Skip to main content
SpringerLink
Log in

Safety

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

  • 1384 Accesses

Abstract

This chapter covers safety topics of the Super LWR. The safety principle is introduced first. The safety system design based on the safety principle is presented. Safety analysis codes for the deterministic approach to the Super LWR safety are introduced. Safety criteria for the integrities of fuel rod and pressure boundary are proposed. Selection, classification, and analyses of the possible abnormal transients and accidents in the Super LWR are presented. There are several key safety characteristics of the Super LWR that are inherent in the design features and their benefits have been identified through systematic safety analyses. A transient subchannel analysis code for the Super LWR is prepared and applied to the flow decreasing events to investigate the influence of cross flow in the fuel assemblies on the safety margin. For the probabilistic approach to the Super LWR safety, simplified level-1 PSA is performed.

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. Y. Ishiwatari, Y. Oka and S. Koshizuka, “Safety of the Super LWR,” Nuclear Engineering and Technology, Vol. 39(4), 257–272 (2007)

    Article  Google Scholar 

  2. Y. Ishiwatari, Y. Oka, S. Koshizuka, A. Yamaji and J. Liu, “Safety of Super LWR, (I) Safety System Design,” Journal of Nuclear Science and Technology, Vol. 42(11), 927–934 (2005)

    Article  Google Scholar 

  3. Y. Ishiwatari, “Safety of Super LWR,” Doctoral thesis, the University of Tokyo (2006) (in Japanese)

    Google Scholar 

  4. Y. Ishiwatari, Y. Oka, S. Koshizuka and J. Liu, “ATWS Characteristics of Super LWR with/without Alternative Action,” Journal of Nuclear Science and Technology, Vol. 44(4), 572–580 (2007)

    Article  Google Scholar 

  5. Y. Ishiwatari, Y. Oka, S. Koshizuka, A. Yamaji and J. Liu, “Safety of Super LWR, (II) Safety Analysis at Supercritical Pressure,” Journal of Nuclear Science and Technology, Vol. 42(11), 935–948 (2005)

    Article  Google Scholar 

  6. Y. Ishiwatari, Y. Oka, S. Koshizuka and J. Liu, “LOCA Analysis of Super LWR,” Journal of Nuclear Science and Technology, Vol. 43(3), 231–241 (2006)

    Article  Google Scholar 

  7. 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, 252–264 (2001)

    Google Scholar 

  8. F. D. Coffman, Jr., “LOCA Temperature Criterion for Stainless Steel Clad Fuel,” NUREG-0065, (1976)

    Google Scholar 

  9. Y. F. Shen, Z. D. Cao and Q. G. Lu, “An Investigation of Cross Flow Mixing Effect Caused by Grid Spacer with Mixing Blades in Rod Bundle,” Nuclear Engineering and Design, Vol. 125(2), 111–119 (1991)

    Article  Google Scholar 

  10. 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 

  11. Proposed standard ANS-5.1 – 1971, American Nuclear Society (1971)

    Google Scholar 

  12. K. Kamei, “Core Design of Super LWR and Its Safety Analysis at Subcritical-pressure,” Master’s thesis, the University of Tokyo (2006) (in Japanese)

    Google Scholar 

  13. K. V. Moore and W. H. Rettig, “RELAP-4: A Computer Program for Transient Thermal-hydraulic Analysis,” ANCR-1127, Aerojet Nuclear Company (1973)

    Google Scholar 

  14. J. R. S. Thom, W. M. Walker, T. A. Fallon and G. F. S. Reising, “Boiling in Subcooled Water During Flow Up Heated Tubes or Annuli,” Proc. Inst. Mech. Eng. 180 (Part 3C) (1966)

    Google Scholar 

  15. V. E. Schrock and I. N. Grossman, “Forced Convection Boiling Studies, Final Report on Forced Convection Vaporization Project,” TID-14632 (1959)

    Google Scholar 

  16. J. B. McDonough, W. Milich and E. C. King, “Partial Film Boiling with Water at 2000 psig in a Round Vertical Tube,” MSA Research Corp., Technical Report 62 (1958) (NP-6976)

    Google Scholar 

  17. D. C. Groeneveld, L. K. H. Leung, A. Z. Vasic, Y. J. Guo and S. C. Cheng, “A Look up Table for Fully Developed Film Boiling Heat Transfer,” Nuclear Engineering and Design, Vol. 225, 83–97 (2003)

    Article  Google Scholar 

  18. D. C. Groeneveld, L. K. H. Leung, P. L. Kirillov, V. P. Bobkov, I. P. Smogalev, V. N. Vinogradov, X. C. Huang and E. Royer, “The 1995 Look-up Table for Critical Heat Flux in Tubes,” Nuclear Engineering and Design, Vol. 163, 1–23 (1996)

    Article  Google Scholar 

  19. R. C. Martinelli and D. B. Nelson, “Prediction of Pressure Drop During Forced-circulation Boiling of Water,” Transactions of ASME, Vol. 71, 695–702 (1948)

    Google Scholar 

  20. J. H. Lee, S. Koshizuka and Y. Oka, “Development of a LOCA Analysis Code for the Supercritical-pressure Light Water Cooled Reactors,” Annals of Nuclear Energy, Vol. 25 (16), 1341–1361 (1998)

    Article  Google Scholar 

  21. J. H. Lee, “LOCA Analysis and Safety System Consideration for the Supercritical-Water Cooled Reactor,” Doctoral thesis, the University of Tokyo (1996)

    Google Scholar 

  22. N. E. Todreas and M. S. Kazimi, “Nuclear Systems I – Thermal Hydraulic Fundamentals,” Hemisphere Publishing Corporation, ISBN 0-89116-935-0 (1990)

