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JAEA Reports

Progress report of the design study on a large reactor

; Hayashi, Hideyuki; ; ;

PNC TN9410 94-222, 355 Pages, 1994/07

PNC-TN9410-94-222.pdf:14.85MB

A design study on a large scale fast reactor was performed with focusing on enhancement of passive safety and capital cost reduction. The passive safety feature in the plant design of next generation fast reactors is one of the important subjects to be sought. In FY 1993, studies on 1300MWe class lage fast reactor were performed aiming at passive shutdown in a typical ATWS such as the unprotected loss of flow accident (ULOF). This report describes the core design, systems design, equipments design and the technical assessment in terms of the passive safety feature. It also includes the evaluation of the seismic as well as thermal capacity of reactor building of the large fast reactor.

JAEA Reports

None

Hayashi, Hideyuki; ; ; ; ;

PNC TN9440 94-014, 232 Pages, 1994/06

PNC-TN9440-94-014.pdf:8.58MB

None

JAEA Reports

Head Access Piping System Desing

; ; ; ;

PNC TN9410 94-173, 34 Pages, 1994/05

PNC-TN9410-94-173.pdf:1.23MB

PNC made design studies on loop type FBR plants:a 600 MWe class in '91, and a 1300 MWe class in '93 both with the "head access" primary piping system. This paper focuses on the features of the smaller plant at first and afterwards on the extension to the larger one. The contents of the paper consist of R/V wall protection mechanism, primary piping circuit, secondary piping circuit, plant layout and then, discusses the extension of the applicability of the wall protection mechanism, primary piping and equipment to the larger plant. Through these studies PNC reached the conclusion that the "head access" concept is applicable to all cases of FBRs from the demonstration to commercial phase.

JAEA Reports

Progress report of the design study on a large scale reactor

; Hayashi, Hideyuki; ; Yamaoka, Mitsuaki; ; ;

PNC TN9410 93-162, 494 Pages, 1993/07

PNC-TN9410-93-162.pdf:24.65MB

A design study on a large scale fast reactor was performed based on the results of the study on 600 MWe class "reactor vessel head access concept" plant in FY1990$$sim$$1991. The objective of this study is to confirm quantitatively the applicability of "reactor vessel head access concept" to larger scale fast reactor plant as well as to establish the basic design such as core design, reactor structure, heat transport system, of 1300 MWe class "reactor vessel head access concept" plant and to evaluate its feasibility. In the former half period of FY1992, studies were performed aiming at evaluation of precision of core design, integrity of the structure and safety reflecting the final equipment design, feasibility of the concept of spent fuel storage, etc. While in the latter half period, added were the subjects on key technologies and plant concepts which enhance economy, safety, and social acceptance in order to ascertain the direction of a design study in the future and to contribute the realization of a commecial fast reactor.

JAEA Reports

Progress report of the design study on a 600MWe class plant; Evaluation of construction cost and summary of drawings

; Hayashi, Hideyuki; ; ; ; Yamaoka, Mitsuaki;

PNC TN9410 92-353, 120 Pages, 1992/11

PNC-TN9410-92-353.pdf:3.2MB

A design study on a large scale fast reactor was performed at OEC about 600MWe class plant which might be the lowest power scale as a commercial one. Results of the design study till the end of JFY1991 were summarized in a previous progress report of the design study on a large scale reactor (PNC ZN9410 92-137). In this report, the evaluation results of the construction cost of the 600MWe class plant are described and also the drawings of their various parts are summaried.

JAEA Reports

Investigation of preventive measures of gas entrainment phenomena for large scale FBR; Investigation on Baffle ring and porous-type UIS

; ; Yamaguchi, Akira; ; ; Sugawara, Satoru

PNC TN9410 92-352, 62 Pages, 1992/11

PNC-TN9410-92-352.pdf:2.3MB

In-vessel thermohydraulic analysis with multi-dimensional code AQUA was conducted to investigate efficiency of a baffle ring and of a porous-type UIS (upper instrumentation structure) for preventation of gas entrainment to coolant from gas plenum of reactor vessel. Through the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Baffle Ring Equipment] (1)In order to reduce maximum surface verocity, the effect with the width 40 cm of the baffle ring equipment better than the width 20 cm. (2)Maximum surface velocity is $$sim$$40 cm/s using the baffle ring equipment of width 40 cm. [Porous-type UIS] (1)Effective mass flow ratio of the UIS porous to the UIS skirt is 50 % to decrease maximum surface velocity. (2)Maximum surface velocity is $$sim$$52 cm/s using the porous-type UIS with the above mass flow distribution. Furthermore analysis with the AQUA code were carried out for the conbined condition of the baffle rings with 40 cm width and the porous-type UIS with the condition of the effective mass flow ratio 50 %. Maximum surface velocity 0.33 m/s closer to the MONJU condition (0.3 m/s) was obtained from the analysis.

Journal Articles

None

; Hayashi, Hideyuki; ; ; ; ;

Donen Giho, (82), p.19 - 37, 1992/06

None

JAEA Reports

Progress report of the design study on a large scale reactor; Design study on a 600MWe class plant

Hayashi, Hideyuki; ; ; ; ; ; Yamaoka, Mitsuaki

PNC TN9410 92-137, 890 Pages, 1992/05

PNC-TN9410-92-137.pdf:21.88MB

A design study on a large scale fast reactor was performed at OEC about 600 MWe class plant which might be the lowest power scale as a commercial one. The purpose of the study is set to present a plant concept which could stand together reality at the demonstration stage and innovativeness through commercialization, as well as to establish technological basis to support the design study of the utilities' plant. Features of this plant are as follows. (1)Application of intrinsic merit of a loop type plant, and introduction of a reactor-vessel-head-access-piping system which produces a new concept of primary piping shortening technology, simplification of cooling systems, improvement in reliability of components, and free-maintenance of equipments underneath the operating floor. (2)Plant design based on the technologies and experiences up to the prototype reactor, and also challenge to the technological breakthrough for the commercialization of FBR, such as drastic simplification of a shielding plug and a spent fuel handling system. This report describes the result of a design study on a large scale FBR plant, which will motivate utilities to construct the demonstration plant. This report eonsists of three parts of "System Design," "Sub-system Designs" and "Safety Design Guide and Safety Evaluation" which correspond to the text, the appendix VIII and the appendix X of the application of reactor construction permit respectively, and a part of R&D subjects derived from the design study.

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