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Journal Articles

Impact of safety design enhancements on construction cost of the advanced sodium loop fast reactor in Japan

Kato, Atsushi; Mukaida, Kyoko

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05

Improvement of economic competitiveness is a part of key requirement in the project. By adopting innovative technologies to reduce plant commodities, JSFR could achieve economic competitiveness compared with LWR. After the Fukushima-Dai-ichi Nuclear Power Plants accident, safety enhancement measures were added on LWR in Japan mainly against external hazards. In parallel, Safety Design Criteria and Guidelines (SDC/SDG) for SFR were constructed in the framework of Generation IV international forum. Design studies of JSFR were carried out responding to GIF SDC/SDG and lessons learn from the Fukushima accident. This reports an impact of recent safety design enhancements on JSFR construction cost. Safety design enhancement adopted in JSFR.

Journal Articles

Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor

Ohgama, Kazuya; Aliberti, G.*; Stauff, N. E.*; Oki, Shigeo; Kim, T. K.*

Mechanical Engineering Journal (Internet), 4(3), p.16-00592_1 - 16-00592_9, 2017/06

Journal Articles

Comparative study on burnup characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor

Ohgama, Kazuya; Aliberti, G.*; Stauff, N. E.*; Oki, Shigeo; Kim, T. K.*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04

Journal Articles

Tradeoff analysis of metal-fueled fast reactor design concepts

Stauff, N. E.*; Ohgama, Kazuya; Aliberti, G.*; Oki, Shigeo; Kim, T. K.*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04

Journal Articles

Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor

Ohgama, Kazuya; Aliberti, G.*; Stauff, N. E.*; Oki, Shigeo; Kim, T. K.*

Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 6 Pages, 2016/06

Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using Japan Sodium-cooled Fast Reactor (JSFR) design with metal fuel. In this benchmark study, core characteristic parameters at the beginning of cycle were evaluated by the best estimate deterministic and stochastic methodologies of ANL and JAEA. The results obtained by both institutions are agreed well with less than 200 pcm of discrepancy on the neutron multiplication factor, and less than 3% of discrepancy on the sodium void reactivity, Doppler reactivity, and control rod worth. The results by the stochastic and deterministic were compared in each party to investigate impacts of the deterministic approximation and to understand potential variations in the results due to different calculation methodologies employed. Impacts of the nuclear data libraries were also investigated using a sensitivity analysis methodology.

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:12.03(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

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors, 1; Overview

Kamide, Hideki; Ando, Masato*; Ito, Takaya*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

JAEA, JAPC and MFBR have been conducted design study for the Japan Sodium-cooled Fast Reactor (JSFR), which is a design concept aiming at future commercial use as sustainable electric power source. Since 2011, in order to contribute to the development of safety design criteria (SDC) and safety design guideline (SDG), which include the lesson learned from the TEPCO's Fukushima Dai-ichi Nuclear Power Plants accident, in the frame work of generation IV international forum (GIF), the design study is focusing on the design measures against sever external events such as earthquake and tsunami. At the same time, the design study is going into detail and paying much attention to the maintenance and repair to make surer its feasibility. This paper summarizes the design concept of the demonstration version of JSFR in which progress of design work was incorporated.

Journal Articles

Water experiments on thermal striping in reactor vessel of Japan Sodium-cooled Fast Reactor; Countermeasures for significant temperature fluctuation generation

Kobayashi, Jun; Ezure, Toshiki; Kamide, Hideki; Oyama, Kazuhiro*; Watanabe, Osamu*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

A column type upper internal structure (UIS) is installed in the upper plenum of reactor vessel in JSFR. High cycle thermal fatigue may occur at the bottom plate (CIP) of the UIS where the hot sodium from the fuel subassembly can mix with the cold sodium from the control rod channel and the blanket fuel subassembly. We have been conducted a water experiment using a reactor upper plenum model to grasp the thermal-hydraulic phenomena around control rod (CR) channels, and to obtain countermeasures for significant temperature fluctuation on the CIP. The experimental apparatus has 1/3 scale and 60$$^{circ}$$ sector model of the reactor upper plenum. By the experiment, characteristics of fluid temperature fluctuation between the handling head of the assemblies and the CIP are measured and countermeasure for the significant temperature fluctuation generation will be discussed on the influence of the distance from the handling head outlet to the lower surface of the CIP.

Journal Articles

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors, 3; Progress of component design

Enuma, Yasuhiro; Kawasaki, Nobuchika; Orita, Junichi*; Eto, Masao*; Miyagawa, Takayuki*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

In the frame work of generation IV international forum, safety design criteria and safety design guideline for the generation IV sodium-cooled fast reactors have been developing. JAEA, JAPC, MFBR have been investigating design study for JSFR to satisfy SDC. In addition to the safety measures, maintainability, reparability and manufacturability are taken into account in the JSFR design study. This paper describes the design of main components. Enlargement of the access route for the inspection devices and addition of the access routes were carried out for the reactor structure. The pump-integrated IHX was modified for the primary heat exchanger, which was installed for the decay heat removal in the IHX at the upper plenum, to be removable for improved repair and maintenance. For the steam generator, protective wall tube type design is under investigation as an option with less R&D risks.

