Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Odano, Naoteru; Ishida, Toshihisa; Wada, Koji*; Imai, Hiroshi*
JAERI-Research 2001-039, 59 Pages, 2001/07
A very small reactor, SCR (Submersible Compact Reactor), whose thermal output is 1250 kW, is an integral-pressurized type reactor to be used as a power source for a scientific research vessel in medium depth region of the Arctic Ocean. Neutronic study has been carried out for design of the SCR core of which could achieve continuous long-term operation without refueling for 10 years considering 50 % of load factor of the core. In the present study, arrangement of fuel rods, U enrichment of UO fuel rods and reflector materials were surveyed. The U enrichment has been determined to be 9.5 wt% to satisfy design criteria. In the present study Be metal was adopted as a reflector material. Reactor physics parameters including reactivity coefficients and power distributions were evaluated for the determined core specifications. Reactor physics parameters related to core safety were also confirmed and the evaluated parameters indicated that the determined core specifications in this study satisfied design conditions.
Odano, Naoteru; Ishida, Toshihisa
JAERI-Research 2001-004, 36 Pages, 2001/03
no abstracts in English
Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; *; *; Koizumi, Koichi; Shibanuma, Kiyoshi; Yagi, Toshiaki; Morita, Yosuke; ; et al.
JAERI-Tech 99-003, 312 Pages, 1999/02
[This article is unavailable to download the full text due to various reasons.]
; 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.