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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

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 FY19901991. 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

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.

JAEA Reports

Design of fuel assembly for an efficiency test of FBR fuel

*; Morii, Tadashi*; *; *; *; *; Kinjo, Hidehito*

PNC TJ9214 88-003, 394 Pages, 1988/06

PNC-TJ9214-88-003.pdf:7.31MB

In the experimental fast reactor JOYO, two new tests programs are scheduled in near future in order to verify high-power and high-burnup capability of LMFBR fuel pins : PTM(Power-to-Melt) test and RTCB(Run-to-Cladding Breach) test. A study is performed for the license of the tests. In this study, the fuel assemblies for the PTM and RTCB tests is designed, Safety assessment for the possible events occurred in the course of the tests, namely melt of sample fuel (PTM test) and cladding breach (RTCB test) is performed. Lastly, safety assessment for the accidents occurred in the course of the tests is also performed to obtain a license. As for the PTM test, the fuel assembly is designed considering thermal expansion of fuel pins and designed in order to prevent local blockage caused by released sample fuel and hold the released fuel within the assembly in preparations for the worst case of pin failure. The effect of reactivity insert by fuel slumping and pellet-cladding mechanical interaction caused by fuel melt within the test pin occurred during the PTM test is studied to show an integrity of the test pins. Analytical results show an integrity of test pins under the conditions with superposition of anticipated transient whose possibility of occurrence is relatively high. Lastly, even if the test pin is breached to release sample fuel, the calculated radiation dose to population is shown to be sufficiently lower than the limited values. As for the RTCB test, the devices are proposed to lower the released rate of FP gas and prevent an adjacent pin failure caused by the released gas in the cource of the test. Analytical results for the event of gas impingement on the adjacent spare pins show no additional breach of those pins. Calculated results with superposition of the representative anticipated transients and accidents also show an integrity of the adjacent spare pins. The released radio-activities calculated for the above events are sufficient smaller ...

JAEA Reports

Evaluation of events in accordance with new guideline

*; *; *; *; Morii, Tadashi*

PNC TJ9214 88-002, 423 Pages, 1988/06

PNC-TJ9214-88-002.pdf:9.11MB

This study investigates an applicability of the 'Guideline of LMFBR Safety', which was established in a licensing process for the prototype fast breeder reactor "MONJU" by Nuclear Safety Committee, to licensing for the facility change of "JOYO" in performing an efficiency test of FBR fuel. The philosophy for safety design which must be described in appendix 8 of the application of license for the facility change is proposed under the provisions of the 'Guideline of LMFBR Safety'. The following three accidents which was judged to require further analysis after reconsideration of the accident classification under the provisions of the 'Guideline of Assessment of LMFBR Safety' are evaluated. The calculated radiation dose to population is shown to be sufficiently lower than the limited values. (1)Fuel Handling Accident. (2)Sodium Leak Accident from Overflow Tank. (3)Sodium Leak Accident from Cold Trap. This report also includes the study on that the recriticality accident described in the present application of license can be classified in LPHC (Low Probability High Consequence) events. The appendix 10 of the application of license for the facility change is proposed in order to perform an efficiency test of FBR fuel.

JAEA Reports