Skip to main content
SpringerLink
Log in

Fast Reactor Design

  • Chapter
  • First Online:
Book cover Super Light Water Reactors and Super Fast Reactors

  • 1520 Accesses

Abstract

This chapter covers designs and analyses of the Super Fast Reactors. Fuel rod failure modes and associated fuel rod design criteria as well as a fuel rod design example are presented. The idea of locating hydrogenous moderator layers in the blanket assemblies for negative void reactivity is introduced. Three-dimensional nuclear core design procedure fully coupled with thermal-hydraulic calculation as well as several examples of core design is introduced. Evaluation method of the maximum cladding surface temperature by subchannel analysis and statistical thermal design procedure is introduced. The feedwater controller designed for the Super LWR is improved to be more suitable for the Super Fast Reactor where the main steam temperature changes more sensitively because of smaller heat capacity. Design of the power raising phase in the plant startup is presented in consideration of the thermal and thermal-hydraulic stability criteria. The influence of complicated two-pass flow scheme is emphasized. Safety of the Super Fast Reactor is found to be severer than that of the Super LWR due to the higher power density, smaller reactivity feedback, and the complicated two-pass flow scheme. Several design improvements of the core and safety system are proposed to improve the safety.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Log in via an institution
Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 189.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 249.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 249.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. J. Yoo, “Three-Dimensional Core Design of Large Scale Supercritical Light Water-Cooled Fast Reactor,” Doctoral thesis, the University of Tokyo (2006)

    Google Scholar 

  2. A. E. Waltar and A. B. Reynolds, “Fast Breeder Reactors,” Pergamon Press (1980)

    Google Scholar 

  3. Y. Oka and K. Kataoka, “Conceptual Design of a Fast Breeder Reactor Cooled by Supercritical Steam,” Annals of Nuclear Energy, Vol. 19, 243–247 (1992)

    Article  Google Scholar 

  4. T. Jevremovic, Y. Oka and S. Koshizuka, “Effect of Zirconium-Hydride Layers on Reducing Coolant Void Reactivity of Steam Cooled Fast Breeder Reactors,” Journal of Nuclear Science and Technology, Vol. 30(6), 497–504 (1993)

    Article  Google Scholar 

  5. T. Jevremovic, Y. Oka and S. Koshizuka, “Design of an Indirect-Cycle Fast Breeder Reactor Cooled by Supercritical Steam,” Nuclear Engineering and Design, Vol. 144, 337–344 (1993)

    Article  Google Scholar 

  6. T. Jevremovic, Y. Oka and S. Koshizuka, “Conceptual Design of an Indirect-Cycle, Supercritical Steam Cooled Fast Breeder Reactor with Negative Coolant Void Reactivity Characteristics,” Annals of Nuclear Energy, Vol. 20, 305–313 (1993)

    Article  Google Scholar 

  7. Y. Oka, S. Koshizuka, T. Jevremovic and Y. Okano, “Design Concept of a Supercritical-Water-Cooled Fast Breeder Reactor,” Proc. 9th KAIF/KNS Annual Conference, Seoul, Korea, April 6–8, 1994, 183–194 (1994)

    Google Scholar 

  8. Y. Oka, T. Jevremovic and S. Koshizuka, “Negative Void Reactivity in a Large Liquid-Metal Fast Breeder Reactor with Hydrogeneous Moderator (ZrH1.7) Layers,” Nuclear Technology, Vol. 107, 15–22 (1994)

    Google Scholar 

  9. T. Jevremovic, Y. Oka and S. Koshizuka, “Core Design of a Direct-Cycle, Supercritical-Water-Cooled Fast Breeder Reactor,” Nuclear Technology, Vol. 108, 24–32 (1994)

    Google Scholar 

  10. Y. Oka, T. Jevremovic and S. Koshizuka, “Negative Coolant Void Reactivity in Large FBRs with Hydrogeneous Moderator Layers,” Proc. ANS Topical Meeting on Advances in Reactor Physics, Knoxville, TN, USA, April 11–15, 1994, 419–428 (1994)

    Google Scholar 

  11. Y. Oka, S. Koshizuka, T. Jevremovic and Y. Okano, “Systems Design of Direct-Cycle, Supercritical-Water-Cooled Reactors,” Transactions of ENC’94, Int. Nucl. Congress, Lyon, France, October 2–6, 1994, 473–477 (1994)

    Google Scholar 

  12. Y. Oka and T. Jevremovic, “Negative Void Reactivity in Large Fast Breeder Reactors with Hydrogeneous Moderator Layer,” Annals of Nuclear Energy, Vol. 23, 1105–1115 (1996)

    Article  Google Scholar 

  13. T. Namba, M. Yamawaki and S. Kanno, “Surface Processes of Hydrogen Transport in Fusion Reactor Materials,” Journal of Nuclear Materials, Vols. 128–129, 646–651 (1984)

