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

https://doi.org/10.1016/j.nucengdes.2019.01.010

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.

Safety and economics of uranium utilization for nuclear power generation

Fukaya, Yuji

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

https://doi.org/10.5772/intechopen.72647

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.

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

http://ci.nii.ac.jp/naid/40020674698

The article describes utilization programs for irradiation facilities for ion beam, -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.

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

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*

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

https://doi.org/10.3327/jaesj.43.1010

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 810 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.

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.

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

http://ci.nii.ac.jp/naid/110002725709

no abstracts in English

None

Sasao, Eiji; Okubo, Seisuke*

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

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

no abstracts in English

None

*

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

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

no abstracts in English

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.