    Google Scholar 

  23. F. M. Bordelon, et al., “SATAN IV Program: Comprehensive Space-time Dependent Analysis of Loss of Coolant,” WCAP-8302 (1974)

    Google Scholar 

  24. A. Yamanouchi, “Effect of Core Spray Cooling in Transient Stat After Loss of Coolant Accident,” Journal of Nuclear Science and Technology, Vol. 5(11), 547–558 (1968)

    Article  Google Scholar 

  25. Y. Murao and T. Hojo, “Numerical Simulation of Reflooding Behavior in Tight-Lattice Rod Bundles,” Nuclear Technology, Vol. 80, 83 (1998)

    Google Scholar 

  26. Anticipated Transients Without Scram for Light Water Reactors, NUREG-0460, US-NRC (1978)

    Google Scholar 

  27. Preliminary Safety Analysis Report Lungmen Nuclear Power Station Units 1 & 2, GE Nuclear Energy (1997)

    Google Scholar 

  28. ABWR Standard Safety Analysis Report, 23A6100 Rev. 1, GE Nuclear Energy (1993)

    Google Scholar 

  29. D. Y. Oh, S. H. Ahn and I. G. Kim, “Sensitivity Study on the Safety Parameters During ATWS with/without AMSAC,” Proc. ICAPP’03, Cordoba, Spain, May 4–7, 2003, Paper 3149 (2003)

    Google Scholar 

  30. Y. Okano, S. Koshizuka, K. Kitoh and Y. Oka, “Flow-induced Accident and Transient Analyses of a Direct-cycle, Light-water Cooled, Fast Breeder Reactor Operating at Supercritical Pressure,” Journal of Nuclear Science and Technology, Vol. 33(4), 307–315 (1996)

    Article  Google Scholar 

  31. K. Kamei, A. Yamaji, Y. Ishiwatari, Y. Oka and J. Liu, “Fuel and Core Design of Super Light Water Reactor with Low Leakage Fuel Loading Pattern,” Journal of Nuclear Science and Technology, Vol. 43(2), 129–139 (2006)

    Article  Google Scholar 

  32. A. A. Amsden and F. H. Harlow, “The SMAC Method: A Numerical Technique for Calculating Incompressible Fluid Flows,” Los Alamos Scientific Laboratory, Report LA-4370 (1970)

    Google Scholar 

  33. J. H. Lee, Y. Oka and S. Koshizuka, “Safety System Consideration of a Supercritical-water Cooled Fast Breeder Reactor with Simplified PSA,” Reliability Engineering & System Safety, Vol. 64, 327–338 (1999)

    Article  Google Scholar 

  34. Reactor Safety Study, An Assessment of Accident Risks in US Commercial Nuclear Power Plants, WASH-1400, Appendix-I, US Nuclear Regulatory Commission (1974)

    Google Scholar 

  35. Reactor Safety Study, An Assessment of Accident Risks in US Commercial Nuclear Power Plants, WASH-1400, Appendix-II, US Nuclear Regulatory Commission (1974)

    Google Scholar 

  36. Analysis of Core Damage Frequency from Internal Events: Peach Bottom Unit 2. Science Applications International Corp, NUREG/CR-4550, Vol. 4, US Nuclear Regulatory Commission (1986)

    Google Scholar 

  37. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants, NUREG-1150, Vol. 1, US Nuclear Regulatory Commission (1990)

    Google Scholar 

  38. Level-1 PSA of 1,100 MWe-class PWRs: Annual Report of FY1997, Nuclear Power Engineering Corporation (NUPEC), INS/M97-04 (1998) (in Japanese)

    Google Scholar 

  39. Development of Level-1 PSA Methods for BWR Plants: Annual Report of FY1999, Nuclear Power Engineering Corporation (NUPEC), INS/M99-15 (2001) (in Japanese)

    Google Scholar 

  40. Development of Level-1 PSA Methods for PWR Plants at Power: Annual Report of FY2000, Nuclear Power Engineering Corporation (NUPEC), INS/M00-04 (2001) (in Japanese)

    Google Scholar 

  41. Development of Level-1 PSA Methods for BWR Plants: Annual Report of FY2000, Nuclear Power Engineering Corporation (NUPEC), INS/M00-09 (2001) (in Japanese)

    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

ABWR

advanced boiling water reactor

ADS

automatic depressurization system

AFS

auxiliary feedwater system

ATWS

anticipated transient without scram

BDBE

beyond design basis event

BWR

boiling water reactor

CDF

core damage frequency/cumulative damage fraction

ECCS

emergency core cooling system

E/G

emergency diesel generator

FPP

fossil-fired power plant

HEM

homogeneous equilibrium model

LOCA

loss of coolant accident

LOSP

loss of offsite power

LPCI

low pressure core injection

LWR

light water reactor

MSIV

main steam isolation valve

PCMI

pellet cladding mechanical interaction

PCS

power conversion system

PCT

peak cladding temperature

PSA

probabilistic safety assessment

PWR

pressurized water reactor

RCIC

reactor core isolation cooling

RCP

reactor coolant pump

RHR

residual heat removal

ROSP

recovery of offsite power

RPS

reactor protection system

RPV

reactor pressure vessel

SCWR

supercritical pressure water cooled reactor

SG

steam generator

SLCS

standby liquid control system

SRV

safety relief valve

Super LWR

high temperature thermal reactor version of SCWR

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). Safety. In: Super Light Water Reactors and Super Fast Reactors. Springer, Boston, MA. https://doi.org/10.1007/978-1-4419-6035-1_6

Download citation

  • DOI: https://doi.org/10.1007/978-1-4419-6035-1_6

  • 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