JOPSS - Search Results

Journal Articles

Demonstration of -ray pipe-monitoring capabilities for real-time process monitoring safeguards applications in reprocessing facilities

Rodriguez, D.; Tanigawa, Masafumi; Nishimura, Kazuaki; Mukai, Yasunobu; Nakamura, Hironobu; Kurita, Tsutomu; Takamine, Jun; Suzuki, Satoshi*; Sekine, Megumi; Rossi, F.; et al.

Journal of Nuclear Science and Technology, 55(7), p.792 - 804, 2018/07

https://doi.org/10.1080/00223131.2018.1439412

Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

Nuclear material in reprocessing facilities is safeguarded by random sample verification with additional continuous monitoring applied to solution masses and volume in important tanks to maintain continuity-of-knowledge of process operation. Measuring the unique rays of each solution as the material flows through pipes connecting all tanks and process apparatuses could potentially improve process monitoring by verifying the compositions in real time. We tested this ray pipe-monitoring method using plutonium-nitrate solution transferred between tanks at the PCDF-TRP. The rays were measured using a lanthanum-bromide detector with a list-mode data acquisition system to obtain both time and energy of -ray. The analysis and results of this measurement demonstrate an ability to determine isotopic composition, process timing, flow rate, and volume of solution flowing through pipes, introducing a viable capability for process monitoring safeguards verification.

Journal Articles

Completion of solidification and stabilization for Pu nitrate solution to reduce potential risks at Tokai Reprocessing Plant

Mukai, Yasunobu; Nakamichi, Hideo; Kobayashi, Daisuke; Nishimura, Kazuaki; Fujisaku, Sakae; Tanaka, Hideki; Isomae, Hidemi; Nakamura, Hironobu; Kurita, Tsutomu; Iida, Masayoshi*; et al.

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04

TRP has stored the plutonium in solution state for long-term since the last PCDF operation in 2007 was finished. After the great east Japan earthquake in 2011, JAEA had investigated the risk against potential hazard of these solutions which might lead to make hydrogen explosion and/or boiling of the solution accidents with the release of radioactive materials to the public when blackout. To reduce the risk for storing Pu solution (about 640 kg Pu), JAEA planned to perform the process operation for the solidification and stabilization of the solution by converted into MOX powder at PCDF in 2013. In order to perform PCDF operation without adaption of new safety regulation, JAEA conducted several safety measures such as emergency safety countermeasures, necessary security and safeguards (3S) measures with understanding of NRA. As a result, the PCDF operation had stared on 28th April, 2014, and successfully completed to convert MOX powder on 3rd August, 2016 for about 2 years as planned.

JAEA Reports

Conceptual design of backend technology R & D facility for TRU recycle in the future cycle system

Fujine, Sachio; Usuda, Shigekazu; Morita, Yasuji; Yoshida, Zenko; ; Furuta, Teruo; Tone, Tatsuzo; *; Nishimura, Kenji*; *

JAERI-M 93-211, 87 Pages, 1993/11

JAERI-M-93-211.pdf:2.42MB

no abstracts in English

Journal Articles

Reactor neutron capture cross section of 60.3-day $^{1}$ $^{2}$ $^{4}$ Sb

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Journal of Nuclear Science and Technology, 16(8), p.546 - 552, 1979/00

https://doi.org/10.3327/jnst.16.546

Times Cited Count：2

no abstracts in English

Journal Articles

Manpower requirements and development for the new 33-GW nuclear generation plan of Japan

Manpower Requirements and Development for Nuclear Power Programes, p.165 - 177, 1979/00

no abstracts in English

Journal Articles

JAERI Nuclear Engineering School and technology transfer

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Journal of Nuclear Science and Technology, 15(10), p.780 - 785, 1978/10

https://doi.org/10.3327/jnst.15.780

Times Cited Count：0

no abstracts in English

JAEA Reports

Evalution of Neutron Cross Sections for $^{19}$ F in the Energy Range From 100 KeV to 20 MeV

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JAERI-M 7253, 51 Pages, 1977/09

JAERI-M-7253.pdf:1.7MB

no abstracts in English

JAEA Reports

Total Neutron Cross Sections of Lanthanum and Praseodymium in the Energy Range from 20 to 240 keV

; ; ; Nakagawa, Tsuneo

JAERI-M 6883, 31 Pages, 1977/01

JAERI-M-6883.pdf:0.68MB

Total neutron cross sections for La and Pr in the energy range from 20 to 240 keV were measured by using monochromatic neutrons, which were produced by the $^{7}$ Li(p,n) $^{7}$ Be reaction. Theenergy spreads of incident neu- trons were about 18 keV for La and about 8 keV for Pr. The measured total neutron cross sections, with statistical error of 2 - 5% for La and 2 - 3% for Pr, were compared with other available data. The average total neutron cross-section data for both nuclides were interpreted in terms of a spherical optical-model potential. S-wave strength functions S $_{0}$ for La and Pr were deduced from the optical-model parameters obtained by fitting to the average total neutron cross-section data; i.e. S $_{0}$ = 0.46 $_{-0.03}^{+0.08}$ 10 $^{-4}$ for La and S $_{0}$ = 1.0 $_{-0.08}^{+0.15}$ 10 $^{-4}$ for Pr. The result of total neutron cross sections for La in the energy range from 70 to 140 keV with the energy spreads of about 2.8 keV is also presented.