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Journal Articles

Study of an HTGR and renewable energy hybrid system for grid stability

Sato, Hiroyuki; Yan, X.

Nuclear Engineering and Design, 343, p.178 - 186, 2019/03

 Times Cited Count:1 Percentile:34.57(Nuclear Science & Technology)

A hybrid system combining HTGR and renewable energy is investigated to compensate intermittent renewable energy power generation. A new proposal of using the inventory and bypass control devices already built in the gas turbine, is found to be effective to compensate hourly to daily variation of renewable energy. The reactor thermal power remains at constant full power while the heat output is increased or decreased subject to the need of reactor power generation. On the other hand, the massive heat capacity in the graphite core is shown to be sufficient to compensate renewable energy on a time scale of seconds to minutes and up to about 20% of the rated power output of the nuclear plant. Similarly, no additional control devices are required to perform this control operation. These findings demonstrate the technical and economic potential of the HTGR system to maintain the stability of a grid being incorporated with significant portfolios of renewable energy power generation.

Journal Articles

HTGR and renewable energy hybrid system for grid stability; Assessment of performance, economics and CO$$_{2}$$ reduction

Yan, X.; Sato, Hiroyuki

IAEA-TECDOC-1885, p.121 - 129, 2019/00

The present study proposes a HTGR renewable hybrid cogeneration plant which can contribute to a grid stability for large penetration of variable renewables. In addition, results of control simulations for representative load-following operations, economics assessment and CO$$_{2}$$ reduction assessment are provided.

Journal Articles

Safety and economics of uranium utilization for nuclear power generation

Fukaya, Yuji

Uranium; Safety, Resources, Separation and Thermodynamic Calculation, p.22 - 48, 2018/05

Safety and economics of uranium utilization for nuclear power generation were investigated and discussed. In order to sustain energy supply with nuclear power generation, uranium resources should be abundant. From the viewpoint of depletion of the resources, FBR, which is breeder reactor of plutonium, has been developed, but that has been not diffused as a commercial reactor yet. Instead of obtaining inexhaustible resources by breeding plutonium, it is known that the inherent safety feature becomes weak in the fast neutron spectrum. As the result of the investigation, it is confirmed with concrete FBR designs that the inherent safety feature and breeding ability are related to the transactions. The amount of uranium resources and electricity generation cost with the resources were investigated. It is concluded that the semi-permanently sustainable energy supply can be established with reasonable cost by using seawater uranium. In addition, the significance of P&T, which is one of the advantages of FBR, was also discussed from the viewpoint of environmental burden from radioactive waste.

Journal Articles

Proposals of new basic concepts on safety and radioactive waste and of new high temperature gas-cooled reactor based on these basic concepts

Ogawa, Masuro

Nuclear Engineering and Design, 308, p.133 - 141, 2016/11

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

A new basic concept on safety; Not causing any serious catastrophe by any means and a new basic concept on radioactive waste; Not returning any waste that possibly affects the environment are proposed in the present study, aiming at nuclear power plants which everybody can accept, in consideration of the serious catastrophe that happened at Fukushima in 2011. In the present study, physical phenomena are used to continue confining, rather than confine. To continue confining is meant to apply natural correction to fulfill inherent safety function. Fission products must be detoxified to realize the new basic concept on radioactive waste, aiming at the final processing and disposal of radioactive wastes as same as that in the other wastes such as PCB. The New HTGR is proposed based on the new basic concepts. It is indicated that the New HTGR can response to social requirements for safety and environmental conservability against radioactive wastes, industrial requirements for economy, uranium resource sustainability and so on, and national requirements for non-proliferation and environmental protection against carbon dioxide.

Journal Articles

Utilization of radiation facilities in Takasaki Advanced Radiation Research Institute under the MEXT grants

Hirota, Koichi

Hoshasen To Sangyo, (139), p.33 - 36, 2015/12

The article describes utilization programs for irradiation facilities for ion beam, $$gamma$$-ray and electron beam in Takasaki Advanced Radiation Research Institute under the MEXT (Ministry of Education, Sports, Culture, Science and Technology) grants. The feature of the facilities and technical support of assistants in the fields of creation of genetic resources, analytical technology, and material development under the grants are introduced. The article also includes recent research activities of development of new flowers, visualization of Li in lithium-ion battery, and development of distortion resistance of fluoro-rubber etc.

