Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Study of an electromagnetic pump in a sodium cooled reactor; Design study of secondary sodium main pumps (Joint research)

Chikazawa, Yoshitaka; Kisohara, Naoyuki; Hishida, Masahiko; Fujii, Tadashi; Konomura, Mamoru; Ara, Kuniaki; Hori, Toru*; Uchida, Akihito*; Nishiguchi, Yohei*; Nibe, Nobuaki*

JAEA-Research 2006-049, 75 Pages, 2006/07

JAEA-Research-2006-049.pdf:4.55MB

In the feasibility study on commercialized fast breeder cycle system, a medium scale sodium cooled reactor with 750MW electricity has been designed. In this study, EMPs are applied to the secondary sodium main pump. The EMPs type is selected to be an annular linear induction pump (ALIP) type with double stators which is used in the 160m$$^3$$/min EMP demonstration test. The inner structure and electromagnetic features are decided reviewing the 160m$$^3$$/min EMP. Two dimensional electromagnetic fluid analyses by EAGLE code show that Rms (magnetic Reynolds number times slip) is evaluated to be 1.08 which is less than the stability limit 1.4 confirmed by the 160m$$^3$$/min EMP test, and the instability of the pump head is evaluated to be 3% of the normal operating pump head. Since the EMP stators are cooled by contacting coolant sodium duct, reliability of the inner structures are confirmed by temperature distribution and stator-duct contact pressure analyses. Besides, a power supply system, maintenance and repair feature and R&D plan of EMP are reported.

JAEA Reports

Design Study on a Fuel Handling System in a Sodium Cooled Reactor

Chikazawa, Yoshitaka; Hori, Toru*; Usui, Shinichi; Konomura, Mamoru; Nishiguchi, Yohei

JNC TY9400 2005-009, 329 Pages, 2005/07

JNC-TY9400-2005-009.pdf:24.1MB

In the feasibility study on commercialized fast breeder cycle system, fuel handling systems for sodium cooled reactors has been studied. In FY 2003 study, a fuel handling system with an EVST for a power plant with 4 medium scale modular reactors is designed and key issues about the system are identified. A manipulator type fuel handling machine suitable for the upper internal structure with a slit designed and seismic analyses show that it can treat spent fuels without interaction with upper internal structure in earthquakes. Fuel handling time is reduced adopting a sodium pot which can carry 2 subassemblies in onetime.In this study, a innovative concept without an EVST is also studied. In this concept, the total mass is not dramatically reduced comparing a system with an EVST because several fuel transfer machines with gas cooling systems are needed for safety point of view.

JAEA Reports

Design Study on Sodium-Cooled Large-Scale Reactor

Murakami, Tsutomu; Hishida, Masahiko; Kisohara, Naoyuki; Hayafune, Hiroki; Hori, Toru; Fujii, Tadashi; Uchita, Masato; Chikazawa, Yoshitaka; Uno, Osamu; Saigusa, Toshiie; et al.

JNC TY9400 2004-014, 78 Pages, 2004/07

JNC-TY9400-2004-014.pdf:7.97MB

This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2003, which is the third year of Phase 2. In the JFY2003 design study, critical subjects related to safety, structural integrity and thermal hydraulics which found in the last fiscal year has been examined and the plant concept has been modified. Furthermore, fundamental specifications of main systems and components have been set and economy has been evaluated. In addition, as the interim evaluation of the candidate concept of the FBR fuel cycle is to be conducted, cost effectiveness and achievability for the development goal were evaluated and the data of the three large-scale reactor candidate concepts were prepared.

JAEA Reports

Design Study on Sodium-Cooled Middle-Scale Modular Reactor

Hishida, Masahiko; Murakami, Tsutomu; Kisohara, Naoyuki; Fujii, Tadashi; Uchita, Masato; Hayafune, Hiroki; Chikazawa, Yoshitaka; Hori, Toru; Saigusa, Toshiie; Uno, Osamu; et al.

JNC TY9400 2004-012, 97 Pages, 2004/07

JNC-TY9400-2004-012.pdf:12.55MB

Based on the concept of a plant consisting of four modules with a capacity of 750 MWe each, which has been established by the end of FY2002, a concept of the entire plant was proposed, reflecting the modifications related to the high internal conversion type core, the double-wall straight tube steam generator (SG), and the fuel storage system. Concept studies were also performed to overcome the drawbacks of the sodium and to achieve in-service inspection and repair as easily as in light water reactor. Furthermore, feasibility studies were carried out to confirm the design, which included safety, thermal-hydraulics and the structures of the primary reactor auxiliary cooling system and the double-wall straight tube SG. A prospect for realization of this plant concept has been obtained through the evaluation results. In addition, as the interim evaluation of the candidate concepts of the FBR fuel cycle is to be conducted, cost effectiveness and achievability for the development goal were evaluated and the data of the three medium-scale reactor candidate concepts were prepared.

