Chiba, Go; Ishikawa, Makoto
AIP Conference Proceedings 769, 468- Pages, 2005/08
The ERRORJ code is the only one which can process the covariance data of the Reich-Moore resolved resonance parameters and the unresolved resonance parameters in the world. Now, the new version, version 2.2, has been developed and is released with much more reliability. In the present paper, details of the upgrade and a result of a validation test with the SAMMY code are described. Covariance data contained in ENDF/B, JEF(F) and JENDL are processed. Large differences are observed in the covariance between these nuclear data files.
AIP Conference Proceedings 769, p.1405 - 1410, 2005/06
Some improvements of the nuclear data application to the fast reactor core field have been accomplished in Japan. The present paper introduces the recent status from three categories, group constant and analytical tools, database of fast reactor experiments, and application to FBR design study. A policy of JNC is to open the products generated from the application study to the world, as much as possible to keep the traceability, reproducibility and accountability.
AIP Conference Proceedings 769, P. 472, 2005/06
This paper presents a validation work on MA nuclear data by PIE analyses in the framework of fast reactor cycle system development. The PIE analyses are in progress on MA samples (237Np, 241Am, 243Am, 244Cm) irradiated at the experimental fast reactor JOYO. The preliminary analysis results showed the isomeric ratio for 241Am capture reaction lies around 0.85 (g/(g+m)) in the fast neutron spectra, which suggested the necessity of re-evaluation of the data both in ENDF/B-VI and in JENDL-3.3. From the results on curium isotopes, overestimations could be pointed out for capture cross-section of 244Cm in ENDF/B-VI and that of 245Cm in JENDL-3.3.
Goto, Jun; Sugawara, Masahiko*; Oshima, Masumi; Toh, Yosuke; Kimura, Atsushi; Osa, Akihiko; Koizumi, Mitsuo; Mizumoto, Motoharu; Osaki, Toshiro*; Igashira, Masayuki*; et al.
AIP Conference Proceedings 769, p.788 - 791, 2005/05
no abstracts in English
Kimura, Atsushi; Toh, Yosuke; Koizumi, Mitsuo; Osa, Akihiko; Oshima, Masumi; Goto, Jun; Igashira, Masayuki*
AIP Conference Proceedings 769, p.792 - 795, 2005/05
The aim of our study is the acquisition of neutron cross-section data for the minor actinides (such as Np, Am and Am). We develop a new advanced measurement technology for the acquirement of neutron cross-section data of the minor actinides. In this technology, we construct a 4 Ge-spectrometer which consists of 30 Ge crystals and BGO anti-Compton shields. Normally, a data acquisition system for such a big Ge spectrometer consists of many NIM modules; it requires large space; in addition, its cost of this system becomes huge. To overcome these problem, we developed a new data acquisition system for the 4 Ge-spectrometer with digital signal processing (DSP) techniques. This system consists of three Main ADC modules, which measure the energy of gamma rays with DSP technique, five Fast Timing modules and a Coincidence module to detect a coincidence condition and to measure timing data. All modules can be mounted a 19 inches VME sub-rack, the cost of this system is less than 2000 dollars per one Ge detector channel.
Satoh, Daiki; Sato, Tatsuhiko; Endo, Akira; Yamaguchi, Yasuhiro; Takada, Masashi*; Ishibashi, Kenji*
AIP Conference Proceedings 769, p.1680 - 1683, 2005/05
Response function of liquid organic scintillators is essential to derive the accurate neutron spectrum. Experimental data above 100 MeV, however, are very scarce. The existing Monte Carlo codes, SCINFUL and CECIL, are often used for estimation of the response function instead of the experimental data. These codes are known to reproduce well the response function for incidences below 100 MeV. Unfortunately, the codes are not applicable to the calculation in the higher energy region. In order to determine the response functions above 100 MeV, a new Monte Carlo code, designated as SCINFUL-QMD, has been developed. In the comparison with the experimental data up to 800 MeV, the validation of SCINFUL-QMD was confirmed. The results of SCINFUL-QMD agreed with the experimental data better than those of other calculation codes.
AIP Conference Proceedings 769, p.47 - 52, 2005/05
In recent years, intermediate energy nuclear data are required for various applications such as accelerator-driven systems for waste transmutation, spallation neutron sources, advanced cancer therapies, estimation of single event up set rate and dose on astronauts. For these requirements, many groups in the world continue intermediate energy nuclear data evaluation. The early stage of this evaluation was initiated in USA. For example, Pearlstein at Brookhaven National Laboratory produced systematics, modified ALICE code and evaluated proton and neutron nuclear data in late 1980s. At Lawrence Livermore National Laboratory, similar data developed for a medical application. Following them, many countries, such as Europe, Japan, Russia, China, Korea, started the preparation of nuclear data in this energy region. Overview of evaluation methods, results of evaluations are presented in comparison between experimental data and evaluated files, mainly JENDL High Energy File, as well as results from benchmark calculations.
