Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Nakamura, Hiroo; Ida, Mizuho*; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki*; IFMIF International Team
Fusion Engineering and Design, 58-59, p.919 - 923, 2001/11
Times Cited Count：9 Percentile：56.08(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JNC TN9400 2000-066, 52 Pages, 2000/06
JNC-TN9400-2000-066.pdf:1.82MB
Phase I of feasibility studies on commercialized fast reactor system is being peformed for two years from Japanese Fiscal Year 1999. In this report, results of the study on fluid fuel reactors (especialiy a molten salt fast breeder reactor concept) are described from the viewpoint of technical and economical concerns of the plant system design. ln JFY1999, we have started to investigate the fluid fuel reactors as alternative concepts of sodium cooled FBR systems with MOX fuel, and selected the unique concept of a molten chloride fast, breeder reactor, whose U-Pu fuel cycle can be related to both light water reactors and fast breeder reactors on the basis of present technical data and design experiences. We selected a preliminary composition of molten fuel and conceptual plant design through evaluation of technical and economical issues essential for the molten salt reactors and then compared them with reference design concepts of sodium cooled FBR systems under limited information on the molten chloride fast breeder reactors. The following results were obtained. (1)The molten chloride fast breeder reactors have inherent safety features in the core and plant performances, ad the fluid fuel is quite promising for cost reduction of the fuel fabrication and reprocessing. (2)On the other hand, the inventory of the molten chloride fuel becomes high and thermal conductivity of the coolant is inferior compared to those of sodium cooled FBR systems, then, the size of main components such as lHX's becomes larger and the amount of construction materials is seems to be increased. (3)Furthermore economical vessel and piping materials which contact with the molten chloride salts are required to be developed. From the results, it is concluded that further steps to investigate the molten chloride fast breeder reactor concepts are too early to be conducted.
*; *; Fumoto, Hiromichi*; *; *
JNC TJ9400 2000-001, 112 Pages, 2000/02
JNC-TJ9400-2000-001.pdf:6.67MB
The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1)The process adopting crystallization method and peroxide precipitation method (2)The process adopting oxalate precipitation method (3)The process under mild aqueous conditions (crystallization method and precipitation method) (4)The process adopting crystallization method and ion-exchange method (5)The process adopting crystallization method and solvent extraction method The processes (1)
(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1)The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process.
Numata, Kazuaki; Otani, Seiji; *; *; *; Goto, Tatsuro*
JNC TN8430 2000-001, 23 Pages, 1999/09
JNC-TN8430-2000-001.pdf:0.89MB
None
Takase, Kazuyuki; Kunugi, Tomoaki*; Yamazaki, Seiichiro*; *
Dai-35-Kai Nihon Dennetsu Simpojiumu Koen Rombunshu, p.801 - 802, 1998/05
no abstracts in English
; *; Ikeda, Hisashi ; Kaminaga, Kazuhiro; ; ; Kuno, Yusuke
PNC TN8410 96-266, 67 Pages, 1996/05
None
Ookubo, Manabu; Shimizu, Ryo; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi
no journal, ,
Under the circumstances where the fuel is disposed in the reactor core and the furnace fuel storage tank during the decommissioning measures of "Monju" where the decay heat is at an extremely low level, while preventing the sodium from being frozen by the preheater heater, It is desirable to continue operation of cooling the dissipated heat released into the compartment by ventilating air conditioning equipment. However, the operation of ventilation air conditioning equipment is designed for normal operation of nuclear reactors, and it is necessary to review the proper operation according to the situation at the stage of decommissioning. In this report, we will summarize the relationship between the actual load and the capacity of the ventilating and air conditioning equipment based on the past operation data and report on the status of consideration on rational ventilation air conditioning equipment operation at the decommissioning stage.
Hashidate, Ryuta; Kondo, Yuki; Yada, Hiroki; Takaya, Shigeru; Enuma, Yasuhiro
no journal, ,
In this study, we propose a new method for extracting maintenance preconditions. Graph structures are used to represent relationship among SSCs. Maintenance preconditions are extracted by analyzing the graph structures. Furthermore, we propose an automatic maintenance scheduling method using extracted maintenance preconditions. Design issues could be extracted based on the created maintenance schedule. A simple example is presented to illustrate the proposed method.
