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Odano, Naoteru; Ishida, Toshihisa
JAERI-Research 2001-004, 36 Pages, 2001/03
JAERI-Research-2001-004.pdf:1.51MB
no abstracts in English
ray detector system for radioactivity measurement in deep seaYamamoto, Tadatoshi; Shimizu, Toku; Kozawa, Teruo; Birumachi, Atsushi; ; Katagiri, Masaki
JAERI-Research 99-032, 59 Pages, 1999/04
JAERI-Research-99-032.pdf:6.47MB
no abstracts in English
PNC TN9410 98-059, 53 Pages, 1998/06
The analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor ・gas turbine system; had been developed in PNC to get the best values of system parameters on fast reactor ・gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. In this report, we performed a parameter survey analysis by using the code to study characteristics of the systems. Concerning the deep sea fast reactor ・gas turbine system, calculations with many variable parameters were performed on the base case of a NaK cooled reactor of 40kWe. We aimed at total equipment weight and surface area necessary to remove heat from the system as important values of the characteristics of the system Electric generation power and the material of a pressure hull were specially influential for the weight. The electric generation power, reactor outlet/inlet temperatures, a natural convection heat transfer coefficient of sea water were specially influential for the area. Concerning the space reactor ・gas turbine system, the calculations with the variable parameters of compressor inlet temperature, reactor outlet/inlet temperatures and turbine inlet pressure were perfomed on the base case of a Na cooled reactor of 40kWe. The first and the second variable parameters were influential for the total equipment weight of the important characteristic of the system. Concening the terrestrial fast reactor ・gas tubine system, the calculations with the variable parameters of heat transferred pipe number in a heat exchanger to produce hot water of 100 
C for cogeneration, compressor stage number and the kind of primary coolant material were performed on the base case of a Pb cooled reactor of 100MWt. In the comparison of calculational results for Pb and Na of primary coolant material, The primary coolant weight flow rate was naturally large for the fomer case compared with for the latter case because density is very different between them. ...
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PNC TN9420 97-006, 70 Pages, 1997/09
Many new types of fast reactors have been studied in PNC. A deep sea fast reactor has the highest realization probability of the reactors studied because its development is desired by many specialists of oceanography, meteorology, deep sea bottom oil field, seismology and so on and because the development does not cost big budget and few technical problems remain to be solved. This report explains the outline and the usage of the reactor of 40 kWe and 200 to 400 kWe. The reactor can be used as a power source at an unmanned base for long term climate prediction and the earth science and an oil production base in a deep sea region. On the other hand, it is used for heat and electric power supply to a lavoratory in the polar region. In future, it will be used in the space. At the present time, a large FBR development plan does not proceed successfully and a realization goal time of FBR has gone later and later. We think that it is the most important to develop the reactor as fast as possible and to plant a fast reactor technique in our present society.
Fumizawa, Motoo; Inaba, Yoshitomo; Hishida, Makoto; Ogawa, Masuro; *
JAERI-Tech 96-022, 82 Pages, 1996/06
no abstracts in English
PNC TN9410 96-070, 52 Pages, 1996/05
Core characteristics calculations were performed on a trasportable deep sea reactor to confirm subcriticality at the state of thermalized neutron flux during a core flooded accident by sea water. The accident conditions were as follows. (1)A sea water leakage accident through a pressure hull occurred at deep sea. (2)The reactor was shut down by insertion of safety and control rods. (3)The primary loop boundary was damaged for some cause and the sea water entered into the core. Two types of fuel core were studied. One is an oxide fuel core using 50% Pu and 50% U of 20% enrichment. The other is a nitride fuel core using U of 97% enrichment like SP-100. The effect of wire spacer was also analysed. The computer program of MCNP was used for the analysis. Calculation results show that the subcriticality is kept by inserting a Re liner into a fuel pin even for the case with the wire spacer, where much volume of sea water exists in the core. The Re has good absorption effect for thermal neutrons. Thickness of the liner was estimated to be 0.15 ㎜ for the oxide fuel and 0.27 ㎜ for the nitride one.
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.
PNC TN9000 94-006, 60 Pages, 1994/07
Main features were studied about an objective deep sea reactor, which will be used as an electric power source at an unmanned deep sea base. The main features determined are as follows. [Thermal power 190 kWt, Fuel Mixed nitride, Cladding material Hasteloy N, Structual material Type 316 Stainless Steel, Coolant NaK, Core height and diameter about 25cm both, Reactor vessel outlet/inlet temperature 605/ 505C, Operation term 10 years.] Some topic subjects of a talk during deep sea reactor research were studied like follows. Availability of electric transmission from the land or a ship is as follows. (1)The electric transmission from the land is limited up to 1,000m in the depth of water and 100km in the distance from the land. (2)The electric transmission from a ship is available only in the days when the sea is calm. Therefore these transmission methods can not be used as the power source for the base. Concerning reliability, reliability analysis were performed about the part of Closed Brayton Cycle Systems of the reactor. Success probability calculated on the part was 0.999942 in the case of continuous four years operation at 20 kWe. Concerning safety, radioactivity contained in the reactor was calculated. The radioactivity was about 1/50,000 of the radioactivity thrown away in the north Atlantic Ocean from 1962 to 1982. Concerning the experience of developping a NaK cooling reactor in U.S., no anormaly was reported to be found in fuel pins and a reactor vessel after about 400 days operation under a reactor outlet temperature condition over about 527C in the test of a ground test reactor FS-3 for SNAP-10A about thirty years ago.