Kishida, Norio*; Murata, Toru*; Asami, Tetsuo*; Kosako, Kazuaki*; Maki, Koichi*; Harada, Hideo*; Lee, Y.*; Chang, J.*; Chiba, Satoshi; Fukahori, Tokio
AIP Conference Proceedings 769, p.199 - 202, 2005/05
Nuclear data for photonuclear reactions are required in the field of shielding design of high-energy electron accelerators and high-energy -ray therapy. The JENDL Photonuclear Data File was prepared by a working group on nuclear data evaluations for photonuclear reactions in Japanese Nuclear Data Committee. From a survey of many literatures, it is difficult to construct the photonuclear data file by using only measured data, since there are not sufficient experimental data. We were therefore evaluating with theoretical calculations based on statistical nuclear reaction models. The photonuclear cross sections that are to be contained in the file are as follows: photoabsorption cross sections, yield cross sections and DDX for neutrons, protons, deuterons, tritons, He-particles and alpha-particles, and isotope production cross sections. For the actinide nuclides, photofission cross sections are also included. The maximum energy of incident photons is 140 MeV and stored are the photonuclear data for 68 nuclides from H to Np.
Iwamoto, Osamu; Herman, M.*; Mughabghab, S. F.*; Oblozinsk, P.*; Trkov, A.*
AIP Conference Proceedings 769, p.434 - 437, 2005/05
Entirely new evaluations for all the Ge isotopes, from thermal energy to 20 MeV, has been performed with focus on photon production. In the resonance region, parameters were improved considerably compared to earlier evaluations. In the fast region, code EMPIRE-2.19 was used. Validation was done against photon data on Fe and Nb. Isotopic evaluations for Ge were summed up and compared with available measurements on natural Ge. Various quantities related to photon production, showing strong dependence on neutron incident energy, are discussed.
Shibata, Keiichi; Nakagawa, Tsuneo; Fukahori, Tokio; Ichihara, Akira; Iwamoto, Osamu; Otsuka, Naohiko*; Katakura, Junichi
AIP Conference Proceedings 769, p.171 - 176, 2005/05
The presentation deals with the activities on JENDL. JENDL-4 is being developed as a general purpose library. This library will include charged-particle and photon induced reaction data as well as spontaneous fission data for a limited number of nuclei in addition to neutron induced reaction data. The maximum incident energy can be extended to higher values than 20 MeV depending on data needs. Key subjects are improvements of accuracy of minor actinide and FP data, evaluations of covariances and so on. Quality assurance is regarded as important for JENDL-4. As special purpose files, we released the JENDL High Energy File and Photonuclear Data File this year. For the development of ADS, the Actinide File is being made. Furthermore,covariance data for some nuclei are also evaluated for ADS. Nuclear model codes are developed in order to reflect recent advances in nuclear theory on data evalulations. For users' covenience, we are working on the development of the Combined System for Nuclear Data Utilization, Circulaiton and Transfer.
Meigo, Shinichiro; Shigyo, Nobuhiro*; Iga, Kiminori*; Iwamoto, Yosuke*; Kitsuki, Hirohiko*; Ishibashi, Kenji*; Maehata, Keisuke*; Arima, Hidehiko*; Nakamoto, Tatsushi*; Numajiri, Masaharu*
AIP Conference Proceedings 769, p.1513 - 1516, 2005/05
For validation of calculation codes that are employed in the design of accelerator facilities, spectra of neutrons produced from a thick iron target bombarded with 1.5-GeV protons were measured. The calculated results with NMTC/JAM were compared with the present experimental results. It is found the NMTC/JAM generally shows in good agreement with experiment. Furthermore, the calculation gives good agreement with the experiment for the energy region 20 to 80 MeV, whereas the NMTC/JAM gives 50 % of the experimental data for the heavy nuclide target such as lead and tungsten target.
Otsuka, Naohiko; Aikawa, Masayuki*; Suda, Takuma*; Naito, Kenichi*; Korennov, S.*; Arai, Koji*; Noto, Hiroshi*; Onishi, Akira*; Kato, Kiyoshi*; Nakagawa, Tsuneo; et al.
AIP Conference Proceedings 769, p.561 - 564, 2005/05
A web-based search and plot system for nuclear reaction data has been developed, covering experimental data in EXFOR format and evaluated data in ENDF format. The system is implemented for Linux OS, with Perl and MySQL used for CGI scripts and the database manager, respectively. Two prototypes for experimental and evaluated data are presented.
Oblozinsk, P.*; Herman, M.*; Mughabghab, S. F.*; Sirakov, I.*; Chang, J.*; Nakagawa, Tsuneo; Shibata, Keiichi; Kawai, Masayoshi*; Ignatyuk, A. V.*; Pronyaev, V. G.*; et al.
AIP Conference Proceedings 769, p.438 - 441, 2005/05
Review of neutron cross-section evaluations for fission products included in 5 major evaluated nuclear-data libralies was performed. The aim of the project, conducted under the WPEC Subgroup 21 during 2001-2004, was to prepare recommendations for best evaluations of nuclei in the range Z=1-68. Altogether, existing evaluations for 211 materials were reviewd, 7 new materials were added, and recommendations were prepared for 218 materials.
