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JNC TJ3410 2000-020, 80 Pages, 2000/03
JNC-TJ3410-2000-020.pdf:41.34MB
no abstracts in English
; Moro, Satoshi; ; Kakehi, Isao; ;
PNC TN9410 98-033, 284 Pages, 1998/03
System engineering division of OEC has being carried out a design study of the advanced nuclear fuel recycle system using electro-metallurgical process, aiming for improvements in safety, reliability, economy and a1so in environmental burden and nuclear non-proliferation. But the public criticism against nuclear power is more severe recently, and the situation is changing as seeing in the conclusion of the round-table conference on FBR. The researcher's meetings, in which researchers in PNC and from other organizations attended, were held during December, 1997 and March, 1998 in order to discuss on the advanced nuclear fuel recycle system and technology for FBR to be aimed in the future, and how to execute its research & development, etc. The conclusions of this meeting are as follows: (1)The future advanced FBR fuel cycle system shall be the system which has high potential for maximum utilization of uranium resources, and also for revolutionary improvements of economy, safety, environmental burden, etc. so as to be accepted in the society. (2)Regarding to the process of the future fuel eycle system, electro-metallurgical process that is able to apply for reprocessing of different types of fuel (oxide, metal and nitride) and is flexible for technical progress is recommended. Research & development of this system and technology shall be carried out. (3)The mission of PNC (new organization) is to select the most appropriate advanced FBR fuel cycle system from the viewpoint of the long-term FBR age in the future, and to conduct development of its system. It is expected for the new organization to execute its research and development steadily in cooperation with other research institutes, etc. under the nation-wide assessment and agreement. According to the above conclusions, the system engineering division will enhance the design study of the advanced FBR fuel cycle system and establish the definite concept of the system in cooperation with concerned in and ...
PNC TN9410 91-286, 117 Pages, 1991/08
A conventional type of RSS in a large scale FBR was designed and its unavailability was analyzed with fault-tree. Reliability of logic circuits of the reaetor protection system is relatively high when compared to that of the control rod insertion. Contributing factors to the unavailabity are multiple failures of detection systems, and failure to insert rods such as failure to deratch or rod jamming. Then the new concept of control rod release mechanism was introduced in the RSS design. The thermal-hydraulic characteristics of the mechanism was analyzed using computer codes SSC-L and AQUA. Further, qualitative analysis of the common cause failure for the RSS was tried with the generic cause approach. The reactor protection systems of the backup RSS are diversified by the self actuated control rod release mechanism. With such a mechanism, the number of common cause factors were decreased for postulated LOF event.
PNC TN241 83-22, 166 Pages, 1984/03
Discussion on partial modification of the Monju design is described, corresponding with the results of research and development, and with the advance of detail design. Items discussed are cancellation of the Concrete Cooling System and alterations of the Primary Argon Gas System, the EX-vessel Fuel Storage System, the SHTS Pump and the Solid Waste Processing System. Safety evaluation of the modifications are described according to the necessity.
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PNC TN241 81-28, 292 Pages, 1981/11
Computer codes for safety analysis, including systems codes, which are used for the evaluation of LMFBR plants, have been developed along with the progress of the construction and the operation of experimental fast reactor "JOYO". On the other hand, a large number of data has been accumulated at O-arai Engineering Center and other laboratories both in Japan and abroad with the advance of safety R&D on Liquid Metal Fast Breeder Reactor (LMFBR). Various models of analysis have been proposed and many computer codes have been developed which are based on these models. This paper describes the essential part of the models and the functions of the codes, thus developed, which are used for the safety evaluation of LMFBR plant such as the prototype fast breeder reactor "MONJU".
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PNC TN941 81-52, 296 Pages, 1981/02
Recently surveillance systems for nuclear power plants are increasingly required for the improvement of plant safety and availability. In order to establish the surveillance system of the prototype fast breeder reactor "MONJU", some techniques have been developed and applied to the 50MW Steam Generator Test Facility ty at OEC. As the first stage of the development, information display techniques for the plant operators and some anomalous state detection techniques are discussed in this paper. The operators can obtain such plant informations as digital and graphic outputs by cathode ray tubes (CRTs) and print out by a lineprinter and typewriters. Also the operators are informed of results of anomalous diagnosis by annunciator alarms moment by moment. Application tests of the anomalous state detection techniques have been carried out. These techniques include a cross check technique of multi-measuring system, a automatic detection system of a small scale sodium-water reaction, a differential alarm and prediction method of the time of anomalous occurrance and a display method of degree of superheat of evaporator (EV) outlet steam. It was concluded by our evaluation of the test results that those techniques are applicable to the "MONJU" design without major modification. We will develop new techniques and improve these systems to make them applicable to "MONJU", considering the "man-machine system", using this test facility.
; ; Makino, Akihiro; Murano, Toru*; Wakabayashi, Hiroaki*; Yoshii, Koji*
PNC TN841 77-06, 76 Pages, 1976/03
no abstracts in English