JAEA Reports

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems Interim Report of Phase II; Technical Study Report for Reactor Plant Systems

Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.

JNC TN9400 2004-035, 2071 Pages, 2004/06

JNC-TN9400-2004-035.pdf:76.42MB

The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.

JAEA Reports

Evaluation on fretting wear of heat-transfer tubes of Primary Sodium Mechanical Pump installed in IHX Component (3); Vibration Analysis Model and 1/4-Scale Vibration Test Equipment

Kisohara, Naoyuki; Soman, Yoshindo; Nishiguchi, Yohei; Konomura, Mamoru

JNC TN9400 2003-090, 76 Pages, 2003/10

JNC-TN9400-2003-090.pdf:4.4MB

The conceptual design study of sodium-cooled FBRs is in progress in the "Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)". In this plant system design, a primary sodium pump are placed into an intermediate heat exchanger (IHX) and these two components are installed in one vessel to reduce plant construction cost. The primary sodium pump is located in the center of IHX tube bundle and this pump-IHX component includes primary/secondary sodium flow shrouds, pump-IHX boundary shroud and bellows. Although the pump and IHX are installed in the same vessel, these two components are structurally separated, because they are connected through a bellows and their weights are supported by different floors. However, the vibration caused by pump rotation has possibility to induce the vibration of heat transfer tubes via sodium and it leads the tubes to fretting wear against their support plates. Therefore, the tube fretting wear has been evaluated by both a simple beam vibration analysis model and a detailed shell vibration analysis model. Since the pump-IHX component consists of many different parts such as shrouds and tube bundle, analysis tools cannot reveal the vibration phenomena precisely. Then the analysis model requires to be validated by vibration tests. A 1/4-scale vibration test equipment of the whole pump-IHX component has been planned to confirm the occurrence and transmission of vibration. This test equipment is precisely minimized based on the actual pump-IHX component structure except the tube bundle. Acceleration sensors are installed on the shrouds to measure beam and shell vibration phenomena, and the signal will be used to reveal vibration modes and pump response properties. The fabrication of the test equipment was completed in FY2002 except the pump. In FY2003 the vibration tests are being executed by using electromagnetic vibrator instead of the pump. In FY2005, the pump will be settled into the test equipment, and the vibration tes

JAEA Reports

Design Study on Sodium-Cooled Middle-Scale Modular Reactor

Kisohara, Naoyuki; Hishida, Masahiko; Nibe, Nobuaki; Hori, Toru; Fujii, Tadashi; Uchita, Masato; Chikazawa, Yoshitaka; Saigusa, Toshiie; Uno, Osamu; Soman, Yoshindo; et al.

JNC TY9400 2003-015, 103 Pages, 2003/09

JNC-TY9400-2003-015.pdf:6.39MB

In Phase I of the "Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)", an advanced loop type reactor has been selected as a promising concept of sodium-cooled middle-scale modular reactor, which has a possibility to fulfill the design requirements of the F/S. This report summarizes the results of the design study on the sodium-cooled middle-scale modular reactor performed in JFY2002, which is the second year of Phase 2. The construction cost of the sodium-cooled middle-scale modular reactor, which has been constructed in JFY2002, was almost achieved the economical goal. But its achievability was not sufficient to accept the concept. In order to reduce the construction cost, the plant concept has been re-constructed based on the 50 MWe plant studied in JFY2002. After that, fundamental specifications of main systems and components for the new concept have been set, and critical subjects have been examined and evaluated. In addition, in order to achieve the further cost reduction, the plant with simplified secondary system, the plant with electric magnetic pump in secondary system, and the fuel handling system are examined and evaluated. As a result of this study, the plant concept of the sodium-cooled middle-scale modular reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowingdown candidate concepts at the end of Phase 2.

JAEA Reports

Design Study on Sodium-Cooled Large-Scale Reactor

Kisohara, Naoyuki; Hishida, Masahiko; Nibe, Nobuaki; Hori, Toru; Fujii, Tadashi; Uchita, Masato; Chikazawa, Yoshitaka; Saigusa, Toshiie; Uno, Osamu; Soman, Yoshindo; et al.

JNC TY9400 2003-014, 52 Pages, 2003/09

JNC-TY9400-2003-014.pdf:3.12MB

In Phase 2 of the F/S, it is planed to precede a preliminary conceptual design of a sodium-cooled large-scale reactor based on the design of the advanced loop type reactor. Through the design study, it is intended to construct such a plant concept that can show its attraction and competitiveness as a commercialized reactor. This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2002, which is the second year of Phase 2. In the JFY2002 design study, critical subjects related to safety, structural integrity and thermal hydraulics which found in the last fiscal year has been examined and the plant concept has been modified. Furthermore, fundamental specifications of main systems and components have been set and economy has been evaluated.As a result of this study, the plant concept of the sodium-cooled large-scale reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000yens/kWe, etc.) and has a prospect to solve the critical subjects.

JAEA Reports

Flow-induced Vibration Tests for Large Diameter and High Velocity Piping (1) Test Planning and Fabrication of Test Facility

Fujii, Tadashi; Nishiguchi, Yohei; Konomura, Mamoru

JNC TN9400 2003-063, 73 Pages, 2003/08

JNC-TN9400-2003-063.pdf:2.75MB

The conceptual design study of the large-scale sodium-cooled reactor is in progress in the "Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)".The cooling system of a large-scale sodium-cooled reactor is composed of two loops in order to reduce construction cost. According to reduction of the loop number, the large diameter pipings are adopted in the primary cooling system (for example, inner diameter of a hot leg piping is 1.27m). And the average velocity in the piping increases to 9 m/s level, which is well over to a conventional plant design, therefore, Reynolds number reaches 10$$^{7}$$order levels. The hydraulic behaviors of the piping elbow, such as pressure fluctuation characteristics and formation range of flow separated layer near an elbow, under high velocity and high Reynolds number conditions are expected to be different to those under lower Reynolds number which is the highest existing number. Further, there would be the possibility of vibration of the piping by flow instability under high velocity condition. However, information of flow-induced vibration behaviors for large diameter piping is limited.Then, flow visualization and flow-induced vibration tests using 1/3 scale water test facility, which simulates hot leg piping, have been planned in order to confirm the realization of the piping design for primary cooling system. Flow pattern in the piping and pressure fluctuation near the elbow, which is a main cause of flow-induced vibration, will be measured in the flow visualization tests using the acrylic elbow model. Moreover, vibration modes and vibration response characteristics of the piping system will be measured in the flow-induced vibration tests using the stainless steel elbow model.The design of the test facility and production of the elbow models and the loop pipings were finished by 2002. In 2003, fabrication and installation of the test facility will be finished and a part of flow visualization tests will be started.

Journal Articles

LMFBR Design and its Evolution, 4; An Innovative Concept of Sodium-Cooled Middle-Scale Modular Reactor Pursuing High Economic Competitiveness

; ; Konomura, Mamoru; Toda, Mikio*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 8 Pages, 2003/00

None

JAEA Reports

Consideration on rationalization of reactor safety systems; evaluation of impact to plant safety and operations against facility sharing

Chikazawa, Yoshitaka; ; Nishiguchi, Yohei; Konomura, Mamoru

JNC TN9400 2002-068, 77 Pages, 2002/12

JNC-TN9400-2002-068.pdf:5.7MB

In the Feasibility Study of JNC, sodium cooled large-scale fast reactor and medium-scale modular reactor are studied as two of promising concepts. Sodium cooled medium-scale modular reactor has disadvantage compared to large-scale reactor that has large-scale effect. To compensate the disadvantage, modular effects are facilitated to improve facility sharing among modules, learning effect and so on. But facility sharing makes the plant system complex and impacts to plant safety and operations are worried. We evaluated the impacts to plant safety and operations by facility sharing in sodium cooled medium-scale modular reactor. We arranged ideas of facility sharing and extracted four ideas which are considered to have big impacts to safety or operations. (1)Sharing of the central control room (2)Reduction of emergency generators (3)Adoption of large capacity turbines (4)Sharing of auxiliary cooling water system In this study, we evaluated impacts to safety operability, annual inspection and availability under consideration of the risk for unscheduled shutdown against above four facility sharing plans. Consistency of the facility sharing was confirmed.

JAEA Reports

None

Aoki, Tadao; *; *; *; *; *; *

PNC TN951 77-10, 142 Pages, 1977/01

PNC-TN951-77-10.pdf:5.67MB

no abstracts in English

12 (Records 1-12 displayed on this page)
  • 1