Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
gas turbine power generation system (User's manual); Sekiguchi, Nobutada
PNC TN9520 95-002, 66 Pages, 1995/02
This analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor gas tubine system; is used to get the adequate values of system parameters on fast reactor gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. Characteristics of the code are as follows. Objective systems of the code are a deep sea, a space and a terrestrial reactors. 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. 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. 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.
Nomura, Norio; Haga, Kazuo;
PNC TN9410 91-298, 74 Pages, 1991/08
High-temperature transpotable liquid-metal-cooled fast reactors are also expected as an energy source in sever environments such as lunar base. Only electricity has been considered as the energy supply system to the lunar base, however, both use of electricity and heat power (co-generation system) may offer better effective use of energy than only the electrification system is considered. In this report, the advantage of co-generation system based on a transpotable reactor examined to a usage in a lunar base. Two energy system diagrams on heat and electricity flows have been compared from the view point of total weight. One is the case of all electrification. The other (co-generation system) is the case in which the exhaust heat from the nuclear reactor is actively utilized to reduce the demand of electricity. A heat transport technique using a chemical process as the heat media is adapted for the latter. In the chemical system, hydrogen and carbon monoxide are formed from methane and steam by adding nuclear heat. Then the gases are transported through a pipe and changes to the original materials generating heat at the consuming spot. As the result of present study, it is clarified that the co-generation system has a possibility to have an advantage over the case of all electrification in total weight of system when the energy demand increase to MWe level. Finally, future R&D items ware mentioned to reduce the weight of this co-generation system and to increase the effectively.
