Analysis of the VENUS-3 experiments

Conference · Mon Jan 01 04:00:00 EST 1990

OSTI ID:6890103

Maerker, R E ^[1]; D'hondt, P; Leenders, L; Fabry, A ^[2]

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1. Oak Ridge National Lab., TN (USA)
2. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)

The results of applying a hybrid superposition-synthesis calculational method to a mockup of a three-dimensional geometry involving a partial length shield assembly 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 usually to within measurement uncertainties estimated at around 5%, 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 suggest a solution to the problem of predicting pressure vessel fluence in reactors modified by these partial-length shield assemblies may already exist. 7 refs., 2 figs., 1 tab.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6890103
• Report Number(s): CONF-900814-2; ON: DE90010708
• Country of Publication: United States
• Language: English

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ALUMINIUM
CONTAINERS
DATA
DOSIMETRY
ELEMENTS
EXPERIMENTAL DATA
INDIUM
INFORMATION
MATHEMATICAL MODELS
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NICKEL
NUMERICAL DATA
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTORS
SHIELDING
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS