References - s3007cn10059

DOE-STD-3007-93

Idaho Chemical Processing Plant Safety Document, Underwater Fuel Storage, Section

4.6.

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.

J. I. Hagen and R. W. Goin (Argonne National Laboratory), BORAX V Neutronics,

ANL-6964, December 1965.

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.

(Argonne National Laboratory), Design and Hazards Summary Report Boiling Reactor

Experiment V (BORAX V), ANL-6302, May 1961.

BORAX-V Project Staff (Argonne National Laboratory), Experiments with Central

Superheater Core CSH-1, ANL-6961, January 1965.

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.

E. B. Johnson and R. K. Reedy (Oak Ridge National Laboratory), Critical Experiments

With SPERT-D Fuel Elements, ORNL-TM-1207, July 14, 1965.

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.

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