Advanced search
Publication Cover
Nuclear Technology Volume 94, 1991 - Issue 3
Submit an article Journal homepage
4
Views
2
CrossRef citations to date
0
Altmetric
Technical Paper

Development of Statistical Core Thermal Design Methodology Using a Modified Latin Hypercube Sampling Method

Seung-Hyuk LeeKorea Institute of Nuclear Safety P.O. Box 16, Daeduk Danji, Taejon, Korea
,
Hyun-Koon KimKorea Institute of Nuclear Safety P.O. Box 16, Daeduk Danji, Taejon, Korea
,
Sang-Ryeol ParkKorea Advanced Institute of Science and Technology P.O. Box 150, Cheongryang, Seoul, Korea
&
Soon-Heung ChangKorea Advanced Institute of Science and Technology P.O. Box 150, Cheongryang, Seoul, Korea
Pages 407-415 | Published online: 12 May 2017

References

  • H. CHELEMER, L. H. BOMAN and D. R. SHARP, “Improved Thermal Design Procedure,” WCAP-8567, Westinghouse Corporation (July 1975).
  • H. K. KIM and K. I. HAN, “Thermal Margin Analysis of KNU-1 Reactor Core Consisting of Standard or Optimized Fuel Assemblies,” J. Korean Nucl. Soc., 16, 3, 155 (Sep. 1984).
  • “Statistical Combination of Uncertainties,” CEN-139, Combustion Engineering (Nov. 1980).
  • H. K. KIM and S. H. CHANG, “A Procedure for Statistical Thermal Margin Analysis Using Response Surface Method and Monte Carlo Technique,” J. Korean Nucl. Soc., 18, 1, 38 (Mar. 1986).
  • R. L. SCHEAFFER and J. T. McCLAVE, Probability and Statistics for Engineers, 2nd ed., Duxbury Press, Boston (1986).
  • L. SACHS, Applied Statistics: A Handbook of Techniques, 2nd ed., Springer-Verlag, New York (1984).
  • C. L. WHEELER and D. S. ROWE, “COBRA IV: An Interim Version of COBRA for Thermal-Hydraulic Analysis Rod Bundle Nuclear Fuel Elements and Cores,” BNWL-1962, Battelle Pacific Northwest Laboratories (Mar. 1976).
  • “Sensitivity Analysis Techniques: Self-Teaching Curriculum,” NUREG/CR-2350 SAND81-1978, U.S. Nuclear Regulatory Commission (June 1982).
  • “A Comparison of Uncertainty and Sensitivity Analysis Techniques for Computer Models,” NUREG/CR-3904, SAND84-1461, U.S. Nuclear Regulatory Commission (Mar. 1985).
  • “Quantification and Uncertainty Analysis of Source Terms for Severe Accidents in Light Water Reactors [QUASAR] Part 1 – Methodology and Program Plan,” NUREG/CR-4688, BNL-NUREG-52008, Vol. 1, U.S. Nuclear Regulatory Commission (June 1986).
  • “Quantification and Uncertainty Analysis of Source Terms for Severe Accidents in Light Water Reactors [QUASAR] Part 2–Sensitivity Analysis Techniques,” NUREG/CR-4688, BNL-NUREG-52008, Vol. 2, U.S. Nuclear Regulatory Commission (Oct. 1987).
  • E. PAGE, “Approximation to the Cumulative Normal Function and Its Inverse for Use on a Pocket Calculator,” Appl. Statistics, 26 (1977).
  • R. L. IMAN and M. J. SHORTENCARIER, “A Fortran 77 Program and User’s Guide for the Generation of Latin Hypercube and Random Samples for Use with Computer Models,” NUREG/CR-3624, SAND83-2365 RG, U.S. Nuclear Regulatory Commission (1984).
  • SPSS/PC+ for the IBM PC/XT/AT, SPSS Inc. (1986)

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.