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Journal Articles

A Conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.

Mechanical Engineering Journal (Internet), 7(3), p.19-00489_1 - 19-00489_16, 2020/06

The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.

Journal Articles

A Conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.

Journal Articles

The Safety design guideline development for Generation-IV SFR systems

Nakai, Ryodai

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 10 Pages, 2017/06

The GIF Safety Design Criteria Task Force (SDC TF) has been developing a set of safety design guidelines (SDG) to support practical application of SDC since the completion of the "SDC Phase I Report" that clarifies safety design requirements for Gen-IV SFR systems. The main objective of the SDG development is to assist SFR developers and vendors to utilize the SDC in their design process for improving the safety in specific topical areas including the use of inherent/passive safety features and the design measures for prevention and mitigation of severe accidents. The first report on "Safety Approach SDGs" aims to provide guidance on safety approaches covering specific safety issues on fast reactor core reactivity and on loss of heat removal. The second report on "SDGs on key Structures, Systems and Components (SSCs)" focuses on the functional requirements for SSCs important to safety; reactor core system, reactor coolant system, and containment system.

Journal Articles

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors, 4; Balance of plant

Chikazawa, Yoshitaka; Kato, Atsushi; Nabeshima, Kunihiko; Otaka, Masahiko; Uzawa, Masayuki*; Ikari, Risako*; Iwasaki, Mikinori*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05

Design study and evaluation for SDC and safety SDG on the BOP of the demonstration JSFR including fuel handling system, power supply system, component cooling water system, building arrangement are reported. For the fuel handling system, enhancement of storage cooling system has been investigated adding diversified cooling systems. For the power supply, existing emergency power supply system has been reinforced and alternative emergency power supply system is added. For the component cooling system and air conditioning, requirements and relation between safety grade components are investigated. Additionally for the component cooling system, design impact when adding decay heat removal system by sea water has been investigated. For reactor building, over view of evaluation on the external events and design policy for distributed arrangement is reported. Those design study and evaluation provides background information of SDC and SDG.

Journal Articles

The High temperature gas cooled reactor fuel

Sawa, Kazuhiro; Ueta, Shohei; Iyoku, Tatsuo

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 10 Pages, 2003/09

This paper provides present status of research and development for the coated fuel particle (CFPs) including the advanced ZrC-CFP. Current HTGR employs so-called TRISO-CFPs with SiC layer. In safety design of the HTGR fuels, it is important to retain fission products within CFPs so that their release to primary coolant does not exceed an acceptable level. The behavior of TRISO-CFPs has been investigated through experiments and reactor operation. These data show excellent performance of the TRISO-CFPs when they are correctly fabricated. On the other hand, the crystalline material comprising the SiC layer has a tendency to decompose at high temperature. The transition temperatures of beta-SiC (as-deposited) to alpha-SiC vary from 1600 to 2200$$^{circ}$$C. ZrC is one of the transition metal carbides which are characterized by the high melting point and the thermodynamic stability etc. The CFPs with CVD-ZrC coatings have been investigated including the fabrication processes and characterization techniques developments.

JAEA Reports

Study on the safety system in the High Temperature Gas Cooled Reactor (Contract research)

Nishihara, Tetsuo; Muto, Yasushi; Uchida, Shoji*; Yoshioka, Naoki*

JAERI-Tech 2001-077, 44 Pages, 2001/12

JAERI-Tech-2001-077.pdf:2.16MB

JAERI has conducted the feasibility study of the HTGR gas turbine system from 1996 to 2000 sponsored by MEXT. This report concludes the safety criteria and rationalization of the safety items in the HTGR system.With respect to the safety criteria, the same value for the LWR is selected as the limit of radiation exposure. Probability of the design basis event (DBE) and beyond design basis event (BDBE) is set lower than those for the LWR to get higher safety margin. Adequate initial events and mitigation system are selected to consider the event sequence. The concept of the probability analysis is applied to identify DBEs and BDBEs. It is found that some safety items can be rationalized in consideration of the safety features of the HTGR. Finally, the safety class and design category of the items in the HGTR-GT are classified.

