Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor
| Autor: | Milan P. Pešić, Marko M. Ninkovic |
|---|---|
| Rok vydání: | 1999 |
| Předmět: |
Epidemiology
020209 energy Health Toxicology and Mutagenesis Astrophysics::High Energy Astrophysical Phenomena Physics::Medical Physics Yugoslavia 02 engineering and technology 01 natural sciences 010305 fluids & plasmas law.invention Physics::Geophysics Nuclear physics nuclear accidents Neutron flux law Nuclear Reactors 0103 physical sciences 0202 electrical engineering electronic engineering information engineering Dosimetry Humans Radiology Nuclear Medicine and imaging Neutron Physics::Chemical Physics dose absorbed Radiometry Monte Carlo Power density Neutrons Chemistry Air Radiochemistry gamma radiation Gamma ray Nuclear reactor Gamma Rays Absorbed dose Health physics Radioactive Hazard Release Monte Carlo Method Health Physics |
| Zdroj: | Health Physics |
| Popis: | The RE experimental reactor has operated at Vinca Institute of Nuclear Sciences since the end of April 1958. Tn this paper, neutron and gamma-ray spectra and corresponding dose quantities near the reactor, calculated by using the MCNP(TM) code, are compared to the measured values during the Third International Intercomparison Experiment on Nuclear Accident Dosimetry carried out at the RE reactor in 1973. Discrepancies in the correlation declared power of the reactor-dose rates are found. Good agreements are obtained between measured and calculated neutron and gamma-ray spectra, and corresponding absorbed doses in air, but only after the reactor declared power is multiplied by a correction factor, determined in this study. |
| Databáze: | OpenAIRE |
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