2007 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

Determination of Neutron Flux Density Distribution in the Core with LEU Fuel IRT-4M at the Training Reactor VR-1

O. Huml
Department of Nuclear Reactors
Faculty of Nuclear Sciences and Physical Engineering
Czech Technical University in Prague
V Holesovickach 2, 180 00, Prague 8, Czech Republic

ABSTRACT

The objective of this work was to determine the neutron flux density distribution in various places of the training reactor VR-1 Sparrow. This experiment was performed on the new core design C1, composed of the new low-enriched uranium fuel cells IRT-4M (19.7 %). This fuel replaced the old high-enriched uranium fuel IRT-3M (36 %) within the framework of the RERTR Program in September 2005. The measurement used the neutron activation analysis method with gold wires. The principle of this method consists in neutron capture in a nucleus of the material forming the activation detector. This capture can change the nucleus in a radioisotope, whose activity can be measured. The absorption cross-section values were evaluated by MCNP computer code. The gold wires were irradiated in seven different positions in the core C1. All irradiations were performed at reactor power level 1E8 (1 kW_therm). The activity of segments of irradiated wires was measured by special automatic device called “Drat” (Wire in English).

 

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