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Updated: Jul 14, 2026
09:18
Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident
Published on: December 14, 2017
Dosimetry at an interim storage for spent nuclear fuel
M Králík1, V Kulich, J Studeny
1Czech Metrology Institute, IIR, Radiova 1, CZ-102 00 Prague 10, Czech Republic. mkralik@cmi.cz
Radiation Protection Dosimetry
|May 29, 2007
Summary
Spent nuclear fuel at the Dukovany plant was measured for radiation. Neutron-photon fields around storage casks were characterized to assess radiation doses.
Area of Science:
- Nuclear Engineering
- Radiation Protection
- Health Physics
Background:
- The Dukovany nuclear power plant began operation in 1985.
- Spent fuel from 1985-2005 is stored in dry interim storage casks.
- Storage casks are designed for VVER 440 reactor fuel assemblies.
Purpose of the Study:
- To characterize neutron-photon mixed fields around spent fuel storage casks.
- To measure ambient dose equivalent from mixed radiation fields.
- To analyze neutron spectra for dose assessment.
Main Methods:
- Ambient dose equivalent measured using standard area dosemeters.
- Neutron spectra measured with a Bonner sphere spectrometer.
- Derivation of neutron ambient dose equivalent from measured spectra.
Main Results:
- Characterization of mixed neutron-photon fields around CASTOR-440/84 casks.
- Measurement of ambient dose equivalent using standard dosimetry.
- Determination of neutron spectra and associated dose equivalents.
Conclusions:
- The study successfully characterized radiation fields around spent fuel storage.
- Dosimetry measurements provide data for radiation protection assessments.
- Neutron spectral analysis enhances understanding of radiation exposure.
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