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Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Hagura, Naoto*; Kubota, Toshio*
Nuclear Instruments and Methods in Physics Research B, 477, p.54 - 59, 2020/08
Times Cited Count：5 Percentile：45.45(Instruments & Instrumentation)Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Kubota, Toshio*
QST-M-23; QST Takasaki Annual Report 2018, P. 59, 2020/03
Watanabe, So; Ogi, Hiromichi*; Arai, Yoichi; Aihara, Haruka; Takahatake, Yoko; Shibata, Atsuhiro; Nomura, Kazunori; Kamiya, Yuichi*; Asanuma, Noriko*; Matsuura, Haruaki*; et al.
Progress in Nuclear Energy, 117, p.103090_1 - 103090_8, 2019/11
Times Cited Count：12 Percentile：77.44(Nuclear Science & Technology)Iwamoto, Yukiharu*; Kusuzaki, Ryo*; Sogo, Motosuke*; Yasuda, Kazunori*; Yamano, Hidemasa; Tanaka, Masaaki
Proceedings of ASME-JSME-KSME Joint Fluids Engineering Conference 2015 (AJK 2015-FED) (USB Flash Drive), p.1767 - 1773, 2015/07
Wall pressure measurements and flow visualization were conducted for a 90 degree elbow of which the axis curvature radius became the same as its inner diameter (125 mm). A deflected inflow, having an almost constant velocity slope, was introduced. Ensemble averaged pressure distributions showed no normalized pressure difference in cases of Reynolds numbers of 320,000 and 500,000. Comparisons with uniform inlet flow case proved; low-pressure region at the intrados of the elbow was weakened whereas a high pressure region outside strengthened in the deflected inflow case. Pressure distribution downstream of the elbow increased at the inside until two diameters downstream from the elbow exit. Flow visualization showed the pressure increase from collision of a strengthened secondary flow of extrados convection. The unsteady pressure distribution showed a circumferential extent of a strongly fluctuating region in and downstream the elbow decreased, comparing with the uniform inlet flow case.
Iwamoto, Yukiharu*; Kondo, Manabu*; Yasuda, Kazunori*; Sogo, Motosuke*; Tanaka, Masaaki; Yamano, Hidemasa
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 10 Pages, 2011/10
Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Yamano, Hidemasa; Kotake, Shoji
Proceedings of 6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-6) (USB Flash Drive), 6 Pages, 2008/11
Pressure measurement, laser Doppler velocimetry (LDV) and flow visualization were carried out using the 1/10-scale model of a hot leg piping installed in a Japanese sodium-cooled fast breeder reactor. LDV measurement with Reynolds number of 50000 showed the following results: (1) A flow separation was confirmed in the region between 45 degrees from the elbow inlet and 0.3 times of pipe diameter downstream of the elbow. (2) There appeared two kinds of fluctuations in the present study. In the case of Reynolds number of 320000, it was found that the height of the flow separation downstream of the elbow became smaller, since the inertia of the flow became superior to the inverse pressure gradient.
Shiotani, Hiroki; Ohtaki, Akira; Ono, Kiyoshi; Hirao, Kazunori; Kato, Atsushi; Yasumatsu, Naoto*; Kubota, Sadae*
JNC TN9400 2004-052, 514 Pages, 2004/09
JNC-TN9400-2004-052.pdf:8.85MB
This report presents the outline of the development and the results of characteristic evaluation on the candidate Fast Reactor (FR) cycle system concepts, scenario study on FR cycle deployment and cost-benefit analysis on the candidate FR cycle system concepts in the interim evaluation (FY2001 through FY2003) of the second phase of the Japanese "Feasibility Study on Commercialization of Fast Breeder Reactor Cycle System (FS)".