Journal Articles

Safety criteria and quality control of HTTR fuel

Sawa, Kazuhiro; Suzuki, Shuichi*; Shiozawa, Shusaku

Nuclear Engineering and Design, 208(3), p.305 - 313, 2001/09

 Times Cited Count:37 Percentile:92.17(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Decrease in coolability events analysis for the safety assessment of JRR-3 silicide core by THYDE-W code

Kaminaga, Masanori; Yamamoto, Kazuyoshi

JAERI-Tech 97-016, 120 Pages, 1997/03

JAERI-Tech-97-016.pdf:3.76MB

no abstracts in English

JAEA Reports

Reactivity initiated events analysis for the safety assessment of JRR-3 silicide core by EUREKA-2 code

Kaminaga, Masanori

JAERI-Tech 97-014, 125 Pages, 1997/03

JAERI-Tech-97-014.pdf:4.04MB

no abstracts in English

JAEA Reports

Proposal of safety design methodologies for an HTGR-hydrogen production system; Mainly on countermeasures against fire and explosion

Nishihara, Tetsuo; Hada, Kazuhiko; Shiozawa, Shusaku

JAERI-Research 97-022, 110 Pages, 1997/03

JAERI-Research-97-022.pdf:4.1MB

no abstracts in English

Journal Articles

Method and results of safety evaluation of the high-temperature engineering test reactor

Nakagawa, Shigeaki; Kunitomi, Kazuhiko; Sawa, Kazuhiro

Nuclear Technology, 115(3), p.266 - 280, 1996/09

 Times Cited Count:3 Percentile:33.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Safety concept of severe accident free HTR and its demonstration by the HTTR

Kunitomi, Kazuhiko; Shiozawa, Shusaku; Baba, Osamu

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.303 - 307, 1996/00

no abstracts in English

JAEA Reports

Reactivity initiated events analysis for the safety assessment of JRR-4 silicide LEU core

Kaminaga, Masanori; Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nakano, Yoshihiro

JAERI-Tech 95-040, 79 Pages, 1995/07

JAERI-Tech-95-040.pdf:2.25MB

no abstracts in English

JAEA Reports

Safety analysis of JMTR-LEU cores, 1; Reactivity initiated accident analysis

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;

JAERI-M 92-095, 68 Pages, 1992/07

JAERI-M-92-095.pdf:1.52MB

no abstracts in English

JAEA Reports

Nuclear hot spot factor of JMTR-LEU core

Nagaoka, Yoshiharu; Komukai, Bunsaku; ; Saito, Minoru;

JAERI-M 92-042, 92 Pages, 1992/03

JAERI-M-92-042.pdf:2.18MB

no abstracts in English

JAEA Reports

Examination on the safety criteria in safety assessment of fuel and core of the High Temperature Engineering Test Reactor(HTTR) under abnormal conditions

Hayashi, Kimio; Shiozawa, Shusaku; Shindo, Masami; Iyoku, Tatsuo; *; Kikuchi, Takayuki; Sawa, Kazuhiro; Nakagawa, Shigeaki; Kashimura, Satoru; ; et al.

JAERI-M 91-140, 61 Pages, 1991/09

JAERI-M-91-140.pdf:2.38MB

no abstracts in English

Journal Articles

Design and safety consideration in the High-Temperature Engineering Test Reactor(HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru

Energy, 16(1-2), p.449 - 458, 1991/00

 Times Cited Count:3 Percentile:52.11(Thermodynamics)

no abstracts in English

Journal Articles

Safety consideration in setting the design criteria on the JAERI design studies

T.IWAKI*; Nozawa, Masao*; J.TAKAHASHI*; S.TERASAWA*; H.SHIOZUKA*; M.FUJITA*

ANL-7520 PART-II, p.67 - 76, 1968/00

no abstracts in English

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