Re-evaluation of electricity generation cost of HTGR

Fukaya, Yuji; Ohashi, Hirofumi; Sato, Hiroyuki; Goto, Minoru; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi (Internet), 21(2), p.116 - 126, 2022/06

https://doi.org/10.3327/taesj.J21.005

An improvement electricity generation cost evaluation method for High Temperature Gas-cooled Reactors (HTGRs) has been performed. Japan Atomic Energy Agency (JAEA) had completed the commercial HTGR concept named Gas Turbine High Temperature Reactor (GTHTR300) and the electricity generation cost evaluation method approximately a decade ago. The cost evaluation was developed based on the method of Federation of Electric Power Companies (FEPC). The FEPC method was drastically revised after the Fukushima Daiichi nuclear disaster. Moreover, the escalation of material and labor cost for the decade should be consider to evaluate the latest cost. Therefore, we revised the cost evaluation method for GTHTR300 and the cost was compared with that of Light Water Reactor (LWR). As a result, it was found that the electricity generation cost of HTGR of 7.9 yen/kWh is cheaper than that of LWR of 11.7 yen/kWh by approximately 30% at the capacity factor of 70%.

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.

Studies on sodium cooled fast breeder reactor

Nibe, Nobuaki; Shimakawa, Yoshio; ; Hayafune, Hiroki; ; ;

JNC TN9400 2000-074, 388 Pages, 2000/06

JNC-TN9400-2000-074.pdf:13.32MB

Large sized sodium-cooled fast breeder reactors of large-size are being studied and have been operated in Japan and many countries. ln this feasibility study, evaluation was made on technical feasibinty for design concepts or 1 loop type and 3 pool types, specially from the viewpoint of improvement of economical competence. The design concepts include the ideas of cost reduction measures such as large-scaled components, reduction of loop number and integration of components on the basic of utilization of sodium characteristics. From the results of the evaluation, it may be possible for all the concepts to attain the economical target of 200 thousands yen per kilowatt, though further confirmation should be made for technical feasibility of those concepts. ln addition, the following items were listed up as further cost-reduction measures. (1)Higher temperature cooling system and steam cycle efficiency (2)Shortening of construction term (3)Reduction of safety systems by using measuring instruments with high performmce (4)Adoption of SG-ACS

Evaluation of cost reduction method for manufacturing ODS Ferritic claddings

Fujiwara, Masayuki; Mizuta, Shunji;

JNC TN9400 2000-050, 19 Pages, 2000/04

JNC-TN9400-2000-050.pdf:0.82MB

For evaluating the fast reactor system technology, it is important to evaluate the practical feasibility of ODS ferritic cdaddings, which is the most promising matelials to attain the goal of high coolant temperature and more than 150 GWd/t. Based on the results of their technology development, mass production process with highly economically benefit as well as manufacturing cost estimation of ODS ferritic claddings were preliminarily conducted. From the view point of future utility scale, the cost for manufacturig mother tubes has a dominant factor in the total manufacturing cost. The method to reduce the cost of mother tube manufacturing was also preliminarily investigated.

The economics of various fuel cycle systems

Kofuji, Hirohide;

PNC TN9410 98-066, 67 Pages, 1998/06

PNC-TN9410-98-066.pdf:2.05MB

The economics of various fuel cycle based on the current domestic situation were evaluated to confirm the adequacy of the economical target of the FBR fuel cycle. Four types of fuel cycle concepts, LWR-once through, LWR-reprocessing, LWR-Pu and FBR, were selected. The unit costs of the fuel cycle components were based on the domestic business base price or estimated values from published construction costs. These setting of the unit costs were the key point of this report. As the results, generating electricity cost of the LWR-reprocessing scenario which was thought to be the domestic reference scenario was estimated to be 8.2 yen/kWh, that of once through scenario was 7.5 yen/kWh, and LWR-Pu scenario was 8.2 yen/kWh. These differences of the generating electricity costs due to the deference of the fuel cycle costs because those three scenario were based on the same reactor concept. The generating electricity cost of the once through scenario is smaller than that of the reprocessing scenario equivalent for the reprocessing cost because that front end costs of the both scenario were equal and spent fuel or waste disposal cost occupied merely small parts of the fuel cycle costs. In the PWR-Pu scenario, natural uranium and enrichment cost were cut down but the fuel cycle cost was the same as the reprocessing scenario due to the relatively high cost of MOX fabrication. On the other hand, though the gcnerating electricity cost of the FBR scenario based on the current technology is 13.3 yen/kWh which is about 1.6 times of that of the LWR reprocessing scenario, its future cost was estimated to be 6.7 yen/kWh which is lower than every LWR scenario results of the future R&D. These economical evaluation showed the adequacy of the economical target of the FBR cycle, it is necessary to improve the evaluation accompanying with the trend of the LWR cycle and the progress of the R&D of the FBR cycle.

