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Journal Articles

Outline of the R&D plan for the fast reactor cycle system development in JAEA

Hayafune, Hiroki; Maeda, Seiichiro; Ohshima, Hiroyuki

Nippon Genshiryoku Gakkai-Shi, 61(11), p.798 - 803, 2019/11

In the "Strategic Roadmap" of Fast Reactor Development decided at the Inter-Ministerial Council for Nuclear Power in December 2018, the development works for the around next 10 years were identified, and the role of JAEA was presented. In response, JAEA has prepared a framework for R&D plans for about 5 years on the fast reactor technology and the fuel cycle technology (reprocessing, fuel manufacturing, fuel and material development). In the future, JAEA will promote independent R&D works based on these plans, and provide the obtained R&D results together with various testing functions of JAEA to the activities of the private sector, etc. Through these actions, JAEA will actively contribute to the future fast reactor development. This article outlines JAEA's policy and the R&D items (development of ARKADIA; Advanced Reactor Knowledge- and AI-Aided Design Integration Approach through the whole Plant Life Cycle, development of standards and standards system, development of safety improvement technology, research in the fuel cycle technology), the policy of international cooperation, the human resource development, and the future perspective were explained.

Journal Articles

Seismic evaluation for a large-sized reactor vessel targeting SFRs in Japan

Uchita, Masato*; Miyagawa, Takayuki*; Dozaki, Koji*; Chikazawa, Yoshitaka; Kubo, Shigenobu; Hayafune, Hiroki; Suzuno, Tetsuji*; Fukasawa, Tsuyoshi*; Kamishima, Yoshio*; Fujita, Satoshi*

Proceedings of 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) (CD-ROM), p.380 - 386, 2018/04

It is well-known that pool-type SFRs are the main streams recently in a field of Generation IV reactors. The pool-type encloses primary pumps and IHXs located around the core barrel in a main vessel. Consequently, the main vessel diameter trends to be larger than that of loop-types. From the viewpoint of commercialization in the future, a target of the vessel diameter and its weight including Sodium coolant will increase further. In this paper, the prospects are described in terms of seismic design and structural integrity for the thermal loadings to prevent buckling of the reactor vessel based on parameter studies with diameters of the vessel. In addition, the seismic isolation device which will be effective as a countermeasure is proposed in order to secure a margin against buckling of a large reactor vessel.

Journal Articles

Benchmarking of economic evaluation models for an advanced loop-type sodium cooled fast reactor

Mukaida, Kyoko; Kato, Atsushi; Shiotani, Hiroki; Hayafune, Hiroki; Ono, Kiyoshi

Nuclear Engineering and Design, 324, p.35 - 44, 2017/12

 Times Cited Count:1 Percentile:78.69(Nuclear Science & Technology)

An economic calculation model based on detailed mass-flow (the JAEA model) was developed for the comprehensive evaluation of an advanced loop-type sodium-cooled fast reactor cycle system (SFR) designed in the FaCT project. The JAEA model enables calculation of the processing amount and its composition in each facility by simulating mass-flow, and has function to evaluate economics based on the processing amount. In this report, to identify the difference in evaluation methods between the JAEA model and an internationally-authorized code, and verify its calculation functions, the generation cost of SFR system was evaluated using the JAEA model and the G4-ECONS. Consequently, it was clarified that the JAEA model is influenced to higher degree by the discount rate. When the present value was not taken into account, the results of both methods were quite similar, but it was found that the sensitivity of the load factor is relatively larger the G4-ECONS than in the JAEA model.

Journal Articles

Advanced sodium-cooled fast reactor development regarding GIF safety design criteria

Hayafune, Hiroki; Chikazawa, Yoshitaka; Kamide, Hideki; Iwasaki, Mikinori*; Shoji, Takashi*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 11 Pages, 2017/06

Design studies on a next generation sodium-cooled fast reactor (SFR) considering the safety design criteria (SDC) developed in the generation IV international forum (GIF) was summarized. To meet SDC including the lessons learned from the TEPCO's Fukushima Dai-ichi Nuclear Power Plants accident, the heat removal function was enhanced to avoid loss of the function even if any internal events exceeding design basis or severe external event happen. Several design options have been investigated and auxiliary core cooling system using air as ultimate heat sink has been selected as an additional cooling system regarding system reliability and diversification. Even though the next generation SFR already adopts seismic isolation system, main component designs have been improved considering revised earthquake conditions. For other external events, design measures for various external events are taken into account. Reactor building design has been improved and important safety components are diversified and located separately improving independency. Those design studies and evaluations on the next generation sodium-cooled reactor have contributed to the development of safety design guidelines (SDG) which is under discussion in the GIF framework.