Watanabe, Yukinobu*; Fukahori, Tokio; Kosako, Kazuaki*; Shigyo, Nobuhiro*; Murata, Toru*; Yamano, Naoki*; Hino, Tetsushi*; Maki, Koichi*; Nakashima, Hiroshi; Odano, Naoteru*; et al.
AIP Conference Proceedings 769, p.326 - 331, 2005/05
An overview is presented of recent nuclear data evaluations performed for the JENDL high-energy (JENDL-HE) file, in which neutron and proton cross sections for energies up to 3 GeV are included for the whole 132 nuclides. The current version of the JENDL-HE file consists of neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double-differential cross sections of secondary light particles ( He, , and ) and -rays, isotope production cross sections, and fission cross sections in the ENDF6 format. The present evaluations are performed on the basis of experimental data and theoretical model calculations. For the cross section calculations, we have constructed a hybrid calculation code system with some available nuclear model codes and systematics-based codes, such as ECIS96, OPTMAN, GNASH, JQMD, JAM, TOTELA, FISCAL, and so on. The evaluated cross sections are compared with available experimental data and the other evaluations. Future plans of our JENDL-HE project are discussed along with prospective needs of high-energy cross section data.
Cano-Ott, D.*; Abbondanno, U.*; Aerts, G.*; lvarez, H.*; lvarez-Velarde, F.*; Andriamonje, S.*; Andrzejewski, J.*; Assimakopoulos, P.*; Audouin, L.*; Badurek, G.*; et al.
AIP Conference Proceedings 769, p.1442 - 1445, 2005/05
Accurate and reliable neutron cross section data for actinides are necessary for the proper design, safety reguartion and precise performance assessment of transmutaion devices. In particular, the neutron capture cross sections of Np, Pu and Am play a key role in the design and optimization of a strategy for the Nuclear Waste Transmutation. The listed cross sections have been measured in 2004 at n_TOF with a high accuracy due to a combination of features unique in the world.
Furman, W.*; Cennini, P.*; Ketlerov, V.*; Goverdovski, A.*; Konovalov, V.*; Abbondanno, U.*; Aerts, G.*; lvarez, H.*; Alvarez-Velarde, F.*; Andriamonje, S.*; et al.
AIP Conference Proceedings 769, p.1039 - 1042, 2005/05
A series of measurements of Np fission cross section have been performed at the CERN spallation neutron source facility n_TOF. A fast ionization chamber was used as a fission fragment detector. Total experimental uncertainties are determined to be at the level of 3%. Analysis of experimental data in the neutron energy from 5 eV to 1 MeV showed a systematic deviation from the evaluated data (ENDF/B-VI). This discrepancy amounts to up to the factor of 3 for resolved resonances in the neutron energy range of 5 eV - 2 keV, and is in good agreement with some previous experiments. A similar disagreement at the level of 6-7% was found for higher energies around the threshold. This energy range is essential for the transmutation of neptunium in ADS or fast reactors. It is concluded that an updated evaluation of nuclear data for Np is required.
Sakane, Hitoshi; Furutaka, Kazuyoshi; Shcherbakov, O.; Harada, Hideo; Fujii, Toshiyuki*; Yamana, Hajimu*
AIP Conference Proceedings 769, p.1000 - 1002, 2004/09
Thermal neutron capture cross sections of N-14 and Al-27 were measured by unfolding prompt -ray spectra in order to confirm the effectiveness of these methods. By comparing the present results with other results, the effectiveness of the present methods was confirmed.
Shcherbakov, O.; Harada, Hideo; Furutaka, Kazuyoshi; Nakamura, Shoji; Sakane, Hitoshi; Kobayashi, Katsuhei*; Yamamoto, Shuji*
AIP Conference Proceedings 769, p.1007 - 1010, 2004/00
The neutron capture cross section of Np-237 has been measured relative to the B-10(n,alpha)Li-7 cross section in the energy range from 0.02 to 100 eV. The measurements were carried out by the time-of-flight method using the 8.54 liters BGO scintillator as a 4-pi capture ray detector and the 46 MeV Linac as a pulsed neutron source. The results of present measurements have been compared with experimental data of other authors and evaluated data.
Furutaka, Kazuyoshi; Harada, Hideo; Raman, S.*
AIP Conference Proceedings 769, p.1454 - 1457, 2004/00
Analyses were made of the prompt rays emitted in the thermal neutron capture reaction by Tc to determine the reaction cross section. From the obtained data, a partial decay scheme was constructed which consists of 88 rays and 36 bound states. Six rays were assigned as the transitions to the ground state of Tc. From the intensities of these six rays, a lower limit of the reaction cross section was obtained to be 21.370.68b. Through a least-squres fit to the level energies, the neutron separation energy of Tc was determined as 6765.200.04 keV. rays in Ru emitted following the beta- decay of the reaction product Tc were also analyzed. The inferred cross section is 22.81.8b.