tokyo Institute of Technology, where the capture cross sections have been derived in the 10-100 keV and 
550 keV energy ranges. In this study those capture -ray spectra and cross sections of isotopes from Fe to Au were calculated by nuclear reaction calculation code CCONE. This code now takes into account various types of GSF (e.g., standard Lorentzian, enhanced generalized Lorentzian, and modified Lorentzian forms). We evaluated the validity of calculated capture -ray spectra and also cross sections on the basis of different GSFs, comparing them with the experimental data. We will report the evaluated results.
PdNakamura, Shoji; Kimura, Atsushi; Toh, Yosuke; Harada, Hideo; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Igashira, Masayuki*; Hori, Junichi*; Kino, Koichi*
JAEA-Conf 2015-003, p.113 - 118, 2016/03
Experiments were carried out with the Ge detector of ANNRI to confirm whether or not the weak resonances were surely due to Pd. The prompt rays due to capture reaction of Pd were clearly observed at the -ray energy at 115 kev and around 300 keV. When a TOF spectrum was extracted by gating at the prompt ray around 300 keV, the small resonance peaks were revealed at the neutron energy of 146 and 156 eV.
Koura, Hiroyuki; Katakura, Junichi*; Tachibana, Takahiro*; Minato, Futoshi
JAEA-Conf 2015-003, p.147 - 152, 2016/03
A chart of the nuclides 2014 version is now preparing to be published from JAEA. This will be the latest successive version of the chart since 1977, and continues every (approximately) four years until 2010. These charts include decay data of isotopes as half-lives, decay modes, and some isomeric states. In addition, the periodic table of elements, fundamental physical constants, thermal neutron capture and fission cross sections are tabulated. The latest version is now compiled with recent experimental data until the end of June in 2014. In the compilation process, we improved in the following parts: (1) Neutron or proton-unbound nuclei in the lighter region. (2) Drawing the neutron and proton-drip lines, and a boundary line of 
-delayed neutron emission. (3) 1- or 2-proton-emission theoretical half-lives are added for unmeasured nuclei in addition to original three partial half-lives of 
-decay, -decay and spontaneous fission. We compiled totally 3150 nuclides, which were experimental identified including 2914 life-measured nuclei. We will show overview of the chart with some statistics and examples.
Li(p,xn) reaction for incident energies up to 200 MeVMatsumoto, Yuiki*; Watanabe, Yukinobu*; Kunieda, Satoshi; Iwamoto, Osamu
JAEA-Conf 2015-003, p.191 - 196, 2016/03
Neutron emission from the Li(p,n)Be reaction can be divided into two components: a mono-energetic component for the transition to the ground and the 1st excited states and a continuum component formed by Li breakup processes. For the former, we have obtained the differential cross sections by interpolation based on Legendre fitting of available experimental data up to 45 MeV and apply DWBA calculations above 45 MeV. Next, we have applied the CCONE code to DDX calculations of the continuum component, and adjusted pre-equilibrium model parameters to reproduce experimental data well. Finally, both the results are merged and then the evaluated DDX data are completed.
Kunieda, Satoshi; Shibata, Keiichi; Fukahori, Tokio; Kawano, Toshihiko*; Paris, M.*; Hale, G.*
JAEA-Conf 2015-003, p.33 - 38, 2016/03
We present recent progress of nuclear data evaluation method in the resolved resonance range. Our multi-channel R-matrix code now includes photon-channel and computational capability of charged-particle elastic scattering. We also present the physical constraint from the theory in the analysis of experimental data. Example analysis results are shown for 
Be and 
O compound system. Finally, perspectives are discussed toward the advancement of nuclear data in the resonance region including those for medium-heavy nuclei.
Konno, Chikara; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro; Sato, Satoshi
JAEA-Conf 2015-003, p.131 - 136, 2016/03
We carried out the benchmark tests of the general-purpose data library for neutron-induced reactions in FENDL-3.0 with the integral experiments at JAEA/FNS, JAEA/TIARA and Osaka Univ./OKTAVIAN. We also tested the MATXS files of FENDL-3.0 with a simple calculation model and compared KERMA and DPA data included in the ACE and MATXS files of FENDL-3.0 with those in other nuclear data libraries. In this symposium we present the following problems in FENDL-3.0 found out in our study; (1) The 
O data above 20 MeV in FENDL-3.0 should be revised. (2) The most MATXS files in FENDL-3.0 have no energy-angular distribution data for the non-elastic scattering reaction. (3) Some of KERMA and DPA data included in the ACE and MATXS files of FENDL-3.0 should be revised.
Konno, Chikara; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro; Sato, Satoshi
JAEA-Conf 2015-003, p.125 - 130, 2016/03
At the last nuclear data symposium we presented the detailed analyses of the iron and concrete shielding experiments with 40 and 65 MeV neutrons at TIARA in JAEA in order to validate FENDL-3.0 and JENDL/HE-2007 and pointed out that calculation results with JENDL/HE-2007 underestimated the measured neutron spectra and calculated ones with FENDL-3.0 in the iron experiment with 65 MeV neutrons. Thus we studied reasons of this underestimation in detail. As a result, we specified that the larger non-elastic scattering cross section data of 
Fe in JENDL/HE-2007 caused the underestimation. The non-elastic scattering data of Fe in JENDL/HE-2007 should be revised.
