Document: NUREG-0800
Document ID: 54e3d49d-900d-4fe8-9297-2fc04501e4e0
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340664.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
e contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 2. "General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application," NEDO-10958, General Electric Company (1973). 3. F. F. Cadek, F. E. Motley, and D. P. Dominicis, "Effect of Axial Spacing on Interchannel Thermal Mixing with the R Mixing Vane Grid," WCAP-7941-L (proprietary), Westinghouse Electric Corp'ration, June 1972. 4. F. E. Motley and F. F. Cadek, "DNB Test Results for New Mixing Vane Grids (R)," WCAP-7695-L (proprietary), Westinghouse Electric Corporation, July 1972. 4.4-8 Rev. 1 - July 1981 5. F. E. Motley and F. F. Cadek, "Application of Modified Spacer Factor to L Grid Typical and Cold Wall Cell DNB," WCAP-7988, Westinghouse Electric Corporation, October 1972. (See also WCAP-8030.) 6. J. S. Gellerstedt, R. A. Lee, W. J. Oberjohn, R. H. Wilson, and L. J. Stanek? "Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water,' in "Two-Phase Flow and Heat Transfer in Rod Bundles," American Society of Mechanical Engineers, New York (1969). (See also BAW-10000 and BAW-10036.) 7. L. S. Tong, "Prediction of Departure from Nucleate Boiling for an Axially Non-Uniform Heat Flux Distribution," Journal of Nuclear Energy, Vol. 21, 241-248 (1967). 8. "TEMP - Thermal Enthalpy Mixing Program," BAW-10021, Babcock and Wilcox Company, April 1970. 9. H. Chelemer, P. T. Chu, and L. E. Hochreiter, "THINC-IV-An Improved Program for Thermal-Hydraulic Analysis of Rod Bundle Cores," WCAP-7956, Westinghouse Electric Corporation, June 1973. (See also WCAP-7359-L and WCAP-7838.) 10. B. C. Slifer and J. E. Hench, "Loss of Coolant Accident and Emergency Core Cooling Models for General Electric Boiling Water Reactors, NEDO-10329, Appendix C, General Electric Company, April 1971. 11. J. Duncan and P. W. Marriott, "General Electric Company Analytical Model for Loss of Coolant Accident Analysis in