Journal Articles

Application of RI and radiation for industry low energy electron accelerator

Kume, Tamikazu

Genshiryoku eye, 48(6), P. 20, 2002/06

no abstracts in English

Journal Articles

Recovery system for uranium from seawater with fibrous adsorbent and its preliminary cost estimation

Sugo, Takanobu; Tamada, Masao; Seguchi, Tadao; Shimizu, Takao*; Uotani, Masaki*; Kashima, Ryoichi*

Nippon Genshiryoku Gakkai-Shi, 43(10), p.1010 - 1016, 2001/10

 Times Cited Count:12 Percentile:31.31(Nuclear Science & Technology)

The cost of uranium recovered from seawater was estimated by using the amidoxime adsorbent of polymer fibers synthesized by radiation modification, and the technical problems in the recovery system were extracted. The cost of adsorbent materials, storage in seawater for uranium absorption, and the uranium detachment from the adsorbent was estimated respectively in three different systems of the storage in seawater as a buoy, floating body, and chain binding system. The recovery cost of uranium from seawater was estimated to be 8$$sim$$10 times of that from mine uranium. More than 80% of the total cost was occupied by the cost for storage in seawater, which is owing to a weight of metal cage for the holding of adsorbents. The cost can be attained to half by the reduction of the weight to 1/4. One of facing research subject is the improvement of adsorbent ability, since the cost directly depends on the adsorbent performance.

Journal Articles

Toward very long-term utilization of nuclear energy; Prospects and problems of water-cooled breeder "reduced moderation water reactor"

Sato, Osamu; Tatematsu, Kenji; Tanaka, Yoji*

Genshiryoku eye, 47(7), p.60 - 64, 2001/07

no abstracts in English

JAEA Reports

A Study on modeling and numerical simulation of extraction in the CMPO-TBP system

; ;

JNC-TN8400 2001-022, 60 Pages, 2001/03

JNC-TN8400-2001-022.pdf:1.31MB

A numerical simulation code for the TRUEX (Transuranium Extraction) process was developed. Concentration profiles of americium and europium were calculated for some experiments of the counter current extraction system those were carried out in CPF (Chemical Processing Facility) by using the code. Calculation profiles were in agreement with the experimental results. Operational conditions were also examinted for the americium recovery experiment by the TRUEX process carried out in the Plutonium Fuel Center. It was shown that lowering the concentration of nitric acid in the scrub solution and decreasing the flow rate of solvent and strip solution was effective for improving the performance of the stripping step and reducing the volume of the waste solution. In order to find the optimum conditions for various experiments, this simulation code was modified to calculate the concentration profiles of other metal elements such as zirconium and iron and the effect of oxalic acid on the extraction behavior of the metal elements. The calculated concentration profiles of americium and europium were varied by this modification. In the experiment at CPF, the calculations were carried out to obtain recovery ratio of americium in the product stream with the amount of oxalic acid added to the process. This calculation result showed that it was possible to improve the performance of decontamination of fission products by increasing oxalic acid concentration added to the process. The calculation was also carried out for finding the optimum conditions of oxalic acid concentration added to the europium recovery process.

Journal Articles

CPU load prediction on heterogeneous distributed computing environments using dataFOREST data-mining tool

Moda, Yukimitsu*; Hayashi, Takuya*; Koide, Hiroshi; Kashima, Toru*; Tsutsui, Hiroaki*; Kasahara, Hironori*

Joho Shori Gakkai Dai-62-Kai (Heisei-13-Nen Zenki) Zenkoku Taikai Koen Rombunshu, p.1_131 - 1_132, 2001/03

no abstracts in English

Journal Articles

Evaluation of the resource information prediction in the resource information server

Koide, Hiroshi; Yamagishi, Nobuhiro*; Takemiya, Hiroshi*; Kasahara, Hironori*

Joho Shori Gakkai Rombunshi, 42(3), p.65 - 73, 2001/03

no abstracts in English

JAEA Reports

None

Funasaka, Hideyuki; ;

JNC-TN1200 2001-002, 209 Pages, 2001/01

JNC-TN1200-2001-002.pdf:7.84MB

no abstracts in English

JAEA Reports

None

Sasao, Eiji; Okubo, Seisuke*

JNC-TN7450 2000-019, 42 Pages, 2000/11

JNC-TN7450-2000-019.pdf:1.16MB

no abstracts in English

JAEA Reports

Investigation of corrosion, water reaction, polonium evaporation and bismuth resource in liquid metal lead-bismuth technology

