Ural Federal University
3JSC «Institute of Reactor Materials»
An oral dosimeter of mixed gamma-neutron radiation for emergency exposure conditions has been developed. The energy dependence of the neutron radiation dosimeter sensitivity is close to the energy dependence of the specific effective dose per unit flux density. For neutron fields containing a significant contribution of fast neutrons, the uncertainty of the dosimeter readings is no more than 25% for the anteroposterior radiation geometry and no more than 35% for the rotation geometry. In neutron fields with a predominance of particles with thermal and intermediate energies, the dosimeter overestimates the effective radiation dose by 2.5 times for the anteroposterior geometry and 3.3 times for the rotation geometry. A staging experiment was carried out, which included placing individual dosimeters inside a canister simulating the torso of a standard adult in a neutron radiation field. The conditionally true values of the effective dose were obtained using the energy and angular distribution of the neutron radiation flux density. Differences in the dosimeter readings and the conditionally true value of the effective dose do not exceed 2.
neutron radiation, dosimeter, emergency exposure
1. Alekseev A.G., Kiryakova N.V., Kryuchkov V.P. i dr. Metrologicheskie voprosy ispol'zovaniya individual'nyh dozimetrov neytronov DVN-A-01 i DVGN-01. Preprint IFVE 2004-14. Protvino, 2004. 15 s.
2. Sannikov A.V., Lebedev V.N., Kustarev V.N. i dr. Individual'nyy dozimetr smeshannogo izlucheniya DVGN-01: razrabotka i issledovanie harakteristik. Preprint IFVE 2005-6. Protvino, 2005. 13 s.
3. Sannikov A.V., Peleshko V.N., Savickaya E.N. i dr. Dozimetr effektivnoy dozy smeshannogo izlucheniya. Preprint IFVE 2008-1. Protvino, 2008. 11 s.
4. Alekseev A.G., Lebedev V.N. Issledovanie metodicheskih voprosov ispol'zovaniya individual'nyh dozimetrov neytronov al'bednogo tipa. Preprint IFVE 2003-8. Protvino, 2003. 10 s.
5. L.G. Beskrovnaya, E.A. Goroshkova, Yu.V. Mokrov, Fizika Elementarnykh Chastits i Atomnogo Yadra, no. 3 (159), pp. 347-363, 2010.
6. M. Luszik-Bhadra, M. Boschung, M. Coeckat el. EVIDOS: Optimisation of Individual Monitoring in Mixed Neutron/Photon Fields at Workplaces of the Nuclear Fuel Cycle.
7. MU 2.6.5.028-2016. Opredelenie individual'nyh effektivnyh i ekvivalentnyh doz i organizaciya kontrolya professional'nogo oblucheniya v usloviyah planiruemogo oblucheniya. Obschie trebovaniya.
8. A. Ferrari, P.R. Sala, A. Fasso, J. Ranft, «FLUKA: a multi-particle transport code», CERN-2005-10, 2005, INFN/TC 05/11, SLAC-R-773.
9. G. Battistoni, S. Muraro, P.R. Sala, F. Cerutti, A. Ferrari, S. Roesler, A. Fasso, J. Ranft, «The FLUKA code: Description and benchmarking», Proceedings of the Hadronic Shower Simulation Workshop 2006, Fermilab 6-8 September 2006, M. Albrow, R. Raja eds., AIP Conference Proceeding 896, 31-49, 2007.
10. Mezhdunarodnoe agentstvo po atomnoy energetike, Ocenka professional'nogo oblucheniya ot vneshnih istochnikov ioniziruyuschego oblucheniya. Seriya norm bezopasnosti N RS-G-1.3, MAGATE, Vena, 1999.
11. O.F. Naismith, B.R.L. Siebert, «A database of neutron spectra, instrument response functions and dosimetric conversion functions for radiation protection applications», Radiat. Prot. Dosim., no. 70, pp. 241-246, 1997.
12. H.J. Delafield, C.A. Perks, «Neutron spectrometry and dosimetry measurements made at nuclear power stations with derived dosemeter responses», Radiat. Prot. Dosim., no. 44, pp. 227-232, 1992.
13. D.T. Bartlett, A.R. Britcher, A.G. Bardell, D.J. Thomas, I.F. Hudson, «Neutron spectra, radiological quantities and instrument and dosemeter responses at a MAGNOX reactor and a fuel reprocessing installation», Radiat. Prot. Dosim., no. 44, pp. 233-238, 1992.
14. M. Pyshkina, A. Vasilyev, A. Ekidin et al. Development and testing of a neutron radiation spectrometer in fields of radionuclide sources. AIP Conference Proceedings 2163 (1).
15. M. Pyshkina, A. Vasilyev, A. Ekidin et al., Study of neutron energy and directional distribution at the Beloyarsk NPPselected workplaces. Nuclear Engineering and Technology. URL: https://doi.org/10.1016/j.net (data obrascheniya: 15.10.2020).
16. MU 2.6.5.052-2017. Dozimetriya. Opredelenie individual'noy effektivnoy dozy neytronnogo izlucheniya.
