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Journal Articles

Development of safety design criteria and safety design guidelines for Generation IV sodium-cooled fast reactors

Futagami, Satoshi; Kubo, Shigenobu; Sofu, T.*; Ammirabile, L.*; Gauthe, P.*

Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 10 Pages, 2022/10

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

Reactivity control system of the high temperature engineering test reactor

Tachibana, Yukio; Sawahata, Hiroaki; Iyoku, Tatsuo; Nakazawa, Toshio

Nuclear Engineering and Design, 233(1-3), p.89 - 101, 2004/10

 Times Cited Count:10 Percentile:55.63(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structural design of high temperature metallic components

Tachibana, Yukio; Iyoku, Tatsuo

Nuclear Engineering and Design, 233(1-3), p.261 - 272, 2004/10

 Times Cited Count:23 Percentile:80.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Integrity assessment of the high temperature engineering test reactor(HTTR) control rod at very high temperatures

Tachibana, Yukio; Shiozawa, Shusaku; *; *; *

Nucl. Eng. Des., 172(1-2), p.93 - 102, 1997/00

 Times Cited Count:8 Percentile:56.29(Nuclear Science & Technology)

no abstracts in English

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