Ono, Kiyoshi; Kubota, Sadae*; Heta, Masanori*; Shiotani, Hiroki; Hirao, Kazunori
JNC TN9400 2003-061, 135 Pages, 2003/07
JNC-TN9400-2003-061.pdf:6.97MB
This report is intended to explain the outline of the scenario studies on FBR (Fast Breeder Reactor) cycle introduction. Recently, people value the reduction of environmental impact in addition to the recycle of energy resources and the energy security in these scenario studies. This report summarizes the analysis about the necessity of plutonium recycling in LWR (Light Water Reactor) from short-term view and about the necessity of FBR cycle introduction from a long-term view in Japan, by comparing "FBR scenario" with "LWR once-through scenario" and "Pu recycle in LWR scenario", from the viewpoints of cumulative uranium demand, spent fuel storage, radioactive waste arising, etc. It becomes clear that the plutonium recycling in LWR has a good effect on the reduction of spent fuel storage and the cumulative natural uranium demand before FBR cycle introduction, from short-term view (20 - 30 years). On the other hand, this analysis also shows that there is much effect of FBR deployment not only on saving amount of uranium use and energy security but also on reduction of high-level radioactive waste (spent fuels and vitrified waste) and minor actinide arising, from long-term view (100 - 200 years).
*; Ohtaki, Akira;
JNC TN9410 2003-002, 84 Pages, 2003/05
In the "Feasibility Study on Commercialized FBR Cycle Systems (F/S)", scenario evaluations, cost-benefit evaluations and system charactelistic evaluations to show the significance of the FBR cycle system introduction concretely are performed while design studies for FBR Plants, reprocessing systems and fabrication systems are conducted. In these evaluations, future society of various conditions and situation is assumed, and investigation and analysis about needs and social effect of FBR cycle are carried out. In this study, promising FBR cycle concepts are suggested by taking information such as domestic and foreign policies and bills, an economic prediction, a supply and demand prediction of resources, a project of technology development into consideration in addition to system design information. The development of the FBR Cycle Database which this report introduced started in 1999 fiscal year to enable managed unitarily and searched reference information to use for the above scenario evaluations, cost-benefit evaluations and system characteristic evaluations. In 2000 fiscal year, its prototype was made and used tentatively, and we extracted the problems in operation and functions from that, and, in 2001 fiscal year, the entry system and the search system using the Web page were made in order to solve problems of the prototype, and started use in our group. Moreover, in 2002 fiscal year, we expanded and improved the search system and promoted the efficiency of management work, and use in JNC through intranet of the database was started. In addition, as a result of having made the entry of about 350 data in 2002 fiscal year, the collected number of the database reaches about 7,250 by the end of March, 2003. We are to continue the entry of related information of various evaluations in F/S Phase 2 from now on. In addition, we are to examine improvement of convenience of the search system and cooperation with the economy database.
Shiotani, Hiroki; ; ; Sagayama, Yutaka; *; *
JNC TN9400 2002-044, 42 Pages, 2002/07
JNC-TN9400-2002-044.pdf:1.69MB
Some studies about the relation between burn-up and economics in the FR cycle have been performed until now. The results of these studies indicate that the core fuel assemblies with average burn-up of 150
200GWd/t is proper for target value from the economic viewpoint. The phase-I of JNC's "Feasibility Studies on Commercialized Fast Reactor Cycle System (the F/S)" started from 1999. In the F/S study, reactor construction cost, reprocessing cost and fabrication cost of FR cycle were revised iargely and importance of improvement of the average burn-up for whole fuel assemblies including blanket fuels was confirmed. Accordingly, based on the newest FR plant and core designs in the F/S study, the influence of the fuel burn-up on the generation cost was examined on the assumption that core diameter, CDF(Cumulative Damage Fraction) condition and so on are constant. The results may be summarized as follows. (1)As for the constant breeding ratio case (about l.1), the generation cost becomes the minimum at around 150GWd/t as average burn-up for core fuel assemblies (or at around 90GWd/t of average burn-up for whole fuel assemblies). It is caused by both effects of decrease of fuel mass flow, and increase of fuel cycle unit cost and decrease of load factor, as fuel burn-up rises. (2)When the breeding ratio increases (addition of axial blanket fuels), the generation cost rises because average burn-up for the whole fuel assemblies decreases.
