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JAEA Reports

Conceptual design study of the actinide recycle reactor; Study of core structural with ductless fuel assemblies

Ogawa, Shinta; Hayafune, Hiroki; Tozawa, Katsuhiro; Ichimiya, Masakazu; Hayashi, Hideyuki; Mukaibo, Ryuichi

PNC TN9430 96-007, 354 Pages, 1996/07

PNC-TN9430-96-007.pdf:13.67MB

It is required enhanced core safety characteristics, recycle cost reduction, mitigation of risk to the environment and nuclear non proliferation for the fast reactor at the commercial use age of actinide recycle. The ductless fuel assembly, which has no wrapper tube, is promising for these requirements. In this study, the thermal hydraulic and mechanical characteristics of the ductless fuel core are evaluated for 600MWe MOX core with high burnup and long operating cycle length, and conceptual structure of the ductless fuel assembly core was established. The results of the study are summarized as follows; (1)Structural of Ductless Fuel Assembly. Conceptual design of components of the ductless fuel assembly, e.g. grid spacer, tie rod, upper shielding, lower nozzle and mechanical hold down spring, were performed and conceptual structure was established. Detail study of fuel pin bundle stiffness are required in the following design study. (2)Thermo-hydraulic Characteristics of Ductless Core and Ductless Fuel Assembly. The bypass flow rate strongly depends on the gap between core region and core barrel. For this bypass flow, it is found that thermal hydraulic feasibility is expected when the gaps between core region and core barrel are decreased($$<$$1mm). Since the core flow distribution is uniform, a coolant temperature distribution depend on the power distribution into core region. For fuel assembly, if the gaps between fuel assemblies are enlarged, the maximum sodium temperature increases (20$$^{circ}$$C/mm), therefore a proper gap design are needed. (3)Mechanical Characteristics of Ductless Core. The seismic safety of ductless core, in which a mechanical hold down are used, is assured. To decrease the impact force at spacer grid, however, some considerations on the grid design is necessary to avoid buckling. (4)Thermohydraulic Safety Characteristics. The maximum sodium temperatures are roughly evaluation under the condition of natural circulation and coolant ...

JAEA Reports

Progress report of the design study on actinide recycle reactor concept; Study on the plant system

Akatsu, Minoru; Tozawa, Katsuhiro; Watanabe, Ichiro; Ichimiya, Masakazu; Hayashi, Hideyuki; Mukaibo, Ryuichi

PNC TN9430 96-005, 237 Pages, 1996/07

PNC-TN9430-96-005.pdf:9.6MB

In 1995, a design study on the mixed-oxide fuel core of the large breeder reactor was done to realize actinide (including minor actinide) 600MWe recycle reactor plant aiming at minimization of the radioactive waste products at the view point of not only to lighten the burden of the environment but also to utilize efficiently the resources, Study was carried out and R&D items were clarified as to the following items, as plant system design. (1)influences to the plant system from decay heat increase. (2)reactor structure concept due to adoption ductless fuel assembly concept. The study results are as follows. The coolant flow pass concept to core assemblies and the core support concept were studied by taking account of ductless core system and the large floating force on core assemblies due to ductless core system, the features of the concepts were clarified and the mechanical hold down (MHD) mechanism concept was adopted against the floating force. The characteristics of the connection between the upper internal structure and the core assemblies were studied for the large eccentricity of the two structures due to installation error, thermal expansion difference, inclination of core assemblies, etc. The connection that were led by MHD was guessed to be done with no large problem by special connection procedure. The reactor auxiliary cooling system capacity of 16MW a loop is sufficient to remove core decay heat to maintain the integrity of the coolant boundary structure. The heat removal characteristics under natural convection circulation coolant flow is confirmed to be superior than ducted core plant because of the lower pressure drop property of the ductless core plant. The cask car type fuel handling system was selected as referenceex-vessel fuel handling system. Because the cask car type system was able to simplify the fuel handling system by the in-line configuration of fuel handling facilities. The decay heat of ductless spent fuel assembly in sodium pot ...

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