Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2

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The hydrodynamics code BOCH was used to obtain the relationship between a large number of variables such as voids, flux, pin spacing, power density, and pressure for VMR lattices. Based upon these relationships, a reference core design was selected for examination, using the integrated physics and hydrodynamics analytical modeis. The analog representations of the VMR core kinetics describing the individual blocks of a model block diagram were completed. A simplified core physics analysis was completed, and design parameters were established. An analysis of these parameters using PUREE' was initiated. The first three energy groups and the thermal group were compared … continued below

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26 pages

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Creator: Unknown. November 30, 1959.

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  • Advanced Technology Laboratories
    Publisher Info: Advanced Technology Labs., Div. of American-Standard, Mountain View, Calif.
    Place of Publication: Mountain View, California

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Description

The hydrodynamics code BOCH was used to obtain the relationship between a large number of variables such as voids, flux, pin spacing, power density, and pressure for VMR lattices. Based upon these relationships, a reference core design was selected for examination, using the integrated physics and hydrodynamics analytical modeis. The analog representations of the VMR core kinetics describing the individual blocks of a model block diagram were completed. A simplified core physics analysis was completed, and design parameters were established. An analysis of these parameters using PUREE' was initiated. The first three energy groups and the thermal group were compared with experimental lattices. Portions of the developed code are being used to analyze the critical experiment design and to investigate the reference core design. The critical experiment facility design is about 60% complete. The preliminary program which has been planned includes consideration of the number, kinds, and schedule of experiments to be performed. Portions of the PUREE' physics analysis are being used to generate information for the hazards repert on the critical experiment. (For preceding period see ATL-A-100.) (J.R.D.)

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26 pages

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Project Agreement No. 3. Orig. Receipt Date: 31-DEC-60

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  • November 30, 1959

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Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2, report, November 30, 1959; Mountain View, California. (https://digital.library.unt.edu/ark:/67531/metadc868253/: accessed December 14, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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