Analysis of the VENUS-3 experiments

Technical Report · Tue Aug 01 04:00:00 EDT 1989

OSTI ID:5620039

Maerker, R E

The results of applying a hybrid superposition-synthesis calculational method to a mockup of a three-dimensional geometry involving a partial length shield assembly (PLSA) at the VENUS-3 facility in Mol, Belgium, are described. Comparisons of transport calculations using the method and many measurements involving nickel, indium, and aluminum dosimeters indicate agreement generally to within five percent if effects of inaccuracies in the dosimeter cross sections are minimized and proper orientation of the coordinate system used in the synthesis procedure is observed. These conclusions bode well for the success of this method in solving neutron transport problems involving the use of PLSAs in light water reactors to reduce core leakage in pressurized thermal shock programs. A second report describing the experimental details of the measurements will serve as companion documentation to this one and will be furnished by the Studiecentrum voor Kernenergie/Centre d'Etude de l'Energie Nucleaire, Mol, Belgium. 12 refs., 4 figs., 22 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5620039
• Report Number(s): NUREG/CR-5338; ORNL/TM-11106; ON: TI89016556
• Country of Publication: United States
• Language: English

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