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Journal Articles

Neutron capture cross sections of light neutron-rich nuclei relevant for $$r$$-process nucleosynthesis

Bhattacharyya, 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

AA2021-0553.pdf:7.41MB

 Times Cited Count:7 Percentile:64.51(Physics, Nuclear)

no abstracts in English

Journal Articles

Ground-state configuration of neutron-rich $$^{35}$$Al via Coulomb breakup

Chakraborty, 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:33.04(Physics, Nuclear)

no abstracts in English

Journal Articles

EBR-II passive safety demonstration tests benchmark analyses; Phase 2

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.

Journal Articles

Development of neutron-monitor detectors applicable to energies from thermal to 100MeV

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

Journal Articles

Study of the IDGS Technique for Mixed Plutonium-Uranium Oxide (MOX) Samples

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.

Journal Articles

Hybrid neutron detector consisting of an organic liquid scintillator and a $$^{6}$$Li glass scintillator for wide energy range

Kim, 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

JAEA Reports

Development of detector for neutron monitor of wide energy range (Joint research)

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

Oral presentation

Recommendations for measurement systems for nuclear material accountancy of Fukushima Daiichi fuel debris; $$gamma$$ technologies

Tomikawa, 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 $$gamma$$ measurement technologies are $$gamma$$ Gross Counting, $$gamma$$ Dosimetry, $$gamma$$-ray Spectroscopy, $$gamma$$-ray Densitometry, $$gamma$$-ray Imaging, Transmission (X-ray) Radiography, Prompt Fission $$gamma$$-ray Counting and Spectroscopy, and Neutron Induced $$gamma$$-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 $$gamma$$ 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 $$gamma$$ measurement technologies for nuclear material accountancy of fuel debris at 1F.

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