Journal Articles

Current status of GIF collaborations on sodium-cooled fast reactor system

Hayafune, Hiroki; Glatz, J.-P.*; Yang, H.*; Ruggieri, J.-M.*; Kim, Y.-I.*; Ashurko, Y.*; Hill, R.*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 12 Pages, 2017/06

The SFR system arrangement Phase II became effective on 16 February 2016 by signatures of CEA, JAEA, KAERI, USDOE, and Rosatom, and was extended for additional 10 years. Collaboration of GIF SFR is growing adding new reactor concepts and related RDs. In 2015, a project arrangement on SFR System Integration and Assessment (SIA) has been signed by 7 members : China, EU, France, Japan, Korea, Russia and US. In the SIA project, RD needs from the SFR design will be shown to the RD project, and RD results from each RD project will be integrated into the designs.

Journal Articles

Severe external hazard on hypothetical JSFR in 2010

Chikazawa, Yoshitaka; Kato, Atsushi; Hayafune, Hiroki; Shimakawa, Yoshio*; Kamishima, Yoshio*

Nuclear Technology, 192(2), p.111 - 124, 2015/11

 Times Cited Count:1 Percentile:85.75(Nuclear Science & Technology)

Evaluation of severe external hazards on JSFR has been analyzed. For seismic design, safety components are confirmed to maintain their functions even against recent strong earthquakes. For tsunam, hypothetical station blackout has been evaluated.

Journal Articles

Japan-France collaboration on the astrid program and sodium fast reactor

Rouault, J.*; Le Coz, P.*; Garnier, J.-C.*; Hamy, J.-M.*; Hayafune, Hiroki; Iitsuka, Toru*; Mochida, Haruo*

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.832 - 837, 2015/05

The French and international industrial partners already joined the project from 2010 to 2013 and many others are also effective in the Research and Development in support of ASTRID. A new partnership is now effective on both topics with Japan. This collaboration on the ASTRID Program and Sodium Fast Reactor is now fully integrated in the ASTRID program organization. In addition a specific Joint Team, CEA, AREVA, JAEA, MHI and MFBR, has been created to follow specifically Japanese contribution and develop evaluations of a common interest to orientate future work and contribute to ASTRID options confirmation and be of an interest for the future Japanese Fast Breeder reactor.

Journal Articles

ASTRID, the SFR GENIV technology demonstrator project; Where are we, where do we stand for?

Rouault, J.*; Abonneau, E.*; Settimo, D.*; Hamy, J.-M.*; Hayafune, Hiroki; Gefflot, R.*; Benard, R.-P.*; Mandement, O.*; Chauveau, T.*; Lambert, G.*; et al.

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.824 - 831, 2015/05

The Preconceptual Design phase of the ASTRID Project ended late 2012, the main goal was to evaluate innovative options. It is now followed by the AVP2 phase planned until the end of 2015 whose objectives are both to focus the design in order to finalize a coherent reactor outline and to finalize by December 2015 the Safety Option Report. The CEA acts as the industrial architect of the project. In 2014, Japan which participates now in the design studies and also in Research and Development in support of the ASTRID Project and VELAN are the latest partners to join the Project. The next important milestone is at the end of 2015 with the release by the Project team of a convincing and coherent Conceptual Design file.

Journal Articles

Comparison of JSFR design with EDF requirements for future SFR

Uematsu, Mari Mariannu; Pr$`e$le, G.*; Mariteau, P.*; Sauvage, J.-F.*; Hayafune, Hiroki; Chikazawa, Yoshitaka

Journal of Nuclear Science and Technology, 52(3), p.434 - 447, 2015/03

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Electricite de France (EDF) and JAEA have signed a bilateral agreement for research and development cooperation and information exchange on future sodium-cooled fast reactors (SFR) since 2008. Within the bilateral framework, a comparison of Japan sodium-cooled fast reactor (JSFR) design with future French SFR concept has been done based on, firstly the requirement of the investor operator (EDF) of future French SFRs and secondly the French safety baseline that could be applicable to these reactors which is currently under preparation. This paper describes the comparison work results of JSFR and EDF requirements for future SFRs where the specific designs of JSFR were evaluated as interesting from EDF point of view. The comparison work pointed out the differences in safety baselines between two countries as well.

