Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor
Apstrakt
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.
Ključne reči:
Monte Carlo / nuclear accidents / dose, absorbed / gamma radiationIzvor:
Health Physics, 1999, 77, 3, 276-281
DOI: 10.1097/00004032-199909000-00005
ISSN: 0017-9078; 1538-5159
PubMed: 10456498
WoS: 000082009800005
Scopus: 2-s2.0-0032588299
Kolekcije
Institucija/grupa
VinčaTY - JOUR AU - Pešić, Milan P. AU - Ninković, Marko M. PY - 1999 UR - https://vinar.vin.bg.ac.rs/handle/123456789/2266 AB - 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. T2 - Health Physics T1 - Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor VL - 77 IS - 3 SP - 276 EP - 281 DO - 10.1097/00004032-199909000-00005 ER -
@article{ author = "Pešić, Milan P. and Ninković, Marko M.", year = "1999", abstract = "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.", journal = "Health Physics", title = "Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor", volume = "77", number = "3", pages = "276-281", doi = "10.1097/00004032-199909000-00005" }
Pešić, M. P.,& Ninković, M. M.. (1999). Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor. in Health Physics, 77(3), 276-281. https://doi.org/10.1097/00004032-199909000-00005
Pešić MP, Ninković MM. Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor. in Health Physics. 1999;77(3):276-281. doi:10.1097/00004032-199909000-00005 .
Pešić, Milan P., Ninković, Marko M., "Comparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactor" in Health Physics, 77, no. 3 (1999):276-281, https://doi.org/10.1097/00004032-199909000-00005 . .