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Reseacher

Name SUZUKI Tohru
Official Title Professor
Affiliation Department of Nuclear Safety Engineering
E-mail torusuzu@tcu.ac.jp
Web
  1. http://www.risys.gl.tcu.ac.jp/Main.php?action=profile&type=detail&tchCd=5002024
  2. https://researchmap.jp/torusuzu
Profile I have been involved in experimental research and numerical simulation for reactor safety engineering and severe accident evaluation based on the knowledge of thermal hydraulics.
Since 2002, I have been concerned with research and development of accelerator-driven subcritical reactors (ADSs) at Karlsruhe Institute of Technology (KIT) by using safety evaluation code SIMMER-III.
Since 2006, I have been leading the safety evaluation and licensing analysis of fast breeder reactors at Japan Atomic Energy Agency (JAEA).
Since 2017, I have been engaged in research and education related to nuclear safety engineering at the Department of Nuclear Safety Engineering, Tokyo City University.
Research Field(Keyword & Summary)
  1. Severe accident analysis, Safety evaluation, Fast breeder reactors, Thermal hydraulics, Multi-phase flow

    Based on academic knowledge about thermal hydraulics and multi-phase flow, severe-accident analysis and safety evaluation have been conducted for advanced reactors, especially fast breeder reactors, by utilizing numerical analysis and fundamental experiments.
Representative Papers
  1. (1) Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor, Journal of Nuclear Science and Technology, Vol.58, No.3, pp.347-360 (2021).
  2. (2) Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor, Mechanical Engineering Journal, Vol.4, No.3, pp.1-14 (2017).
  3. (3) Evaluation of recriticality behavior in the material-relocation phase for Japan sodium-cooled fast reactor, J. Nuclear Science and Technology, Vol.52, No.11, pp.1448-1459 (2015).
  4. (4) A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor, Nuclear Engineering and Technology, Vol.47, Vol.3, pp.240-252 (2015).
  5. (5) A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention, J. Nuclear Science and Technology, Vol.51, No.4, pp.493 - 513 (2014).
  6. (6) Characteristics of self-leveling behavior of debris beds in a series of experiments, Nuclear Engineering and Technology, Vol.45, No.3, pp.323-334 (2013).
  7. (7) Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels, J. Nuclear Instruments and Methods in Physics Research, Vol.562, No.2, pp.863-866 (2006).
  8. (8) Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code, Nuclear Engineering and Design, Vol.235, No.24, pp.2594-2611 (2005).
  9. (9) Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III; Extended verification using multi-bubble condensation experiment, Nuclear Engineering and Design, Vol.220, No.3, pp.240-254 (2003).
  10. (10) Analysis of gas-liquid metal two-phase flows using a reactor safety analysis code SIMMER-III, Nuclear Engineering and Design, Vol.220, No.3, pp.207-223 (2003).
Patent
  1. N/A
Award March 2021, JNST Most Cited Article Award
Grant-in-Aid for Scientific Research Support: Japan Society for Promotion of Science (JSPS) N/A
Research Grants/Projects including subsidies, donations, grants, etc. (1) Innovative Nuclear Research and Development Program, "Development of integrated safety evaluation simulation platform system for various innovative sodium-cooled fast reactors" (2020- present).
(2) Innovative Nuclear Research and Development Program, "Development of evaluation methodology for relocation behavior of disrupted core materials" (2010-2013).
(3) Innovative Nuclear Research and Development Program, "Development of evaluation technology for core disruption (Level-2 PSA)" (2009-2012).
Recruitment of research assistant(s) No
Affiliated academic society (Membership type) Atomic Energy Socicety of Japan (AESJ/member)
Education Field (Undergraduate level) Nuclear safety engineering, Reactor thermal hydraulics
Education Field (Graduate level) Nuclear safety engineering, Reactor thermal hydraulics

Affiliation