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JENDL-4.0: A New Library for Innovative Nuclear Energy Systems
N. Otuka 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The fourth version of Japanese Evaluated Nuclear Data Library (JENDL-4.0) has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the improvements of fission product and minor actinide data. Achieving this, nuclear model codes were developed. Coupled-channel optical model parameters, which can be applied to a wide mass range, were obtained for evaluations. Thermal cross sections of many actinides were revised on the basis of experimental data or systematics. Simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. The new library JENDL-4.0 is made available on the Web site of the JAEA Nuclear Data Center.
Database for Time-of-flight Spectra Including Covariances
N. Otuka,A. Borella,S. Kopecky,C. Lampoudis,P. Schillebeeckx 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
A data format for time-of-flight spectra (transmission, reaction andself-indication yields) and their covariance matrices based on the AGS(Analysis of Geel Spectra) format is discussed in collaboration betweenEC-JRC IRMM and IAEA-NDS for the EXFOR library. Experimentalists areencouraged to consider the uncertainty propagation following the AGSprinciple and submission of their data to the International Networks NuclearReaction Data Centres (NRDC) for EXFOR compilation using a proposedtemplate.
The Role of the Nuclear Reaction Data Centres in Experimental Nuclear Data Knowledge Sharing
N. Otuka,S. Dunaeva,E. Dupont,O. Schwerer,A. Blokhin 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The International Network of Nuclear Reaction Data Centres (NRDC) consists of 14 data centres from 10 countries and 2 international organisations, and is collaborating for compilation, exchange and dissemination of various types of nuclear reaction data information. The nuclear data centres common data collection, the EXFOR database today contains experimental information and numerical data from more than 18,000 experiments consisting of more than 134,000 data sets mainly of nuclear reaction data for incident neutrons, charged-particles and photons with incident energy lower than 1 GeV. A brief history and the current status of NRDC collaboration are presented for EXFOR as well as CINDA and ENDF.
Development of Granulated Powders by SUS316L Ultra Fine Powder
Kadomura Takeshi,Maeta Yu,Otuka Isamu 한국분말야금학회 2006 한국분말야금학회 학술대회논문집 Vol.2006 No.1
Granulated powders, prepared from PF-5F(D50=4μm), PF-10F(D50=6μm) and PF-20F(D50=10μm) water atomized powder, were compacted, debound and sintered to evaluate the properties of sintered parts. As a result, the relative sintered density of about 97% at sintering temperature of 1423K was obtained. It can be considered that by using granulated finer particle size powder, mechanical properties of sintered parts were also improved.
Exploratory Data Analysis of the EXFOR Database
Emmeric Dupont,Arjan J. Koning,Naohiko Otuka 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The EXFOR database is a large collection of experimental nuclear reaction data for incident neutrons, charged particles and photons. The EXchange FORmat was designed to be very flexible in order to be able to store the data as published. However, this flexibility is a drawback for systematic comparison of EXFOR data with evaluated data or nuclear reaction code results. The WPEC Subgroup 30 on ``Improvement of Accessibility and Quality of the EXFOR Database'' was founded with the aims to establish EXFOR as a more easily accessible and reliable database. In this framework, a directory-structured database was created in simple tabular format. The content of this database was verified with various statistical tests and compared with default results from the TALYS code. This work allowed various problems to be identified, either in the EXFOR translating codes or in the EXFOR database, and sometimes in the original publications.
Covariance Evaluation for Actinide Nuclear Data in JENDL-4
O. Iwamoto,T. Nakagawa,S. Chiba,N. Otuka 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Covariances of actinide nuclear data stored in JENDL-4.0 have been evaluated based on available experimental data and reaction model calculation. The covariance matrix was basically deduced applying the consistent method with the nuclear data evaluation. For the fast neutron fission cross sections of 6 major actinides of ^(233,235,238)U and ^(239, 240, 241)Pu were evaluated simultaneously with experimental data of both cross sections and their ratios using the least-squares code SOK, resulting in giving the covariance matrices that has correlations between the data of different nuclei. For the minor actinide, the least-squares fitting code GMA was used for fission cross section evaluation. The covariances were obtained from the same calculation. For other reaction cross sections, covariances were evaluated using KALMAN code with the sensitivities calculated by CCONE code. Covariances for other data such as resonance parameters and average numbers of fission neutrons were also evaluated. The evaluated covariance data have been complied to the ENDF-6 format files. The JENDL-4.0 library contains covariance data of (1) average number of neutrons per fission (MF = 31), (2) resonance parameters (MF = 32), (3) cross sections (MF = 33), (4) angular distributions of elastic scattering (MF = 34), and (5) prompt fission spectra (MF = 35) for all 79 actinides.