TY - GEN
T1 - Development of nuclear data processing and utilization system for innovative reactors
AU - Yamano, N.
AU - Hasegawa, A.
AU - Kato, K.
AU - Igashira, M.
PY - 2005/5/24
Y1 - 2005/5/24
N2 - A research and development (R&D) project on a nuclear data processing and utilization system was started in 2002 for a five-year plan for innovative nuclear energy systems such as innovative reactors and accelerator-driven systems. The nuclear data processing and utilization system is being developed to use on a PC-Linux server through the Internet, so that it has a graphic user interface (GUI) in order to easily utilize the system for various nuclear design studies in the innovative reactor development. The nuclear data processing and utilization system, which is able to handle JENDL-3.3, ENDF/B-VI, and JEFF-3 to generate point-wise and group-wise cross sections in several formats, has the capability to perform criticality and shielding benchmarks. A prototype system was developed in order to examine the operability of the user interface and discuss detailed specifications of the system. The system is expected to be a verification tool of nuclear data for development of innovative nuclear reactors, because cross-section generation with nuclear data and the various benchmarks for criticality and shielding problems can be easily performed.
AB - A research and development (R&D) project on a nuclear data processing and utilization system was started in 2002 for a five-year plan for innovative nuclear energy systems such as innovative reactors and accelerator-driven systems. The nuclear data processing and utilization system is being developed to use on a PC-Linux server through the Internet, so that it has a graphic user interface (GUI) in order to easily utilize the system for various nuclear design studies in the innovative reactor development. The nuclear data processing and utilization system, which is able to handle JENDL-3.3, ENDF/B-VI, and JEFF-3 to generate point-wise and group-wise cross sections in several formats, has the capability to perform criticality and shielding benchmarks. A prototype system was developed in order to examine the operability of the user interface and discuss detailed specifications of the system. The system is expected to be a verification tool of nuclear data for development of innovative nuclear reactors, because cross-section generation with nuclear data and the various benchmarks for criticality and shielding problems can be easily performed.
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U2 - 10.1063/1.1944968
DO - 10.1063/1.1944968
M3 - Conference contribution
AN - SCOPUS:33749500389
SN - 073540254X
SN - 9780735402546
T3 - AIP Conference Proceedings
SP - 109
EP - 112
BT - International Conference on Nuclear Data for Science and Technology
T2 - International Conference on Nuclear Data for Science and Technology
Y2 - 26 September 2004 through 1 October 2004
ER -