    Article  Google Scholar 

  14. M. Suzuki and H. Saitou, “Light Water Reactor Fuel Analysis Code FEMAXI-6 (Ver.1),” JAEA-Data/Code 2005-003, JAEA (2005)

    Google Scholar 

  15. D. Baron and J. C. Couty, “A Proposal for Unified Fuel Thermal Conductivity Model Available for UO2, (U-Pu)O2, and UO2-Gd2O3 PWR Fuel,” Proc. the IAEA TCM on Water Reactor Fuel Element Modeling at High Burnup and Its Experimental Support, Windermere, UK (1994)

    Google Scholar 

  16. M. Suzuki, H. Saitou and T. Iwamura, “Analysis of MOX Fuel Behavior in Reduced Moderation Water Reactor by Fuel Performance Code FEMAXI-RM,” Nuclear Engineering and Design, Vol. 227, 19–27 (2004)

    Article  Google Scholar 

  17. R. J. White and M. O. Tucker, “A New Fission Gas Release Model,” Journal of Nuclear Materials, Vol. 118, 1–38 (1983)

    Article  Google Scholar 

  18. M. V. Speight, “A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation,” Nuclear Science and Engineering, Vol. 37, 180–185 (1969)

    Google Scholar 

  19. D. Schrire, A. Kindlund and P. Ekberg, “Solid Swelling of LWR UO2 Fuel,” Proc. Enlarged HPG Meeting, Lillehammer, Norway, HPR-349/22 (1998)

    Google Scholar 

  20. D. L. Hagrman and G. A. Reyman, “MATPRO-Version 11. A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior,” NUREG/CR-0497, TREE-1280, Rev. 3, US-NRC (1979)

    Google Scholar 

  21. T. Kaito, T. Mizuno and S. Ukai, “An Evaluation of Creep Rupture Strength of Advanced Austenitic Stainless Steel (PNC1520),” JNC-TN-9400-99-036, JNC (1999) (In Japanese)

    Google Scholar 

  22. K. Rempe, K. Smith and A. Henry, “SIMULATE-3 Pin Power Reconstruction: Methodology and Benchmarking,” Proc. Int. Reactor Phys. Conf., Jackson Hole, Wyoming, September 18–22, 1988, Vol. III, 19 (1988)

    Google Scholar 

  23. R. Boer and H. Finnemann, “Fast Analytical Flux Reconstruction Method for Nodal Space–Time Nuclear Reactor Analysis,” Annals of Nuclear Energy, Vol. 19, 617–628 (1992)

    Article  Google Scholar 

  24. M. Mori, “Core Design Analysis of the Supercritical Water Fast Reactor,” Doctoral thesis, Institut fur Kernenergetik und Energiesysteme der Universitat Stuttgart (2005)

    Google Scholar 

  25. Uranium-Zirconium Hydride Fuels for TRIGA Reactors, General Atomics Report, UZR-28, General Atomics (1997)

    Google Scholar 

  26. L. Cao, Y. Oka, Y. Ishiwatati and Z. Shang, “Fuel, Core Design and Subchannel Analysis of a Super Fast Reactor,” Journal of Nuclear Science and Technology, Vol. 45(2), 1–11 (2008)

    Article  Google Scholar 

  27. L. Cao, H. Ju, Y. Ishiwatari, et al., “Research and Development of a Super Fast Reactor (2) Core Design Improvement on Local Void Reactivity,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1291 (2008)

    Google Scholar 

  28. L. Cao, Y. Oka, Y. Ishiwatari and S. Ikejiri, “Three-Dimensional Core Analysis on a Super Fast Reactor with Negative Local Void Reactivity,” Nuclear Engineering and Design, Vol. 239, 408–417 (2009)

    Article  Google Scholar 

  29. Y. Ishiwatari, M. Yamakawa, Y. Oka and S. Ikejiri, “Research and Development of a Super Fast Reactor (1) Overview and High-Temperature Structural Design,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1290 (2008)

    Google Scholar 

  30. H. Ju, L. Cao, Y. Ishiwatari, et al., “Core Design and Fuel Rod Analyses of a Super Fast Reactor with High Power Density,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper 9264 (2009)

    Google Scholar 

  31. Y. Ishiwatari, C. Peng, T. Sawada, et al., “Design and Improvement of Plant Control System for a Super Fast Reactor,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper 9261 (2009)

    Google Scholar 

  32. J. Cai, Y. Ishiwatari, S. Ikejiri and Y. Oka, “Thermal and Stability Considerations for a Supercritical Water-Cooled Fast Reactor During Power-Raising Phase of Plant Startup,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper 9265 (2009)

