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Hori, Toru; Chikazawa, Yoshitaka; Kida, Masanori; Konomura, Mamoru
JNC TY9400 2003-013, 314 Pages, 2003/08
JNC-TY9400-2003-013.pdf:21.54MB
In the "Feasibility Studies on Commercialized Fast Reactor System", sodium-cooled small-scale reactor concepts have been studied fromstandpoints of economy, safety, and long lived core. And in JFY2002,based on study of technical issues, three concepts (electricity output of 150MWe) were designed with parameter of reactivity control and coolant circulation type. The above concepts had prospect to attain safety enhancement (avoiding core melt without SASS at ATWS) and long lived core (10 years). They could not satisfy cost target (350,000 yen/kWe), because the inherent and passive safe core was flat (phi3.3m x h0.6m),and upper reactor diameter increased by considering some space to take out EMP periodically. But forced circulation-type concepts had potential to decrease construction cost by adopting compact core with mitigation of coolant temperature reactivity coefficient and devising in-vessel EMP arrangement.Control rod system had merits about decreasing reactor diameter, utilizing relative displacement reactivity coefficient between reactor and control rod, and small technical issues, by comparing with reflector system. And EMP had no necessity to be taken out from reactor, except failure accidents, by considering EMP characteristic of Passive equipment and maintenance process. Based on these results, it was important that some attractive small-scale reactor concepts, which attained compact and high temperature reactor with control rod and forced circulation-type, would be proposed by aiming at "longer lived core (more than 10 years)", "simpler operation and maintenance" , and "diversified social needs (hydrogen production)".
Morishita, Masaki; Kitamura, Seiji; Inoue, Kazuhiko; Kida, Masanori; Moro, Satoshi; Kato, Asao; Fushimi, Minoru*
JNC TY9400 2003-009, 682 Pages, 2003/05
JNC-TY9400-2003-009.pdf:35.1MB
Japan Nuclear Cycle Development Institute(JNC) and Japan Atomic Power Company (JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies,as part of the supporting R&D activities for the feasibility studies on commercialized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy,Trade,and Industry (METI) with technical support by JNC is included in this joint study. This report contains the results of the research on the structural design technology. The research scope was identified as (1) Study on Developing Program,(2) Study on 3-dimentional Entire Building Base Isolation System,and (3) Study on Vertical Isolation System for Main Equipment, and the results of this year's studies are summarized as follows.
Moribe, Takeshi; Kubo, Shigenobu; Saigusa, Toshiie; Konomura, Mamoru
JNC TY9400 2003-007, 188 Pages, 2003/05
JNC-TY9400-2003-007.pdf:7.62MB
In (Feasibility Study on Commercialized Fast Reactor Cycle System), technological options including various coolant (sodium,heavy metal, gas, water,etc.), fuel type (MOX, metal, nitride) and output power are considered and classified, and commercialized FBR that have economical cost equal to LWR are pursued. In conceptual study on gas cooled FBR in FY2002, to identify the prospect of the technical materialization of the helium cooled FBR using coated particle fuel which is an attractive concept extracted in the year of FY2001, the preliminary conceptual design of the core and entire plant was performed. This report summarizes the results of the plant design study in FY2002. The result of study is as follows. (1)For the passive core shutdown equipment, the curie point magnet type self-actuated device was selected and the device concept was set up. (2)For the reactor block, the concept of the core supporting structure, insulators and liners was set up. For the material of the heat resistant structure, SiC was selected as a candidate. (3)For the seismic design of the plant, it was identified that a design concept with three-dimensional base isolation could be feasible taking the severe seismic condition into account. (4)For the core catcher, an estimation of possible event sequences under severe core damage condition was made. A core catcher concept which may suit the estimation was proposed. (5)The construction cost was roughly estimated based on the amount of materials and its dependency on the plant output power was evaluated. The value for a small sized plant exceeds the target construction cost about 20%.
Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*
JAERI-Tech 2003-041, 106 Pages, 2003/03
JAERI-Tech-2003-041.pdf:6.58MB
In the second stage of the research and development for a high-temperature helium-leak detection system, the temperature sensor using optical fibres was studied. The sensor detects the helium leakage by the temperature inclease surrounded opitical fibre with or without heat insulator. Moreover, the applicability of high temperature equipments as the HTTR system was studied. With the sensor we detected 5.0-20.0 cm
/s helium leakages within 60 minutes. Also it was possible to detect earlier when the leakage level is at 20.0 cm/s.
Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*
JAERI-Research 2003-006, 65 Pages, 2003/03
JAERI-Research-2003-006.pdf:2.89MB
In the final third stage of the research and development for a high-temperature helium-leak detection system, the radiation sensor was developed in order to detect very small helium leakage. Applying the radiation sensor, we proposed not only the direct detection method which uses the detection of FP gas in helium, but also the active method which uses the difference in the radiation absorption between helium and air. From obtained data it was found that we can detect 0.2 cm/s leakage within 10 minutes by the active method.
Fujii, Kimio; Matsuo, Hideto*
JAERI-Review 2002-034, 44 Pages, 2002/12
JAERI-Review-2002-034.pdf:3.34MB
Graphite material is used as a moderator and reflector of graphite-moderated gas-cooled reactors such as the Tokai Nuclear Power Station of Japan Atomic Power Company. For the decommissioning of those reactors, it is very important to obtain the density of carbon-14 in the graphite of which half-time is very long, and the development of the reduction technique for density of carbon-14 is one of the main technical issues as well. The reactor ceased the commercial operation on March 1998, and is in the process of the decommissioning. Technical developement on nuclear graphite disposal is one of the main issues, and it is pointed out that carbon-14 density is an impotant factor for the treatment on the disposal of the nuclear graphite. In order to resolve the problem, literatures survey was carried out for describing the status of technical development on resolving the problem. This report describes the outline of the literatures surveyed and the list of the related literatures is attached as well.
; Aoto, Kazumi; kasahara, Naoto; ; Sagayama, Yutaka*; *; *
JNC TY9400 2001-026, 978 Pages, 2002/01
JNC-TY9400-2001-026.pdf:28.0MB
None
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JNC TY9400 2001-023, 362 Pages, 2001/07
JNC-TY9400-2001-023.pdf:16.74MB
no abstracts in English
; ; ; Kawasaki, Nobuchika; ; Kamiyama, Kenji;
JNC TY9400 2001-012, 1793 Pages, 2001/06
JNC-TY9400-2001-012.pdf:83.61MB
no abstracts in English
; ;
JNC TY9400 2001-014, 489 Pages, 2001/04
JNC-TY9400-2001-014.pdf:17.82MB
no abstracts in English
; Hayashi, Hideyuki; ; ; ; Takaki, Naoyuki;
JNC TY9400 2001-011, 493 Pages, 2001/03
JNC-TY9400-2001-011.pdf:20.55MB
no abstracts in English
; ; ; ; ;
JNC TY9400 2000-026, 287 Pages, 2000/07
JNC-TY9400-2000-026.pdf:11.72MB
no abstracts in English
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JNC TY9400 2000-025, 280 Pages, 2000/07
JNC-TY9400-2000-025.pdf:10.32MB
no abstracts in English
; Hayafune, Hiroki; ; ; ; Kawasaki, Nobuchika;
JNC TY9400 2000-024, 706 Pages, 2000/06
JNC-TY9400-2000-024.pdf:28.02MB
no abstracts in English
; Hayashi, Hideyuki; ; ; *; ;
JNC TY9400 2000-021, 452 Pages, 2000/03
JNC-TY9400-2000-021.pdf:16.64MB
no abstracts in English
Shono, Akira; ; ; Hoshi, Takashi*; Kusunoki, Hiroyuki*; Hamada, Masao*
PNC TY9471 94-002, 48 Pages, 1994/03
None
Shono, Akira; ; ; Hoshi, Takashi*; Kusunoki, Hiroyuki*; Hamada, Masao*
PNC TY9471 94-001, 539 Pages, 1994/03
None