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Yamasaki, Chisato*; Murakami, Katsuhiko*; Fujii, Yasuyuki*; Sato, Yoshiharu*; Harada, Erimi*; Takeda, Junichi*; Taniya, Takayuki*; Sakate, Ryuichi*; Kikugawa, Shingo*; Shimada, Makoto*; et al.
Nucleic Acids Research, 36(Database), p.D793 - D799, 2008/01
Times Cited Count：52 Percentile：71.76(Biochemistry & Molecular Biology)Here we report the new features and improvements in our latest release of the H-Invitational Database, a comprehensive annotation resource for human genes and transcripts. H-InvDB, originally developed as an integrated database of the human transcriptome based on extensive annotation of large sets of fulllength cDNA (FLcDNA) clones, now provides annotation for 120 558 human mRNAs extracted from the International Nucleotide Sequence Databases (INSD), in addition to 54 978 human FLcDNAs, in the latest release H-InvDB. We mapped those human transcripts onto the human genome sequences (NCBI build 36.1) and determined 34 699 human gene clusters, which could define 34 057 protein-coding and 642 non-protein-coding loci; 858 transcribed loci overlapped with predicted pseudogenes.
; Haga, Kazuo;
JNC TN4420 2002-001, 102 Pages, 2002/10
JNC-TN4420-2002-001.pdf:4.13MB
no abstracts in English
Otsubo, Akira
JNC TN4420 2000-011, 34 Pages, 2000/09
JNC-TN4420-2000-011.pdf:1.16MB
no abstracts in English
; Haga, K.;
Underwater Technology 2000, 0 Pages, 2000/00
; ; Takahashi, Nobutomo; Sato, Kazujiro;
Journal of Nuclear Science and Technology, 36(6), p.522 - 534, 1999/00
Times Cited Count：8 Percentile：53.67(Nuclear Science & Technology)None
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PNC TN9410 98-077, 69 Pages, 1998/07
Availability of proton beam accelerator-driven subcritical fast reactor (ADSFR) system as a fuel-self-supporting type power reactor, has been estimated by a cor neutronic analyses. Multiplication effect of neutrons generated in a target of the subcritical system is investigated by transport calculation. The effect of core parameters are examined by diffusion and burnup calculation with respect to possibility of a long term reactor operation. In a core which surrounds the target region, neutron transport calculation are made using DORT code based on both simple and realistic methods in order to appreciate propriety of the former method by compareing the results calculated by the two methods on a neutron flux distribution and a subcritical multiiiplication factor. THe former method is called general eigen value calculation (EVC) treating the target region as a non-multipling region, and the later is practical subcritical multiplication calculation (SMC) treating it as a local neutron source. The simple EVC underestimates the fast neutron flux as part of the core closer to the target region, but overestimates the subcritical multiplication factor of whole core. The diffusion and burnup calculation are made using 2DBURN code over many cycles in ADSFR core with the target region. The core volume in this calculation is increased by about three times compared with that in the previous preliminary analyses. The variation range of effective multiplication factor (k
) with burnup is enlarged to k = 0.90
0.05 necessary to driving an accelerator. It is possible to achieve a long term reactor operation over about 40 years, if 10wt% enriched uranium and partially dummy assemblies without fuel meat are used for an initial core and natural uranium for an exchange core.
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.
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PNC TN9410 97-064, 42 Pages, 1997/06
In our study on a hyblid fast reactor system, we have investigated it from the view point of transmutation ability of trans-uranium (TRU) nuclide making the most effective use of special features (controllability, hard neutron spectrum) of the system. It is proved that a proton beam is superior in generation of neutrons compared with an electron beam. Therefore a proton accelerator using spallation reaction with a target nucleous has an advantage to transmutation of TRU than an electron one. A fast reactor is expected to primarily have a merit that the reactor can be operated for a long temrm without employment of highly enriched plutonium fuel by using external neutron source such as the proton accelerator. Namely, the system has a desirable characteristic of being possible to self-sustained fissile plutonium. Consequently in the present report, core characteristics of the system were roughly studied by analyses using 2D-BURN code. The possibility of self-sustained fuel was investigated from the burnup and neutronic calculation in a cylindrical core with 300w/cc of power density without considering a target material region for the accelerator. For a reference core of which the height and the radius are both 100cm, there is a fair prospect that a long term reactor operation is possible with subsequent refueling of natural uranium, if the medium enriched (around 10wt%) uranium or plutonium fuels are fully loaded in the initial core. More precise analyses will be planed in a later fiscal year.