None

; *; Fukazawa, E.*; Yamamoto, H.*; Taira, K.*; Tanaka, Toshiyuki*; Suyama, Yasuhiro*; Kondo, Y.*; *; *; et al.

PNC TJ1100 97-002, 85 Pages, 1997/03

PNC-TJ1100-97-002.pdf:5.08MB

None

None

Kajima Corporation*

PNC TJ1100 96-006, 62 Pages, 1996/03

PNC-TJ1100-96-006.pdf:1.91MB

None

A Study of direct disposal technology in the world (2)

*; Okubo, Hiroo*

PNC TJ9222 95-002, 111 Pages, 1995/03

PNC-TJ9222-95-002.pdf:3.33MB

There are two methods of handling the spent fuel generated from the light water reactor; they are (l)direct disposal and (2)reprocessing-plutonium recycling. At present, Japan is following the line of "Reprocessing-Plutonium Recycling," but in the rest of the world, the movement for reviewing the Plutonium recycling is spreading, and in the future, the world opinion and pressure from overseas countries will increase against this method. Under these circumstances, Japan must compare the two methods to clarify the meaning of plutonium recycling. In this investigation, an overseas document by which the spent fuel had directly examined disposal was investigated. And, the content of those documents was arranged. The case of which directly disposed in Japan was set and the basic specification and the cost were evaluated. As a result of the investigation, the disposal cost became 54,900,000 yen/tU in the case with our country. This evaluation value is about 25% higher than Sweden and Finland where the cost is the highest in an overseas case. In cost items, the ratio which the article expense occupies is high. Moreover, the cost of construction and the close of underground facilities occupies the entire half for our country. This investigation is an evaluation based on in the case of the evaluation the current. Therefore, I want you to note going as for a technical detailed examination. However, the guess of the cost when directly disposing in Japan pounded. Moreover, the nuclear material control of the spent fuel is not evaluated. I want you to note cannot the comparison for that with the disposal of the glass solidification body.

None

Endo, Hideo; ; ; ; ; Nagai, Shuichiro

PNC TN8410 93-065, 192 Pages, 1993/04

PNC-TN8410-93-065.pdf:4.77MB

None

None

*

PNC TJ6557 91-045, 121 Pages, 1990/12

PNC-TJ6557-91-045.pdf:2.63MB

None

Study on the main design parameters of large scale fast breeder reactor (II); Investigation on reduction of piping length by application of IHX floating support piping to primary main heat transport system piping of LMFBR.

*; *; Nakanishi, Seiji; *

PNC TN9410 88-103, 115 Pages, 1988/08

PNC-TN9410-88-103.pdf:14.73MB

Current emphasis in the development of liquid-metal cooled fast breeder reactors (LMFBRs) is placed on the reduction of the plant construction cost without spoiling the safety in view of its practical application. So much effort is paid for the cost reduction. The reduction of piping length of heat transport system piping is considered as an effective measure for the cost reduction. An application of component floating support piping which brings good results in LWR leads to reduction of piping length and it is an effective measure as well as bellows expansion joint piping and high-chrome-steel piping in LMFBR. A design study for the application of the IHX floating support piping system to primary main heat transport system piping of LMFBR was conducted to demonstrate the adequacy of the piping system by using the improved structural design method considering the characteristics of LMFBR. The stress analysis of piping due to dead weight, thermal expansion at steady and transient conditions, and earthquake was performed, while the nozzles stress due to internal pressure, dead weight, earthquake and thermal expansion reaction force, and thermal transients was analyzed. It was confirmed that the analytical results were satisfied the allowable values and the piping support equipments were highly put into practical use. Therefore it was concluded that the adequacy of the IHX floating support piping system was demonstrated.