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Design Features and Administrative Limits
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Guidelines For Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities
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Appendices - s3007cn10060


DOE-STD-3007-93
1.
Idaho Chemical Processing Plant Safety Document, Underwater Fuel Storage, Section
4.6.
2.
Staff of Technical Applications, Computing and Telecommunications Division at ORNL,
SCALE: A Modular Code System for Performing Standardized Computer Analysis for
Licensing Evaluations, Vols. 1-3, CCC-545.
3.
J. I. Hagen and R. W. Goin (Argonne National Laboratory), BORAX V Neutronics,
ANL-6964, December 1965.
4.
W. C. Kramer and C. H. Bean (Argonne National Laboratory), Fabrication of UO2-
Stainless Steel Dispersion Fuel For BORAX V Nuclear Superheat, ANL-6649, December
1963.
5.
(Argonne National Laboratory), Design and Hazards Summary Report Boiling Reactor
Experiment V (BORAX V), ANL-6302, May 1961.
6.
BORAX-V Project Staff (Argonne National Laboratory), Experiments with Central
Superheater Core CSH-1, ANL-6961, January 1965.
7.
K. E. Plumlee, Q. L. Baird, G. S. Stanford, and P. I. Amundson (Argonne National
Laboratory), Critical Experiment with BORAX V Internal Superheater, ANL-6691,
December 1965.
8.
E. B. Johnson and R. K. Reedy (Oak Ridge National Laboratory), Critical Experiments
With SPERT-D Fuel Elements, ORNL-TM-1207, July 14, 1965.
9.
B. M. Palmer, C. Crawford, Validation of the CSAS25 Module of Scale, Part I: Highly
Enriched Uranium Solutions, CSS-91-005, Westinghouse Idaho Nuclear Company, July
1991.
10.
B. M. Palmer, C. Crawford, Validation of the CSAS25 Module of Scale, Part II: Highly
Enriched Uranium Solutions, CSS-91-013, Westinghouse Idaho Nuclear Company,
September 1991.
11.
B. M. Palmer, C. Crawford, Validation of the CSAS25 Module of Scale, Part III: Highly
Enriched Uranium Solutions, CSS-91-015, Westinghouse Idaho Nuclear Company,
October 1991.
12.
Letter from J. E. Tanner to G. T. Paulson, Subject: "Best CPP Concrete Formula," JET-
03-91, September 9, 1991.
2-28


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