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-process nucleosynthesisBhattacharyya, A.*; Datta, U.*; Rahaman, A.*; Chakraborty, S.*; Aumann, T.*; Beceiro-Novo, S.*; Boretzky, K.*; Caesar, C.*; Carlson, B. V.*; Catford, W. N.*; et al.
Physical Review C, 104(4), p.045801_1 - 045801_14, 2021/10
Times Cited Count：5 Percentile：57.13(Physics, Nuclear)no abstracts in English
Al via Coulomb breakupChakraborty, S.*; Datta, U.*; Aumann, T.*; Beceiro-Novo, S.*; Boretzky, K.*; Caesar, C.*; Carlson, B. V.*; Catford, W. N.*; Chartier, M.*; Cortina-Gil, D.*; et al.
Physical Review C, 96(3), p.034301_1 - 034301_9, 2017/09
Times Cited Count：4 Percentile：27.61(Physics, Nuclear)no abstracts in English
Briggs, L.*; Monti, S.*; Hu, W.*; Sui, D.*; Su, G. H.*; Maas, L.*; Vezzoni, B.*; Partha Sarathy, U.*; Del Nevo, A.*; Petruzzi, A.*; et al.
Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.3030 - 3043, 2015/08
The International Atomic Energy Agency Coordinated Research Project, "Benchmark Analyses of an EBR-II Shutdown Heat Removal Test" is in the third year of its four-year term. Nineteen participants representing eleven countries have simulated two of the most severe transients performed during the Shutdown Heat Removal Tests program conducted at Argonne's Experimental Breeder Reactor II. Benchmark specifications were created for these two transients, enabling project participants to develop computer models of the core and primary heat transport system, and simulate both transients. In phase 1 of the project, blind simulations were performed and then evaluated against recorded data. During phase 2, participants have refined their models to address areas where the phase 1 simulations did not predict as well as desired the experimental data. This paper describes the progress that has been made to date in phase 2 in improving on the earlier simulations and presents the direction of planned work for the remainder of the project.
Endo, Akira; Kim, E.; Yamaguchi, Yasuhiro; Sato, Tatsuhiko; Yoshizawa, Michio; Tanaka, Susumu; Nakamura, Takashi; Rasolonjatovo, A. H. D.*
Journal of Nuclear Science and Technology, 41(Suppl.4), p.510 - 513, 2004/03
no abstracts in English
Sumi, Mika; Masashige, Kobayashi,*; Onishi, Sumitaka; Suzuki, Toru; Li, T. K.*; Vo, D.*
Final Program P.657 #229, 657- Pages, 2004/00
The Isotope Dilution Gamma-ray Spectrometry (IDGS) technique has developed at LANL. Feasibility study to implement IDGS for measuring MOX samples at PFC has performed and its results will be presented.
Li glass scintillator for wide energy rangeKim, E.; Endo, Akira; Yamaguchi, Yasuhiro; Yoshizawa, Michio; Nakamura, Takashi*; Rasolonjatovo, D. R. D.*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(3), p.317 - 319, 2002/09
no abstracts in English
Kim, E.; Endo, Akira; Yamaguchi, Yasuhiro; Yoshizawa, Michio; Tanaka, Susumu; Shiomi, T.*; Nakamura, Takashi*; Rasolonjatovo, D. R. D.*
JAERI-Tech 2002-041, 73 Pages, 2002/03
JAERI-Tech-2002-041.pdf:4.47MB
no abstracts in English
technologiesTomikawa, Hirofumi; Heinberg, C.; Nauchi, Yasushi*; Vo, D.*; Carroll, C.*; Hori, Keiichiro
no journal, ,
In order to survey technologies to be developed for nuclear material quantification of fuel debris at 1F, Japan Atomic Energy Agency (JAEA) and United States Department of Energy (DOE) started collaborative research from November 2012. Under the collaborative research, three Working Groups, Neutron Working Group (NWG), Gamma Working Group (GWG) and Source Term Working Group (STWG) were established. The roles of GWG are to identify measurement systems that could be studied further for possible implementation at 1F. Candidate measurement technologies are Gross Counting, Dosimetry, -ray Spectroscopy, -ray Densitometry, -ray Imaging, Transmission (X-ray) Radiography, Prompt Fission -ray Counting and Spectroscopy, and Neutron Induced -ray Spectroscopy. Taking into account system cost, system size, measurement time, development period, and potential for applicability to fuel debris, GWG members have identified recommended combinations among the technologies supplemented with neutron measurement technologies. The evaluation was carried out by literature search and simulation works. This paper provides recommendations of the GWG for measurement systems based on mainly measurement technologies for nuclear material accountancy of fuel debris at 1F.