Konno, Chikara; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro; Sato, Satoshi
JAEA-Conf 2015-003, p.137 - 141, 2016/03
For fusion reactor nuclear analyses we produce new nuclear group constant sets, FUSION-F21.175 (neutron: 175 groups, : 42 groups, P5 approximation) and FUSION-F21.42 (neutron: 42 groups, : 21 groups, P5 approximation), similar with FUSION-J3 and FUSION-40 from FENDL-2.1 with the TRANSX code. The materials in these sets are H-1, H-2, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-12, N-14, O-16, F-19, Na-23, Mg, Al-27, Si, P-31, S, K, Ca, Ti, V-51, Cr, Mn-55, Fe, Co, Ni, Cu, Zr, Nb-93, Mo, Cd, W, Pb, Bi-209, Cl, Ta-181, Sn and Ga. It should be noted that the self-shielding effect is not corrected in these libraries. KERMA, DPA and gas production libraries are also prepared from the MATXS files with TRANSX. Several test calculations are carried out in order to validate these nuclear group constant sets. They suggest that these group constant sets have no problem.
Okumura, Keisuke; Kojima, Kensuke; Tanaka, Kenichi*
JAEA-Conf 2015-003, p.43 - 47, 2016/03
In the safety assessment concerning disposal of radioactive wastes generated in the decommissioning of nuclear facilities, it is necessary to evaluate the radionuclide inventory produced by the activation of structured materials. For this purpose, we have to pay much attention to the activation of many impurities irradiated in various neutron spectra depending on their positions and materials. Therefore, accurate activation cross-section data are necessary for many nuclides and reactions. A new multi-group neutron activation cross-section library (MAXS) was developed based on the recent nuclear data JENDL-4.0 and JEFF-3.0/A to apply it to the activation calculations for the decommissioning of nuclear facilities. The library contains cross-sections and isomeric ratios for many reactions such as (n,), (n,f), (n,2n), (n,3n), (n,p), (n,), (n,d), (n,t), (n,n), (n,np), and so on, for 779 nuclides, in the 199-energy group structure of VITAMIN-B6.
Am using JENDL-4.0Mizuyama, Kazuhito; Iwamoto, Nobuyuki; Iwamoto, Osamu
JAEA-Conf 2015-003, p.245 - 250, 2016/03
The management of the nuclear waste problem requires the high precision of the neutron capture cross section for minor actinides. One of the important reaction is the neutron capture reaction of Am. However, the thermal neutron capture cross section of Am is not optimized yet. Especially the values of thermal cross sections measured by the activation technique are around 20% bigger than the other methods (TOF, & spectroscopy etc.). In the activation method, the Westcott conventional representation and the Cd-ratio method are used for the analysis of the cross section. However, it may not work well due the special resonance structure of Am. In our study, we verify the Cd-ratio method using the JENDL-4.0, and try to correct the experimental cross section based on our verification of the Cd-ratio method. Consequently we obtained the very close value of the cross section to the JENDL-4.0.
Am neutron-induced capture cross section measurement with a large coverage HPGe detector at ANNRI/J-PARCLeong, L.; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Harada, Hideo
JAEA-Conf 2015-003, P. 235, 2016/03
Rashid, M. M.*; Shigyo, Nobuhiro*; Ishibashi, Kenji*; Iwamoto, Nobuyuki; Iwamoto, Osamu
JAEA-Conf 2015-003, p.319 - 324, 2016/03
Neutron nuclear data of krypton isotopes have been evaluated in the incident neutron energy range from 1 keV to 20 MeV by using theoretical nuclear reaction model code CCONE. The phenomenological optical model potential was employed to calculate total reaction cross section for natural krypton. This calculation is based on the coupled channel method. However, optical potential parameters were obtained by best fitting the calculation result with experimental total cross section of natural krypton. The transmission coefficients were calculated which was used for getting the cross sections in outgoing reaction channels. Compound, pre-equilibrium, and direct reaction processes were taken into consideration for cross section calculation. The present calculation results were compared with the experimental data and major evaluated nuclear data libraries. It is observed that the present evaluation can explain the experimental data reasonably well.
Murata, Toru; Iwamoto, Nobuyuki; Kosako, Kazuaki*
JAEA-Conf 2015-003, p.237 - 242, 2016/03
Development of non-destructive assay technique of nuclear materials is required for the nuclear safeguard and nuclear security, especially for high level radioactive wastes such as vitrified solids. For these objects, irradiation of high transparent rays and detection of fission responses with high discrimination are required and will be attained with high energy photon irradiation and delayed neutron detections. To study the feasibility of the methods and to design the apparatus, the delayed neutron data will be requested. Their evaluation was performed approximately by utilizing neutron induced fission delayed neutron data of JENDL-4.0 for the same compound nucleus as the photo-fission. If the same compound nucleus data were not available, group delayed neutron intensities (say six or so groups) were calculated with the method given by Brady and England with the cumulative fission yields systematics given by Wahl. The present results will be given at the symposium.
