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U.S. Department of Energy
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NUCLEAR SUPERHEAT DEVELOPMENT PROGRAM. Twelfth Quarterly Progress Report, April-June 1962

Technical Report ·
OSTI ID:4798619
NUSU critical experiments were completed during the period and the final report on the criticai experiment program with annular multitube fuel elements is currently in preparation. Lattice parameter measurements (disadvantage factors and U/sup 238/ capture ratios) in the NUSU criticai experiment were also completed; data are included. Measured and calculated eigenvalues were found to agree within 1% for both uniform cores and cores containing heterogeneities such as water channels and cylindrical rods. Application of the engineering physics method developed for calculating control rod effectiveness to the NUSU reference design essentially suhstantiated the original plan. Results of a study using this method also re vealed that the design is very near optimum for use in a large power reactor. Development of alternate cladding materials is reported. Weld test results are reported on Inconel-to-Inconel, Hastelloy-X-to-Inconel, and stainless steel-to-Inconel. A study was initiated to evaluate the state-of-the- art of superheat reactor core physics analyses. The study was initiated to find the range of applicability of various calculation packages. Another study was initiated on the design, development, and fabrication of annular multitube fuel elements. (J.R.D.)
Research Organization:
Combustion Engineering, Inc., Windsor, Conn.; General Nuclear Engineering Corp., Dunedin, Fla.
NSA Number:
NSA-16-030070
OSTI ID:
4798619
Report Number(s):
GNEC-241
Country of Publication:
United States
Language:
English