Iida, Hiromasa; Ishizaka, Yuichi*; Y-C.Kim*; *
Nuclear Technology, 107, p.38 - 48, 1994/07
Times Cited Count：10 Percentile：66.21(Nuclear Science & Technology)no abstracts in English
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PNC TN9410 94-093, 52 Pages, 1994/05
Sodium-water reaction under the high pressure condition of several hundred times of atmospheric pressure was analysed based on the occurence assumption of a hypothetical sea water leakage accident through a pressure hull with the rupture of a bellows type accumulator concerning a deep sea reactor. The sodium-water reaction analysis code of SWACS/REG4 was used in the analysis. The basic calculation case of the analysis adopted the water leakage rate of 0.128 kg/s by considering the accumulator rupture time of 1 s and the water leakage rate used in the heat transfer pipe rupture accident analyses of FBR heat exchangers which had been performed by the code. The calculational result clarified no existence of pressure wave in the upper plenum of a reactor vessel, which was due to the attenuation of the wave in the long slender pipe of 1.5 m in length and 2 cm in inner diameter between the accumulater rupture point and the reactor vesssel. In the analysis, survey calculations were also performed by changing the parameter values of the pressure, the water leakage rate and the gas space volume remaining in the pressure hull.
; Haga, Kazuo
PNC TN9410 92-095, 84 Pages, 1992/03
[Objective] The objective of this report was image construction of a fast reactor for a manned deep sea base expected in a next century. The fast reactor will be used as power and heat sources. [Method] Based on ocean data clarified up to now, the following fast reactor system conception was studied with reference to a closed Brayton cycle system for a very small reactor. Power source (about 400 kWe) (1)Sodium cooled fast reactor system (2)Lithium cooled fast reactor system Heat source (2,235 KWt) (3)Sodium cooled fast reactor system [Result] The system image of a reactor and primary/secondary loops set in a pressure hull using two or three spheres was constructed for each system. It was cocluded that the technical feasibility of the fast reactor system was high for the base.
; Haga, Kazuo
PNC TN9410 92-050, 71 Pages, 1992/02
Objective : A conceptual design of a fast reactor system was studied for deep sea research submersibles diving to the maximum depthes of 10,924m and 8,000m. Method : A space reactor concept was used for the system. Primary coolant of the system was NaK, whose temperatures was set as 680 and 550 C at the exit of a reactor vessel. Secondary system was a closed brayton xcycle using He(60)-Xe(40) gas as working fluid. Electric power output was 20kWe. Thermal efficiency, transported thermal energy, and flow rates and temperatures of the gas and NaK were calculated at closed Brayton cycle analyses. Results : The conceptual design was drawn, based on the size of an each component fixed with the calculated results of these values. The system could be set in a pressure hull comprising of a 2.3m
shere and a 1.1m pipe. A simple figure was drawn of the research submersible loading the system. The whole length of the submersible was about 14m. Its weights were about 100ton and 70ton for the maximum depthes of 10,924m and 8,000m respectively. It could be carried by a nother ship. Conclusion : The submersible had the following features compared with the one loading electric cells on account of affluent electric power generation by the fast reactor system. A continuous stay longer than a week and movement at a high speed were made possible over a deep sea bottom. An illuminated region was very wide during sea bottom survey. Observation by watching was possible over a wide region. Therefore the submersible could be considered to be used for detail observation over crackes in the Japan trench and etc.
; Haga, Kazuo
PNC TN9410 91-305, 20 Pages, 1991/09
Additional calculation was performed concerning "Study of Weight of Fast Reactor Power System for Deep Sea Research" (PNC ZN9410 91-176) published in 1991. In the above report, weight was calculated of power systems of 10kWe for an unmanned base located at the depth of water of 8,020m and of 20kWe for a research submersible diving to that of 10km. The power systems consisted of fast reactor systems and pressure hulls. The main points of the additional calculation were as follows. (1)The depth of water was not fixed, but treated as a parameter. (2)When the power systems will be used in future, some buoyancy material will be attached to the systems in order to make the weight of the systems zero in the sea water. The weight of the buoyancy material was also calculated in this report. (3)In the case of 10kWe power source, electric power was generated by eight sets of closed Brayton cycles of 1.3kWe, but two sets of 5kWe were used in this report. The additional calculation lead to the result that the total weight of the power systems at the depth of water containing the buoyancy material were 13.6t and 13.9t for 10kWe and 20kWe respectively.
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Nucl.Chem.Waste Manage., 1(2), p.129 - 138, 1980/00
no abstracts in English
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JAERI-M 8525, 64 Pages, 1979/11
no abstracts in English
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JAERI-M 7780, 41 Pages, 1978/07
no abstracts in English
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Nihon Genshiryoku Gakkai-Shi, 20(12), p.887 - 896, 1978/00
Times Cited Count：1no abstracts in English
