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Nakajima, Norihiro; Aoki, Keiko*
Tokyo Daigaku Jinkobutsu Kogaku Kenkyu Senta 2017-Nendo Kenkyu Nempo, p.51 - 53, 84, 2018/12
Visiting professors research division in the Research into Artifacts, Center for Engineering (RACE) has been conducting research collaboration in Socio-Artifactology and Human-Artifactology, in order to establish the methodology of the fusion research in sociology and science for artifacts engineering for the third era activity of RACE. The division decided to observe how the methodology works in applications with social experiments and numerical experiments for 2017.
; Yamaguchi, Akira
JNC TN9400 2000-056, 150 Pages, 2000/05
JNC-TN9400-2000-056.pdf:6.67MB
[Purpose] The work was performed to make clear thermal-hydraulic issues resulting in the use of various coolants for fast reactors. [Method] Plant design features due to a use of working fluid other than sodium and design concepts relating a simplification of safety related systems were investigated. And based on the results, quantitative evaluation was made on the topical themal-hydraulic issues. Then both thermal stratification and striping phenomena were evaluated by the used of thermo-hydraulics computer programs. [Results] (1)Thermal-hydraulic issues Topical thermal-hydraulic issues of gaseous and heavy metal cooled reactors were extracted. (a)Gas cooled reactors : natural circulation,flow-induced vibration, depressurization accident (b)Heavy metal cooled reactors : thermal stratification, flow-induced vibration, sloshing And also the thermal-hydraulic issues relating compact reactor assembly and RVACS were extracted resulting from a simplification of safety related systems. (2)Evaluation of thermal stratification and striping phenomena. The following order of affects for the phenomena was obtained: (a) Thermal stratification: CO
Sodium Lead, (b) Thermal Striping: CO Lead Sodium
*; *; *
JNC TJ8420 2000-003, 99 Pages, 2000/03
JNC-TJ8420-2000-003.pdf:5.47MB
no abstracts in English
PNC TJ1409 97-023, 19 Pages, 1997/03
None
PNC TJ1409 97-022, 53 Pages, 1997/03
1 Reflection of R&D Results, Design and Operation Experiences All knowledge obtain in the project, such as R&D results, design, operation experiences and so on, are tbe reflected to following items. 1) Improvement of safety and reliability in plant eration 2) Design modification of the plant 3) Design of the next plant 2 Basic Sndpoint for Data Base Composition "Design/R&D/Plant Performance Data Base" will be mposed ad shown in the following, so that the Data Base could be utilized for reflecng them to the above items and for improving the above items, effectively and efficitly. (1) United Data Bases of Design and R&D "Design/R&D/Plant Performance Data Ba" will be composed by uniting design data base and R&D data base, considering that t R&D of the project is mainly made in order to establish the design engineering and chnical basis, such as design policy, design criteria, design conditions, alloable dign limits, design verification, etc. (2) Addition of Initial Plant Performa
PNC TJ1409 97-021, 27 Pages, 1997/03
1 Reflection of R&D Results, Design and Operation Experiences All knowledge obtain in the project, such as R&D results, design, operation experiences and so on, are tbe reflected to following items. 1) Improvement of safety and reliability in plant eration 2) Design modification of the plant 3) Design of the next plant 2 Basic Sndpoint for Data Base Composition "Design/R&D/Plant Performance Data Base" will be mposed ad shown in the following, so that the Data Base could be utilized for reflecng them to the above items and for improving the above items, effectively and efficitly. (1) United Data Bases of Design and R&D "Design/R&D/Plant Performance Data Ba" will be composed by uniting design data base and R&D data base, considering that t R&D of the project is mainly made in order to establish the design engineering and chnical basis, such as design policy, design criteria, design conditions, alloable dign limits, design verification, etc. (2) Addition of Initial Plant Performa
PNC TJ1409 97-020, 29 Pages, 1997/03
1 Reflection of R&D Results, Design and Operation Experiences All knowledge obtain in the project, such as R&D results, design, operation experiences and so on, are tbe reflected to following items. 1) Improvement of safety and reliability in plant eration 2) Design modification of the plant 3) Design of the next plant 2 Basic Sndpoint for Data Base Composition "Design/R&D/Plant Performance Data Base" will be mposed ad shown in the following, so that the Data Base could be utilized for reflecng them to the above items and for improving the above items, effectively and efficitly. (1) United Data Bases of Design and R&D "Design/R&D/Plant Performance Data Ba" will be composed by uniting design data base and R&D data base, considering that t R&D of the project is mainly made in order to establish the design engineering and chnical basis, such as design policy, design criteria, design conditions, alloabledesignlimits, design verification, etc. (2) Addition of Initial Plant Performa
Hayashi, Hideyuki; ;
PNC TN9410 96-062, 186 Pages, 1996/02
A conceptual design study on a 1300MWe large FBR plant was performed with focusing on enhancing passive safety and capital cost reduction. Spectrum-adjusted mixed nitride fueled core in which zirconium hydride was added, was applied to enlarge Doppler reactivity coefficient. Breeding ratio of 1.2 was obtained only with one layer of radial blanket subassemblies by optimizing the content of the zirconium hydride. The optimization also lightened the burden to the reactor structure through the reduction of the core diameter. Reactor passive shutdown were performed in the ATWS events of ULOF and ULOHS, and UTOP caused by one control rod full runout was endurable under the criterion of the prevention of coolant boiling. The safety feature can be called as inherent safety, because the feature comes only from the reactivity characteristics of the core. The integrities of the reactor structures which characterize head-access loop type reactor were evaluated on the transient thermal stress at the loss of flow accident and on seismic strain. Vertical strain of core support plate at loss of flow condition was also evaluated on the passive shutdown at ULOF. The capital cost of the large FBR plant was estimated 1.3 to 1.4 times as high as that of the same scale LWR based on the weight of major components.
*; *; Fukumura, Nobuo*; *; *; *; *
PNC TN1410 91-063, 239 Pages, 1991/08
no abstracts in English
;
Gummaken Gesuido Kenkyukai Hokokusho, Showa-61-Nendo, No.9, p.46 - 48, 1987/09
no abstracts in English
; ; *
JAERI-M 83-217, 85 Pages, 1983/12
no abstracts in English
; Saito, Keiichiro; Naruse, Yuji; Shiba, Koreyuki; *; *; *
JAERI-M 9735, 45 Pages, 1981/10
no abstracts in English
JAERI-M 4798, 32 Pages, 1972/04
no abstracts in English
Tanaka, Masaaki
no journal, ,
Japan Atomic Energy Agency (JAEA) is promoting research and development (R&D) related to fast reactors and nuclear fuel cycles as a contribution to carbon neutrality through the investigation of innovative technologies such as safety improvement. In order to maintain, develop, and provide the technological infrastructure for nuclear power plant innovation, that is the role of JAEA, an integrated evaluation method "ARKADIA" is under development to create innovative plant concepts and reform of the development process utilizing the wide range of knowledge cultivated through the development of fast reactors in JAEA. This presentation introduces the current status of development of sodium-cooled fast reactors and the ARKADIA-Design as a part of ARKADIA for design optimization support to address the R&Ds on thermal-hydraulics-related issues for design evaluation.