    Google Scholar 

  33. M. J. Watts and C. T. Chou, “Mixed Convection Heat Transfer to Supercritical Pressure Water,” Proc. 7th Int. Heat Transfer Conf., Munich, W. Germany, September 6–10, 1982, 495–500 (1982)

    Google Scholar 

  34. K. Kitoh, S. Koshizuka, and Y. Oka, “Refinement of Transient Criteria and Safety Analysis for a High-Temperature Reactor Cooled by Supercritical Water,” Nuclear Technology, Vol. 135, 252–284 (2001)

    Google Scholar 

  35. A. A. Bishop, R. O. Sandberg and L. S. Tong, “Forced Convection Heat Transfer to Water at Near-Critical Temperatures and Supercritical Pressures,” WCAP-2056, Part IV, Westinghouse Electric Corp. (1964)

    Google Scholar 

  36. F. W. Dittus and L. M. K. Boelter, “Heat Transfer in Automobile Radiators of the Tubular Type,” University of California Publications in English, Berkeley, Vol. 2, 443–461 (1930)

    Google Scholar 

  37. S. Ikejiri, Y. Ishiwatari and Y. Oka, “Loss of Coolant Accident Analysis of a Supercritical-Pressure Water-Cooled Fast Reactor with Downward Flow Channels,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper 9257 (2009)

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Department of Nuclear Energy Graduate School of Advanced Science and Engineering, Waseda University, Nishi-Waseda campus Building 51 11F, room 09B 3-4-1 Ohkubo, Shinjuku-ku, Tokyo, 169-8555, Japan

    Yoshiaki Oka

  2. Department of Systems Innovation Graduate School of Engineering, University of Tokyo, Building 8, 3FL room 317 Hongo-campus, 7-3-1 Hongo, Bunkyo-ku, Tokyo, 113-8656, Japan

    Seiichi Koshizuka

  3. Department of Nuclear Engineering and Management Graduate School of Engineering, University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo, 113-8656, Japan

    Yuki Ishiwatari

  4. Department of Nuclear Engineering and Management, University of Tokyo, Hongo 7-3-1, 113-8656, Bunkyo-ku, Tokyo, Japan

    Akifumi Yamaji

Authors
  1. Yoshiaki Oka
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Seiichi Koshizuka
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Yuki Ishiwatari
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Akifumi Yamaji
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Yoshiaki Oka .

Glossary

ADS

Automatic depressurization system

AFEN

Analytic function expansion nodal method

ALHGR

Average linear heat generation rate

ANM

Analytic nodal method

ATWS

Anticipated transient without scram

BOEC

Beginning of equilibrium cycle

BOL

Beginning of fuel lifetime

BWR

Boiling water reactor

CDF

Cumulative damage fraction

CPM

Collision probability method

CR

Control rod

CRBRP

Clinch River Breeder Reactor Project

EOEC

End of equilibrium cycle

EOL

End of fuel lifetime

FDM

Finite difference method

FDS

Finite difference scheme

FIV

Flow induced vibration

FR

Fast reactor

HFF

Heterogeneous form factor

IR

Intermediate resonance

LMFBR

Liquid-metal-cooled fast breeder reactor

LMP

Larson–Miller Parameter

LOCA

Loss of coolant accident

LPCI

Low-pressure core injection

LWR

Light water reactor

MCPR

Minimal critical power ratio

MCST

Maximum cladding surface temperature

MCSTDP

Monte Carlo Statistical Thermal Design Procedure

MDNBR

Minimum departure from nucleate boiling ratio

MLHGR

Maximum linear heat generation rate

MOC

Method of characteristic

MOEC

Middle of equilibrium cycle

MOX

Mixed oxide

MSS-AS

Method of successive smoothing with analytic solution

NEM

Nodal expansion method

NR

Narrow resonance

PCI

Pellet cladding interaction

P/D

Pitch-to-diameter

PWR

Pressure water reactor

RCP

Reactor coolant pump

RPV

Reactor pressure vessel

RTDP

Revised thermal design procedure

SCWR

Supercritical Water-Cooled Reactor

SWU

Separate working unit

TD

Theoretical density

TH

Thermal hydraulic

TRU

Transuranium

ZRH

Zirconium hydride

Rights and permissions

Reprints and permissions

Copyright information

© 2010 Springer Science+Business Media, LLC

About this chapter

Cite this chapter

Oka, Y., Koshizuka, S., Ishiwatari, Y., Yamaji, A. (2010). Fast Reactor Design. In: Super Light Water Reactors and Super Fast Reactors. Springer, Boston, MA. https://doi.org/10.1007/978-1-4419-6035-1_7

Download citation

  • DOI: https://doi.org/10.1007/978-1-4419-6035-1_7

  • Published:

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4419-6034-4

  • Online ISBN: 978-1-4419-6035-1

  • eBook Packages: EngineeringEngineering (R0)

Publish with us

Policies and ethics

Search

Navigation