Takano, Hideki; Takizuka, Takakazu; Kitano, Teruaki*

JAERI-Review 2000-014, 134 Pages, 2000/10

JAERI-Review-2000-014.pdf:13.43MB

no abstracts in English

JAEA Reports

None

*

JNC-TN1440 2000-005, 214 Pages, 2000/08

JNC-TN1440-2000-005.pdf:13.81MB

no abstracts in English

Journal Articles

Implementation of resource information server for meta scheduling

Koide, Hiroshi; Yamagishi, Nobuhiro*; Takemiya, Hiroshi*; Hayashi, Takuya*; Kasahara, Hironori*

Keisan Kogaku Koenkai Rombunshu, p.357 - 360, 2000/05

no abstracts in English

JAEA Reports

The second maintenance report at plutonium conversion development facility

; ; *; *; *; *; *

JNC-TN8440 2000-013, 179 Pages, 2000/04

JNC-TN8440-2000-013.pdf:10.31MB

The plutonium conversion development facility (PCDF) has been operated for 17 years and about 12 tons plutonium-uranium mixed oxide (MOX) powder has been converted since operation started in 1983. The first maintenance program for aging of apparatus was carried out from 1993 to 1994. The calcination-reduction fumace, liquid waste evaporator had been dismantled and renewed. The second maintenance program was carried out form 1998 to 1999. The microwave ovens, powder blender, ventilation control panel and so on were dismantled and renewed. Large volume radioactive wastes were generated during this maintenance such as the furnace, the filter casings and glove boxes. These wastes were too large to be packed into the waste container and these wastes were polluted by MOX powder unfixed on these surface. SO cutting and packing operation for these wastes and recovery of MOX powder from them were carried out. In this report, the method of this cutting and packing operation, the radioactive exposure to the operators in this operation, the estimation of nuclear material quantity migrated to filters, the evaluation of re-floating factor of radioactive material, etc. were discussed.

JAEA Reports

Study on reducing the generation of general waste

Aoki, Isao; ; ; ; ; ;

JNC-TN8420 2000-005, 42 Pages, 2000/04

JNC-TN8420-2000-005.pdf:2.09MB

On August 1999, the Director of Tokai Work proposed an activity regarding recycling and reuse of general waste generated from Tokai Works. The activity was initiated by the Waste Management and Fuel Cycle Research Center, and is now being in progress through out the Tokai Works. In the course of this activity, Plutonium Fuel Center had settled the Working Group and the issues related to the waste reduction have been examined. This report collects the problems that became obvious through the survey of existing segregation method, treatment process, and the amount of the waste generation, and accounts for the concrete methodology for the recycling and reuse of general waste. In order to reduce waste, it is necessary to aware of the facing issues and adopt the countermeasures proposed in this report whenever possible. The activity will then leads us to reduce waste generation, which in turn will enable us to make 100 % waste recycling possible.

JAEA Reports

None

; ; *

JNC-TY7430 2000-001, 57 Pages, 2000/03

JNC-TY7430-2000-001.pdf:2.17MB

no abstracts in English

JAEA Reports

MA transmutation in various fast reactor core concepts

; Iwai, Takehiko*; Jin, Tomoyuki*

JNC-TN9400 2000-080, 532 Pages, 2000/03

JNC-TN9400-2000-080.pdf:14.98MB

Transmutation Property of minor actinide nuclides (MA) was analyzed for fast reactor cores having different coolant and fuel types in order to obtain basic data for evaluating an ability of the efficient use of resource and reducing the effect on the environment. The investigated fast reactor cores were (a) sodium cooled and oxide fueled core, (b) lead cooled and nitride fueled core (BREST-300), (c) carbon dioxide gas cooled and oxide fueled core (ETGBR), (d)lead cooled and oxide fueled core, (e) sodium cooled and nitride fueled core (both He-bond and sodium-bond), and (f) sodium cooled and metallic fueled core. Followings were observed for the relation between MA transmutation property and the different types of coolant and fuel of fast reactor core. (1) For the MA transmutation rate, the relation "Oxide $$<$$ Metal $$<$$ Nitride" was found out for difference of fuel type. A main reason of the increment of MA transmutation rate is that the neutron flux level rises on nitride and metallic fueled cores in comparison with oxide core. (2) The relation "Lead $$<$$ Sodium and Carbon dioxide" can be seen for the MA transmutation rate in the difference of coolant, but it is not clear whether the cause is driven from the difference of coolant itself on the difference of core design. (3) The changes of MA transmutation property mentioned above are comparatively small.

113 (Records 1-20 displayed on this page)