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PNC TN9410 97-029, 39 Pages, 1997/03
At present, a high power CW(Continuous Wave) electron linac accelerator is under development in PNC as a part of transmutation study by accelerators. Last year we performed nuclear and thermal calculation on a hybrid reactor system combining the electron linac and a subcritical core with TRU fuel as one of applied uses. It is well known that the hybrid reactor system can also use a proton accelerator instead of the electron one. The nuclear and thermal calculation was performed on the system using the proton accelerator in this year. Comparison of the extinguished quantity of TRU fuel was performed between calculation results of both systems. In the proton linac hybrid system, a proton beam accelerated from the linac is injected into a target located in the center of the subcritical core to produce neutrons by spallation reactions. The neutrons enter the surrounding subcritical core to extinguish the TRU. The result of calculation showed that the extinguished quantity of TRU was about 10 kg where the proton beam power of 100 MW injected into the subcritical core system of keff = 0.95 over 1 year. The extinguished quantity of TRU was about 100 times as large as that in the case studied last year on the electron linac hybrid system.
; ; Seino, Hiroshi; Kataoka, H.
p1101-1110, p.1101 - 1110, 1997/00
None
; Nomura, Masahiro;
PNC TN9410 96-205, 42 Pages, 1996/07
At present, a high power CW(Continuous Wave) electron linac accelerator is under development in PNC as a part of transmutation study by accelerators. As one of applied uses, we study a hybrid reactor system combining the linac and a subcritical core with TRU fuel. This report shows nuclear and thermal calculation results to obtain characteristics of the system. In the system, an electron beam from the linac is injected into a target located in the center of the system. In the first place, the injected electrons generate photons of 
ray via Bremsstrahlung production. After this, these photons produce neutrons by (, n) reactions. As a result, an extinguished quantity of TRU fuel is about 0.1kg when the electron beam of incident energy 100 MeV is injected into the target over 1 year. It is proven that the system might be established from the point of thermal engineering. The hybrid reactor system can also use a proton accelerator instead of the electron one. Nuclear and thermal calculation will be performed on the system using the proton accelerator. Comparison of the extinguished quantity of TRU fuel will be performed between calculation results of both systems.
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.
; Nomura, Masahiro
PNC TN9420 96-001, 57 Pages, 1996/03
Hybrid systems with a subcritical fission reactor driven by an accelerator have been studied in a few foreign countries and Japan. Such a hybrid system concept can make a high safety reactor system, but they have many technological difficulties to be solved. A system using solid core fuel and a proton accelerator is considered to have the highest technical feasibility among them. The technological difficulties were picked up to develop the system. Study was performed on methods to solve the difficulties of the methods. Important problems concerning the accelerator were a life of a filament for anion source, decrease of proton beam loss, development of CWRFQ (Continuous Wave Radio Frequency Quadruople Linear Accelerator) and CCL (Coupled Cavity Linear Accelerator) etc. The problems concerning the subcritical reactor were possession of TRU(MA) inventory, control of burn-up reactivity loss etc. The problems concerning the part connecting the accelerator and the reactor were countermeasures against damage due to radioactivation of magnetic components, development of a window for a proton beam etc.
; Sakuma, Minoru; Harada, Hideo
PNC TN9410 95-072, 39 Pages, 1995/04
Study was performed on hybrid systems of a subcritical fission reactor driven by an accelerator last year. A system using solid core fuel and a solid target was concluded to have the highest technical feasibility among them. The system of the highest feasibility was studied this year. The system studied this year uses a subcritical LMFR based on a reactor like "JOYO" and the accelerator. The study was specially focused on a core, the accelerator and reconstracted parts of the reactor. The chief end of the reconstraction is for building a plant to grasp plant characteristics of burning TRU. The objective of a reconstracted plant is acquirement of experimental data and actual results on burning TRU by changing its core geometrical parameters. Therefore the policy of the reconstruction is conserving the present state of the reactor as far as possible. Component exchange is performed only on its upper core structure. Concerning the core, its target part consists of 19 target assemblies made of tangsten and its fuel part surrounding the target part consists of fuel assemblies made of TRU metal or oxide. Core height is 1 m. Four control rods are set in the core in order to get flat power density distribution there. A proton linear accelerator of the capability of 500Mev and 10mA is adopted as the accelerator for the hybrid system. The proton accelerator is set at the south west direction part of the reactor where there are few buildings. In addition to the above, reconstruction arrangements, items required to get a liscence and RD items are studied in this report.
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.
