C. B. Davis

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Reactor Pressure Vessel Temperature Analysis for Prismatic and Pebble-Bed VHTR Designs

H. D. Gougar, C. B. Davis, 2006 .

Thermal-hydraulic analyses of overcooling sequences for the H. B. Robinson Unit 2 pressurized thermal shock study

C. B. Davis, C. D. Fletcher, D. M. Ogden, 1985 .

Effects of control system failures on transients and accidents at a 3-loop Westinghouse pressurized water reactor. Main report. Volume 1

C. B. Davis, D. M. Ogden, S. J. Bruske, 1985 .

Development of HyPEP, A Hydrogen Production Plant Efficiency Calculation Program

C. B. Davis, W. J. Lee, C. H. Oh, 2006 .

Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR]

S. R. Behling, C. B. Davis, M. T. Hsu, 1981 .

Post-test analysis of international standard problem 10 using RELAP4/MOD7. [PWR]

S. R. Behling, C. B. Davis, A. C. Peterson, 1981 .

Effects of control system failures on transients and accidents at a 3-loop Westinghouse pressurized water reactor. Volume 2. Appendices

C. B. Davis, D. M. Ogden, S. J. Bruske, 1985 .

RELAP5/MOD2 assessment calculation of Semiscale Test S-UT-8

C. B. Davis, D. M. Ogden, 1984 .

Transient Analysis Needs for Generation IV Reactor Concepts

C. B. Davis, L. J. Siefken, Edwin Allan Harvego, 2002 .

RELAP5 thermal-hydraulic analyses of pressurized thermal shock sequences for the H. B. Robinson Unit 2 pressurized water reactor

C. B. Davis, C. D. Fletcher, Bolander, 1985 .

Applicability of RELAP5-3D for Thermal-Hydraulic Analyses of a Sodium-Cooled Actinide Burner Test Reactor

C. B. Davis, C. Davis, 2006 .

Evaluation of integral continuing experimental capability (CEC) concepts for light water reactor research: PWR scaling concepts

C. B. Davis, T. K. Larson, G. E. McCreery, 1987 .