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:0.01(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:4 Percentile:36.81(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

Studies on maintainability and repairability for Japan Sodium-cooled Fast Reactor (JSFR)

Isono, Kenichi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Dozaki, Koji*; Oya, Takeaki*; Yui, Masahiro*

Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 7 Pages, 2014/07

Aiming at enabling maintenance and repair of almost all components in JSFR demonstration reactor to a level equivalent to that attained for the light water reactors, we identified a number of parts which have difficulty in maintenance and repair in main components of the reactor structure and the primary/secondary main coolant system. And we defined the criteria for design improvement and then provided candidates of improvement measures for the identified parts. Furthermore, we made a modification of the plant design in a consistent manner integrating the improvements investigated for each major component. A series of evaluations were conducted to check the feasibility as a power plant. As the result, we found that the concept could be adopted not only to the demonstration reactor (750 MWe) but to the commercial one (1500 MWe).

Oral presentation

Study on reliability enhancement of JSFR spent fuel pool facility

Otaka, Masahiko; Kato, Atsushi; Chikazawa, Yoshitaka; Uzawa, Masayuki*; Kaneko, Fumiaki*

no journal, , 

Reliability of JSFR spent fuel pool make-up system was improved through design study including related evaluation on the cooling capability under extreme high ambient temperature conditions.

Oral presentation

Design study for seismic isolation system of fast reactor JSFR, 1; Concept of seismic isolation system

Sakamoto, Yoshihiko; Fukasawa, Tsuyoshi*; Kawasaki, Nobuchika; Okamura, Shigeki*

no journal, , 

Design study of an FBR demonstration facility is now in progress for the sodium-cooled fast reactor (JSFR). In JSFR, a seismic isolation system is adopted from the viewpoint of reduction in seismic force to major components taking into account the characteristics of the fast reactor. After the 2011 off the Pacific coast of Tohoku Earthquake, a design earthquake was revised for investigation to ensure seismic resistance under a severer seismic condition. Moreover, countermeasures against various external hazards such as tsunami, etc. were investigated for the purpose of establishment of safety design guidelines and enhancement of safety. This presentation introduces the design earthquake and the seismic isolation system concept responding to the external hazards with issues for realization.

Oral presentation

Improvement of JSFR failed fuel detection system by delayed neutron monitoring

Nabeshima, Kunihiko; Aizawa, Kosuke; Chikazawa, Yoshitaka; Okazaki, Hitoshi*; Hayashi, Masateru*

no journal, , 

FFD-DN (failed fuel detection system by delayed neutron monitoring) method is to measure the delayed neutron flux which is released from failed fuel to sodium coolant when fuel failure occurs. Here, the part of FFD-DN method will be cleared. Then, reactor trip before fuel failure propagation could be performed by new FFD-DN detection form with B$$_{4}$$C filter and collimator.

Oral presentation

Design study for flow around pump shaft of Integrated IHX/pump of fast reactor JSFR, 1; Study of pump shaft deformation by natural convection of cover gas

Enuma, Yasuhiro; Handa, Takuya; Shimazaki, Masanori*; Ono, Yukihiko*; Yoshida, Kazuhiro*; Hayakawa, Satoshi*; Inoue, Tomoyuki*

no journal, , 

no abstracts in English

Oral presentation

Safety improvement in SFR building layout design

Kato, Atsushi; Chikazawa, Yoshitaka; Nabeshima, Kunihiko; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*

no journal, , 

Based on the Safety design criteria for the Generation-IV sodium cooled fast reactor and intrinsic features of SFR, we studied the reactor building layout design in order to improve its safety.

Oral presentation

Development of the JSFR main components, 2; Conceptual design on the straight double-walled tube SG against sodium-water reaction

Futagami, Satoshi; Enuma, Yasuhiro; Kawamura, Masaya*; Kanda, Hironori*; Ichihara, Takashi*

no journal, , 

no abstracts in English

Oral presentation

Study on reduction of vertical seismic response for JSFR

Yamamoto, Tomohiko; Kawasaki, Nobuchika; Ishikawa, Nobuyuki; Chikazawa, Yoshitaka; Fukasawa, Tsuyoshi*; Okamura, Shigeki*

no journal, , 

Due to the increase of the seismic condition for JSFR design study, the seismic condition for the design study of components is severer. This report explains the effect of study on reduction of vertical seismic response through the 3-dimensional FEM analysis focusing on study on reduction of vertical seismic response of main components that are critical in seismic feasibility. It also explains the integrity of vertical seismic response of FEM model and the mass model used in design studies with reflecting the vertical seismic response reduction.

Oral presentation

21 (Records 1-20 displayed on this page)