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JAEA Reports

Stationary analysis program code STEDFAST for space, terrestrial and deep sea fast reactor $$cdot$$ gas turbine power generation system (User's manual)

; Sekiguchi, Nobutada

PNC TN9520 95-002, 66 Pages, 1995/02

PNC-TN9520-95-002.pdf:2.55MB

This analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor $$cdot$$ gas tubine system; is used to get the adequate values of system parameters on fast reactor $$cdot$$ gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. Characteristics of the code are as follows. $$cdot$$ Objective systems of the code are a deep sea, a space and a terrestrial reactors. $$cdot$$ Primary coolants of the systems are NaK, Na, Pb and Li. Secondary coolant is the mixture gas of He and Xe. The ratio of He and Xe is arbitrary. $$cdot$$ Modeling of components in the systems was performed so that detailed modeling might be capable in future and that a transient analytical code could be easily made by using the code. $$cdot$$ A progra㎜ing language is MAC-FORTRAN. The code can be easily used in a personal computer. The code made possible instant calculation of various state values in a Brayton cycle, understanding the effects of many parameters on thermal efficiency and finding the most adequate values of the parameters. From now on, detailed modeling of the components will be performed. After that, the transient program code will be made.

JAEA Reports

Gas turbine power generation system using a fast reactor

; Haga, Kazuo; Sekiguchi, Nobutada

PNC TN9410 92-252, 62 Pages, 1992/05

PNC-TN9410-92-252.pdf:1.1MB

[Objective] Study on the concept of a fast reactor gas turbine cogeneration system used near a small town, where there are not a large number of engineers, in a cold district distant from a large city. [Method] The population of the small town is supposed 200 to 2000 thousands. The study was performed on three kinds of plant systems, that is, 100, 50 and 10 MWe's. The design of a high temperature fast reactor previously studied for hydrogen production was used for a primary system. A closed Brayton cycle (CBC) was adopted for the secondary system to generate electric power. These plant systems have not the accident occurence possibility of sodium-water reaction since a steam turbine is not used for electric power generation. Water treatment is not necessary, too. In order that the gas turbine system has high thermal efficiency, the reactor vessel coolant outlet temperature is desirable to be high. Therefore the temperature was set to be 650 to 700$$^{circ}$$C which is considered the highest temperature attained by steel and nickel alloy structural material. The temperature is higher than that of usual FBR's by 100 to 150$$^{circ}$$C. Exhausted heat from the closed Brayton cycle is used for cogenration like district heating. [Result] The following plant systems were found to be possible from the conceptual design study on the above three kinds of power scale plants. [100 and 50MWe systems] Both systems adopted two loops for primary system. The former adopted four loops design and the latter two loops design for the secondary system, respectively. The reactor coolant temperature was 700$$^{circ}$$C at the reactor outlets for both systems. An non-intercooling type compressor was used in the secondary system. The thermal efficiency of the CBC was about 24%. The scales of the building containing the secondary system were 31m in width, 40m in depth and 30m in height for the former and 31m in width, 22m in depth and 30m in height for the latter. [10MWe system] A ...

JAEA Reports

Conceptual design study of high temperature fast reactor

; Haga, Kazuo; Sekiguchi, Nobutada

PNC TN9410 91-126, 118 Pages, 1991/03

PNC-TN9410-91-126.pdf:2.08MB

A conceptual design study has been performed in order to establish an outline image of the High Temperature Fast Reactor (HTFR) which has been aimed to produce the hydrogen as a most promising energy source in 21st century. The study covers the following systems. (1)Reactor system (2)Cooling system (3)Safety system and containment From results of the study, the concepts of the compactized reactor system and the heat exchanging system has been presented. Based on the concept obtained, a preliminary estimate of the cost of hydrogen produced by the HTFR was also conducted in another report. Result revealed that the cost is compatible with that by the High Temperature Gas-cooled Reactor (HTG CR) already published.

Journal Articles

None

Sekiguchi, Nobutada; Nishino, Osamu*; Wakayama, Naoaki*; Iwasaki, Toshio*; Araki, Hitoshi*; Miyazawa, Tatsuo*

Nihon Genshiryoku Gakkai-Shi, 22(9), p.604 - 615, 1980/00

Journal Articles

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Otsubo, A.; Haga, Kazuo; Sekiguchi, Nobutada

Donen Giho, , 

None

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