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  7. Reyes, J. N., Jr. A Theory of Decompression of Two-phase Fluid Mixtures. Oregon State University, December 1, 1994. OSU-NE-9407.

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  9. Reyes, J. N., Jr., L. E. Hochreiter, A. Y. Lafi, and L. K. Lau. AP600 Low Pressure Integral Systems Test at Oregon State University Facility Scaling Report. Westinghouse Report WCAP-14270, January 1995.

  10. ASME NQA-1-1989. Quality Assurance Program Requirements for Nuclear Facilities. American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017.

  11. Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. Appendix B of Title 10, Part 50 of the United States Code of Federal Regulations. US Government Printing Office, issued annually.

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  13. Reyes, J. N., A. Y. Lafi, S. C. Franz and J. T. Groome. Quick-Look Report for OSU APEX NRC-1. 1-Inch Cold Leg Break with Failure of ADS Valves 1-3. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. July, 1995.

  14. Groome, J. T., J. N. Reyes and H. C. Scott. Preliminary Test Acceptance Report for NRC-5005. Cold Leg #3, ½-Inch Bottom of Pipe Break with Modified ADS Logic, NRC-5, Revision 0. APEX Long-Term Cooling Test Facility, Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. August, 1995.

  15. Reyes, J. N., A. Y. Lafi, O. L. Stevens and J. T. Groome. Quick-Look Report for OSU APEX NRC-5105. ½-Inch Break on Cold Leg #3 with Modified ADS 1-3 Logic and No CMT Refill. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. March, 1996.

  16. Groome, J. T., J. N. Reyes and H. C. Scott. Preliminary Test Acceptance Report for NRC-5007. Cold Leg #3, 1-Inch Bottom of Pipe Break with Modified ADS 1,2 and 3 Logic and No N2 Injection, NRC-7, Revision 0. APEX Long-Term Cooling Test Facility, Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. June, 1995.

  17. Reyes, J. N., A. Y. Lafi, O. L. Stevens and J. T. Groome. Quick-Look Report for OSU APEX NRC-7. 1-Inch Cold Leg Break with Modified ADS 1-3 Logic and No Nitrogen Injection. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. October, 1995.

  18. Reyes, J. N., A. Y. Lafi, S. C. Franz, S. Asghar and J. T. Groome. Quick-Look Report for OSU APEX NRC-10. 1-Inch Break on Cold Leg #3 with Failure of Three ADS 4 Valves and No CMT Refill. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. March, 1996.

  19. Reyes, J. N., A. Y. Lafi, D. A. Pimentel and J. T. Groome. Quick-Look Report for OSU APEX NRC-3. 2-Inch Cold Leg Break with Long-Term Cooling and Check Valve CSS-912 Removed. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. March, 1995.

  20. Reyes, J. N., A. Y. Lafi, S. C. Franz and J. T. Groome. Quick-Look Report for OSU APEX NRC-11. 2-Inch Cold Leg Break with Modified ADS 1-3 Logic and No CMT Refill. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. August, 1995.

  21. Reyes, J. N., A. Y. Lafi, D. A. Pimentel and J. T. Groome. Quick-Look Report for OSU APEX NRC-12. Two-Inch Break on Cold Leg #4 with Modified ADS 1-3 Logic and No CMT Refill. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. December, 1995.

  22. Yundt, M. OSU APEX Instrument Calibration Database. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon. Updated April 10, 1996.

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