Journal Articles

Design features and cost reduction potential of JSFR

Kato, Atsushi; Hayafune, Hiroki; Kotake, Shoji*

Nuclear Engineering and Design, 280, p.586 - 597, 2014/12

 Times Cited Count:3 Percentile:67.39(Nuclear Science & Technology)

To improve the economic competitiveness of the Japan Sodium-cooled Fast Reactor (JSFR), several innovative designs have been introduced, e.g. reduction of number of main cooling loop, shorter pipe arrangement by adopting thermally durable material, a compact reactor vessel (RV), integration of a primary pump and an intermediate heat exchanger (IHX). A new approach for construction cost estimation has been introduced to handle innovative technologies, for example, concerning different kinds of material, fabrication processes of equipment etc. As results of cost estimations and the latest conceptual JSFR design, economic goals of Generation IV nuclear energy systems can be achieved by expecting the following cost reduction effects: commodity reduction by adopting innovative design, economy of scale by power generation increase, learning effect etc.

Journal Articles

Design approach for decay heat removal systems based on the safety design criteria for Gen-IV sodium-cooled fast reactor

Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Hayafune, Hiroki; Yokoi, Shinobu*; Nakata, Shuhei*; Tani, Akihiro*; Shimakawa, Yoshio*

Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.616 - 623, 2014/04

This paper focuses on loss of heat removal system (LOHRS) type event as Design Extension Condition (DEC) and describes candidates design measures to improve the decay heat removal system of JSFR against LOHRS type DEC. The design requirements are determined based on the Safety Design Criteria for Generation-IV Sodium-cooled fast reactor system. Effectiveness and reliability of the candidate design measures are discussed with preliminary evaluations.

Journal Articles

R&D in support of ASTRID and JSFR; Cross-analysis and identification of possible areas of cooperation

Devictor, N.*; Chikazawa, Yoshitaka; Saez, M.*; Rodriguez, G.*; Hayafune, Hiroki

Nuclear Technology, 182(2), p.170 - 186, 2013/05

 Times Cited Count:1 Percentile:86.44(Nuclear Science & Technology)

CEA and JAEA intend to develop prototype or demonstration (proto/demo) of sodium-cooled fast reactors within these two decades. Common final goals of their respective programs are SFR commercialization. The target of commercialized SFR for both parties is basically consistent with the Generation IV goals. Due to industrial backgrounds and feedback of past/existing reactor experiences, ASTRID and JSFR have selected pool and loop configurations respectively. CEA and JAEA have cross-analyzed both pool and loop concepts (ASTRID and demonstration JSFR). The analysis results showed that both concepts are technologically feasible and meet design goals. From the view point of collaboration, the present analysis has identified a wide range of collaborative items, in several fields: design principles (ex. design target, design standard), development on components and systems, development on parts of components, devices, or sub-systems, design methods, simulation tools, etc.

Journal Articles

Evaluation of severe external events on JSFR

Hayafune, Hiroki; Kato, Atsushi; Chikazawa, Yoshitaka; Okubo, Tsutomu; Sagawa, Hiroshi*; Shimakawa, Yoshio*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Safe Technologies and Sustainable Scenarios (FR-13) (USB Flash Drive), 11 Pages, 2013/03

Evaluation of earthquake and tsunami on JSFR has been analyzed. For seismic design, safety components are confirmed to maintain their functions even against recent strong earthquakes. As for Tsunami, some parts of reactor building might be submerged including component cooling water system whose final heat sink is sea water. However, in the JSFR design, safety grade components are independent from component cooling water system (CCWS). The JSFR emergency power supply adopts a gas turbine system with air cooling, since JSFR does not basically require quick start-up of the emergency power supply thanks to the natural convection DHRS. Even in case of long station blackout, the DHRS could be activated by emergency batteries or manually and be operated continuously by natural convection.

Journal Articles

Evaluation of JSFR key technologies

Chikazawa, Yoshitaka; Aoto, Kazumi; Hayafune, Hiroki; Kotake, Shoji; Ono, Yushi; Ito, Takaya*; Toda, Mikio*

Nuclear Technology, 179(3), p.360 - 373, 2012/09

 Times Cited Count:9 Percentile:33.93(Nuclear Science & Technology)

Key technologies for Japan Sodium-cooled Fast Reactor (JSFR) have been evaluated. The ten technologies: high burn-up fuel, safety enhancement, compact reactor vessel, two-loop cooling system using high chromium steel, integrated intermediate heat exchanger/pump component, reliable steam generator, natural circulation decay heat removal system, simplified fuel handling system, containment vessel made of steel plate reinforced concrete and advanced seismic isolation system have been confirmed to be feasible to be installed a conceptual design of demonstration JSFR to be ready for large scale demonstration experiments.

