Determination of neutron flux density distribution in the core with LEU fuel IRT-4M at the training reactor VR-1

Conference · Tue Jul 15 04:00:00 EDT 2008

OSTI ID:21113484

Huml, O ^[1]

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1. Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University, Prague V Holesovickach 2, 180 00, Prague 8 (Czech Republic)

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{sub therm}). The activity of segments of irradiated wires was measured by special automatic device called 'Drat' (Wire in English). (author)

• Research Organization: Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic)
• OSTI ID: 21113484
• Report Number(s): INIS-US--08N0001
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ABSORPTION
ACTIVATION DETECTORS
CAPTURE
COMPUTER CODES
CROSS SECTIONS
DESIGN
DISTRIBUTION
FLUX DENSITY
FUEL CELLS
GOLD
HIGHLY ENRICHED URANIUM
IRRADIATION
MODERATELY ENRICHED URANIUM
NEUTRON ACTIVATION ANALYSIS
NEUTRON FLUX
NEUTRON REACTIONS
RADIOISOTOPES
VR-1 REACTOR