Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Yamauchi, Michinori; Iida, Hiromasa; Nishitani, Takeo; Konno, Chikara
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.995 - 998, 2008/05
no abstracts in English
Iwamoto, Yosuke; Niita, Koji*; Sakamoto, Yukio; Sato, Tatsuhiko; Matsuda, Norihiro
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.945 - 948, 2008/05
The "Event Generator Mode" has been introduced into the PHITS code in the treatment of lower energy particles. In this mode, nuclear data for neutrons and a special evaporation model are combined so as to trace all higher correlations keeping the energy and the momentum conservation in a collision. This mode enables us to calculate the above-mentioned correlated quantities without any assumptions such as the pulse height tally adopted in the MCNP code, and also to estimate the Kerma factor and the DPA data without additional evaluated cross section libraries. In this work, we have calculated particle production cross sections, Kerma and DPA by using our developed event generator mode, and compared them with the evaluated nuclear data for the validation of the mode in neutron-induced reactions under 30 MeV. As an application of this mode, we will suggest a new approach to Kerma factor library weighted by quality factors for radiation protection against low energy neutron exposure.
Murata, Isao*; Takagi, Satoshi*; Shiken, Kimiaki*; Kondo, Keitaro; Miyamaru, Hiroyuki*; Ochiai, Kentaro; Nishitani, Takeo; Konno, Chikara
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.999 - 1002, 2008/05
The (n,2n) reaction plays a very important role in the design of fusion reactor. In the present study, using a pencil-beam DT neutron source, angle-correlated two neutrons emitted through (n,2n) reaction have directly been measured to determine (n,2n) reaction cross section with the coincidence detection technique for beryllium which is the most important element in the fusion reactor. In the experiment, two NE213 detectors were arranged very close to the sample to efficiently measure the two neutrons. The measured spectra were unfolded by FORIST with the detector response matrix evaluated by SCINFUL. As a relust, comparing with the evaluations of ENDF/B-VI and JENDL-3.3 for energies above 800 keV of the lower measurable limit energy, the shape of derived angula-differential cross-section fits JENDL-3.3 better than ENDF/B-VI. However, agreement of the cross section of (n,2n) above 800 keV was acceptable within 10 percents for both libraries.
Shibata, Keiichi; Nakagawa, Tsuneo; Fukahori, Tokio; Iwamoto, Osamu; Ichihara, Akira; Iwamoto, Nobuyuki; Kunieda, Satoshi; Otsuka, Naohiko; Katakura, Junichi; Watanabe, Yukinobu*; et al.
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.727 - 732, 2008/05
General- and special-purpose JENDL data files are being produced in cooperation with the Japanese Nuclear Data Committee. We have developed nuclear model codes to improve the quality of MA and FP data. In the FP region, we obtained global coupled-channel optical model parameters, which can be applied to neutron- and proton-induced reaction data up to 200 MeV. These parameters are used for statistical model calculation. Resolved resonance parameters of MA and FP nuclei were updated to improve the low-energy behavior of the cross sections by using recent measurements. As a follow-up of JENDL-3.3, which was released in 2002, covarainces of several nuclei were estimated for a study on ADS. Concerning special-purpose files, the compilation of the 2007 versions of JENDL High Energy File and Photonulcear Data Files is in the final stage.
Yokoyama, Kenji; Jin, Tomoyuki*
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.807 - 810, 2008/05
Post irradiation experiment (PIE) data on depleted fuel composition of the experimental fast reactor "JOYO" MK-II has been accumulated since 1986 in JNC (the former of JAEA). In the present study, all the available PIE data of JOYO MK-II driver fuel were analyzed and integral data concerning U depletion and U generation were prepared. Both the integral data are sensitive to U capture cross section and applicable to nuclear data benchmarks. The recent evaluated nuclear data libraries, JENDL-3.2, -3.3, JEFF-3.1 and ENDF/B-VII, have a tendency to overestimate the generation of U. A cross section adjustment demonstrated that re-evaluation of U capture cross section improved the overestimation.
Ishikawa, Makoto; Hazama, Taira
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.817 - 820, 2008/05
Three series of BFS critical experiments which loaded approximately 10 kg of Np -dioxide were analyzed to verify the performance of major libraries with Np nuclear data. The latest JENDL-3.3, ENDF/B-VII.0 and JEFF-3.1 showed satisfactory results from the Np data viewpoint; however some other major data such as Pu nu and fission, U and/or the sodium inelastic scattering cross-sections of some libraries may need re-evaluation. Further, the effect of integral experimental information to obtain better predictions of reactor core parameters was demonstrated by the cross-section adjustment method.
Koning, A.*; Katakura, Junichi; Oblozinsk, P.*; Nichols, A. L.*; Nordborg, C.*
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.741 - 746, 2008/05
The Working party on international nuclear data Evaluation Cooperation (WPEC) is a collaborative effort between the major OECD nuclear data project: ENDF/B (USA), JENDL (Japan) and JEFF (Europe), and the IAEA-supported non-OECD project CENDL (China) and BROND (Russia). Nuclear data challenges and problems that are common to all projects are considered in various WPEC subgroups that are normally pf limited time span. The achievements of these subgroups are reviewed in this paper. Among the recent accomplishments are improved criticality predictions through revised U evaluations, the completion of new cross-section standards, and the creation of a new Fission Product library. Problems that are currently being addressed are the processing and inclusion of covariance data in the libraries, improvements in decay data to assist in decay heat calculations, assembly of a well-structured High Priority Request List, validation of the new fission product cross-section library, and the assessment of nuclear data needs for GEN-IV.
Yamano, Naoki*; Katakura, Junichi; Kato, Kiyoshi*; Igashira, Masayuki*
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.825 - 828, 2008/05
A nuclear data processing and utilization system has been developed as a modular code system of the integrated nuclear data utilization system for innovative nuclear energy system. The system is able to handle evaluated nuclear data in ENDF-6 format to generate point-wise and group-wise cross sections in several formats, and has a capability to perform criticality and shielding benchmarks. An overview of the integrated nuclear data utilization system and the scheme of cross-section generation and benchmark procedure in the system have been described as well as future development plan based on the system.
Fischer, U.*; Batistoni, P.*; Forrest, R. A.*; Konno, Chikara; Perel, R. L.*; Seidel, K.*; Simakov, S. P.*
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.973 - 978, 2008/05
An overview is presented of the nuclear data required for nuclear design analyses of fusion technology focusing on ITER, the International Thermonuclear Experimental Reactor, and IFMIF, the International Fusion Materials Irradiation Facility. The status of the available data evaluations and libraries is reviewed with regard to the required materials/nuclides and data types and, in particular, with regard to their quality as compared to differential and integral experimental data. Future development needs are identified on this basis addressing nuclear data evaluations for neutron and photon transport simulations, cross-section data for activation and transmutation calculations, and co-variance data for uncertainty analyses.