Journal Articles

Comparison of JSFR design with EDF requirements for future SFR

Uematsu, Mari Mariannu; Pr$`e$le, G.*; Mariteau, P.*; Sauvage, J.-F.*; Hayafune, Hiroki; Chikazawa, Yoshitaka

Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.836 - 849, 2012/06

EDF and JAEA have signed a bilateral agreement for research and development cooperation and information exchange on future sodium-cooled fast reactors (SFR) since 2008. Within the bilateral framework, a comparison of Japan Sodium-cooled Fast Reactor (JSFR) design with future French SFR concept has been done based on the requirement of EDF, the investor-operator of future French SFR, and the French safety baseline, under the framework of EDF-JAEA bilateral agreement of research and development cooperation on future SFR. The specific designs of JSFR were evaluated as interesting from EDF point of view. The comparison work pointed out the differences in safety baselines between two countries as well.

Journal Articles

Evaluation of Earthquake and Tsunami on JSFR

Chikazawa, Yoshitaka; Enuma, Yasuhiro; Kisohara, Naoyuki; Yamano, Hidemasa; Kubo, Shigenobu; Hayafune, Hiroki; Sagawa, Hiroshi*; Okamura, Shigeki*; Shimakawa, Yoshio*

Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.677 - 686, 2012/06

Evaluation of Earthquake and Tsunami on JSFR has been analyzed. For seismic design, safety components are confirmed to maintain their functions even against recent strong Earthquakes. As for Tsunami, some parts of reactor building might be submerged including component cooling water system whose final heat sink is sea water. However, in the JSFR design, safety grade components are independent from component cooling water system (CCWS). The JSFR emergency power supply adopts a gas turbine system with air cooling, since JSFR does not basically require quick start-up of the emergency power supply thanks to the natural convection DHRS. Even in case of long station blackout, the DHRS could be activated by emergency batteries or manually and be operated continuously by natural convection.

Journal Articles

Steam generator with straight double-walled tube; Development of fabrication technologies of main structures made of high chrome steel-made

Kurome, Kazuya*; Kawamura, Masaya*; Enuma, Yasuhiro*; Tsujita, Yoshihiro*; Sato, Mitsuru*; Futagami, Satoshi; Hayafune, Hiroki

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 11 Pages, 2012/00

Journal Articles

Conceptual design for a large-scale Japan sodium-cooled fast reactor, 1; Feasibility of key technologies

Chikazawa, Yoshitaka; Aoto, Kazumi; Hayafune, Hiroki; Ono, Yushi; Kotake, Shoji; Toda, Mikio*; Ito, Takaya*

Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), p.426 - 435, 2011/05

Key technologies for Japan Sodium-cooled Fast Reactor (JSFR) has been evaluated. The hot vessel, two-loop cooling system using high chromium steel, integrated intermediate heat exchanger/pump component, highly reliable steam generator, natural circulation decay heat removal system and improved in-service inspection and repair capability have been confirmed to be feasible as development items for the next stage.

Journal Articles

POOL and LOOP type sodium-cooled fast reactors; Identification of cooperation possibilities

Devictor, N.*; Chikazawa, Yoshitaka; Saez, M.*; Rodriguez, G.*; Hayafune, Hiroki

Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), p.664 - 673, 2011/05

CEA and JAEA intend to develop prototype or demonstration (proto/demo) of sodium-cooled fast reactors within these two decades. Common final goals of their respective programs are SFR commercialization. The target of commercialized SFR for both parties is basically consistent with the Generation IV goals. Due to industrial backgrounds and feedback of past/existing reactor experiences, ASTRID and JSFR have selected pool and loop configurations respectively. CEA and JAEA have cross-analyzed both pool and loop concepts (ASTRID and demonstration JSFR). The analysis results showed that both concepts are technologically feasible and meet design goals. From the view point of collaboration, the present analysis has identified a wide range of collaborative items; they are described in the paper.

Journal Articles

Steam water pressure drop under 15 MPa

Liu, W.; Tamai, Hidesada; Takase, Kazuyuki; Hayafune, Hiroki; Futagami, Satoshi; Kisohara, Naoyuki

Journal of Power and Energy Systems (Internet), 5(3), p.229 - 240, 2011/04

For a steam generator with straight double-walled heat transfer tubes that used in a sodium cooled faster breeder reactor, clarification of flow instability in heat transfer tubes is one of the most important research themes. As the first step of the research, thermal hydraulics experiments with water were performed under high pressure condition in JAEA with using a circular tube. Pressure drop, heat transfer coefficients and void fraction data were derived. This paper summarizes the pressure drop characteristics under 15MPa. Several two-phase flow multiplier models were checked and then, it was found that both two-phase flow multiplier models of Chisholm and homogeneous can predict the present experimental data in high accuracy.

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