*; Ohtaki, Akira;
JNC TN9400 2002-034, 41 Pages, 2002/06
JNC-TN9400-2002-034.pdf:1.76MB
In the "Feasibility Study on Commercialized Fast Reactor Cycle System (F/S)", scenario evaluations, cost-benefit evaluations and system characteristic evaluations to show significance of the Fast Breeder Reactor (FBR) cycle system introduction concretely are performed in parallel with a design study for FBR plants, reprocessing systems and fabrication systems. In these evaluations, informations such as economic prospects, prospects for supply and demand of resources and a progress of engineering development are used in addition to design information. This report explains a FBR Cycle Database in order to carry out management and search of various design information and the relating information. The prototype system of the database was completed in the 2000 fiscal year, and the problem of the user number restriction of the prototype system has been improved by Web-ization in the 2001 fiscal year, About 7,000 data are stored in this data base (as of the end of March, 2002). The expansion of user etc., and the continuation of input work of various evaluation information will be carried out, in the phase 2 of F/S.
; Ohtaki, Akira; ; *; *
JNC TN9400 2001-028, 51 Pages, 2000/12
JNC-TN9400-2001-028.pdf:1.96MB
This scenario study on the global nuclear energy was performed from the viewpoints of the maximum utilization of natural uranium resources, in order to clarify the role of nuclear energy in the future global primary energy supply. Social conditions, such as site issue and financial issue, aren't taken into consideration. Main three scenarios set up in this study are as follows, (1)LWR once-through (2)LWR with plutonium recycling (3)LWR+FBR From preliminary estimation, the following results were obtained. In the LWR once-through scenario and the LWR with plutonium recycling scenario, the nuclear energy can't support energy supply in the reference case B estimated by IIASA/WEC in the Global Energy Perspectives 1998. The nuclear energy decreases gradually after the middle of 21
century and exhausts uranium resource to phase out till the beginning of 22
century. On the other hand, if the FBR cycle is introduced in the future for Plutonium utilization, the nuclear energy is expected to be one of the most important sustainable energy options beyond the next century.
Ohtaki, Akira; ; ; *; *;
JNC TN9410 2000-006, 74 Pages, 2000/04
JNC-TN9410-2000-006.pdf:3.01MB
To evaluate materials balance in nuclear fuel cycle quickly and quantitatively the fuel cycle requirement code "FAMILY" was improved. And an accumulated TRU&LLFP quantity analysis code was developed. The contents are as follows: (1)A calculation ability of minor actinide production and expenditure was added to the "FAMILY" code. (2)An output program for the "FAMILY" calculation results was developed. (3)A simple version of "FAMILY" code was developed. (4)An analysis code for accumulated TRU&LLFP quantity in nuclear fuel cycle was developed.
Iwamoto, Yukiharu*; Kondo, Manabu*; Ikeuchi, Hiroki*; Yasuda, Kazunori*; Sogo, Motosuke*; Tanaka, Masaaki; Yamano, Hidemasa
no journal, ,
To clarify the effect of a straight pipe length connecting to the upstream on the elbow flow, the experiment was performed to measure the velocity distribution of the flow with a buffer tank in the upstream from the elbow. The measured data were compared with the previous data in the upstream condition with a fully developed flow.
Kondo, Manabu*; Ikeuchi, Koki*; Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Yamano, Hidemasa; Tanaka, Masaaki
no journal, ,
no abstracts in English
Ikeuchi, Koki*; Kondo, Manabu*; Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Tanaka, Masaaki; Yamano, Hidemasa
no journal, ,
no abstracts in English
Takai, Yu*; Kondo, Manabu*; Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Tanaka, Masaaki; Yamano, Hidemasa
no journal, ,
In the present study, velocity distributions were measured using LDV under 320000 of Reynolds number in an experimental facility, where a swirling flow entered a 90 degree bend.
Kondo, Manabu*; Takai, Yu*; Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Yamano, Hidemasa; Tanaka, Masaaki
no journal, ,
In the present study, velocity distributions were measured using LDV under 320000 of Reynolds number in an experimental facility, where a swirling flow entered to a 90-degree bend.
Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Tanaka, Masaaki; Yamano, Hidemasa
no journal, ,
LDV measurement has been performed on the swirling inflow with its non-dimensional angular momentum of 0.12 in an elbow whose radius of pipe-axis curvature and inside pipe diameter are the same. Flow-induced-vibration generated in the flow field and elbow has been compared with that of non-swirling inflow to show no difference in non-dimensional frequency.
Ogawa, Shota*; Iwamoto, Yukiharu*; Yasuda, Kazunori*; Sogo, Motosuke*; Yamano, Hidemasa; Tanaka, Masaaki
no journal, ,
no abstracts in English
