Investigation of molten salt fast breeder reactor

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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.

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PNC TN9440 91-010, 45 Pages, 1991/07

PNC-TN9440-91-010.pdf:6.16MB

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Study on the main design parameters of large scale fast breeder reactor (II); Investigation on reduction of piping length by application of IHX floating support piping to primary main heat transport system piping of LMFBR.

*; *; Nakanishi, Seiji; *

PNC TN9410 88-103, 115 Pages, 1988/08

PNC-TN9410-88-103.pdf:14.73MB

Current emphasis in the development of liquid-metal cooled fast breeder reactors (LMFBRs) is placed on the reduction of the plant construction cost without spoiling the safety in view of its practical application. So much effort is paid for the cost reduction. The reduction of piping length of heat transport system piping is considered as an effective measure for the cost reduction. An application of component floating support piping which brings good results in LWR leads to reduction of piping length and it is an effective measure as well as bellows expansion joint piping and high-chrome-steel piping in LMFBR. A design study for the application of the IHX floating support piping system to primary main heat transport system piping of LMFBR was conducted to demonstrate the adequacy of the piping system by using the improved structural design method considering the characteristics of LMFBR. The stress analysis of piping due to dead weight, thermal expansion at steady and transient conditions, and earthquake was performed, while the nozzles stress due to internal pressure, dead weight, earthquake and thermal expansion reaction force, and thermal transients was analyzed. It was confirmed that the analytical results were satisfied the allowable values and the piping support equipments were highly put into practical use. Therefore it was concluded that the adequacy of the IHX floating support piping system was demonstrated.