CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS

By calculation methods, the dose rate of the radioactive waste, behind concrete protection, was evaluated in current work. Parameters, which were taken in account in the calculations, are geometry of the protection shell, size of the source and its isotopic composition. As model geometrical paramete...

Full description

Bibliographic Details
Main Authors: M. S. Malovytsia, S. A. Pismenetskiy, G. S. Hrushch, O. P. Shchus
Format: Article
Language:English
Published: V.N. Karazin Kharkiv National University Publishing 2018-06-01
Series:East European Journal of Physics
Subjects:
Online Access:https://periodicals.karazin.ua/eejp/article/view/10747
id doaj-b8528f57d19547278068ce9a5a1ef6f5
record_format Article
spelling doaj-b8528f57d19547278068ce9a5a1ef6f52020-11-24T21:33:11ZengV.N. Karazin Kharkiv National University PublishingEast European Journal of Physics2312-43342312-45392018-06-0152626710.26565/2312-4334-2018-2-0810747CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMSM. S. Malovytsia0S. A. Pismenetskiy1G. S. Hrushch2O. P. Shchus3V.N. Karazin Kharkiv National University 4 Svobody Sq., Kharkov, 61022, UkraineV.N. Karazin Kharkiv National University 4 Svobody Sq., Kharkov, 61022, UkraineV.N. Karazin Kharkiv National University 4 Svobody Sq., Kharkov, 61022, UkraineV.N. Karazin Kharkiv National University 4 Svobody Sq., Kharkov, 61022, UkraineBy calculation methods, the dose rate of the radioactive waste, behind concrete protection, was evaluated in current work. Parameters, which were taken in account in the calculations, are geometry of the protection shell, size of the source and its isotopic composition. As model geometrical parameters the spent fuel assembly’s size and thickness of the concrete wall of the ventilated storage container (VSC)-VVER were taken. The computer program that does numerical calculation was composed in the Wolfram Alpha environment. The program takes into account change of the isotopic composition and spectra of gamma-radiation with time. Calculation results were compared to the known data on the spent nuclear fuel heat dissipation. Approach described in this work can be used for fast estimation of change in the quality of radioactive waste (RAW) in the long-term storage without recycling, for different initial isotopic composition. Obtained results were analyzed on the matter of change in gamma-radiation of RAW.https://periodicals.karazin.ua/eejp/article/view/10747radioactive waste, dose rate, long terms storage, concrete protection, isotopic composition
collection DOAJ
language English
format Article
sources DOAJ
author M. S. Malovytsia
S. A. Pismenetskiy
G. S. Hrushch
O. P. Shchus
spellingShingle M. S. Malovytsia
S. A. Pismenetskiy
G. S. Hrushch
O. P. Shchus
CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS
East European Journal of Physics
radioactive waste, dose rate, long terms storage, concrete protection, isotopic composition
author_facet M. S. Malovytsia
S. A. Pismenetskiy
G. S. Hrushch
O. P. Shchus
author_sort M. S. Malovytsia
title CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS
title_short CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS
title_full CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS
title_fullStr CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS
title_full_unstemmed CHANGE OF QUALITY OF A RADIOACTIVE WASTE UNDER LONG STORE TERMS
title_sort change of quality of a radioactive waste under long store terms
publisher V.N. Karazin Kharkiv National University Publishing
series East European Journal of Physics
issn 2312-4334
2312-4539
publishDate 2018-06-01
description By calculation methods, the dose rate of the radioactive waste, behind concrete protection, was evaluated in current work. Parameters, which were taken in account in the calculations, are geometry of the protection shell, size of the source and its isotopic composition. As model geometrical parameters the spent fuel assembly’s size and thickness of the concrete wall of the ventilated storage container (VSC)-VVER were taken. The computer program that does numerical calculation was composed in the Wolfram Alpha environment. The program takes into account change of the isotopic composition and spectra of gamma-radiation with time. Calculation results were compared to the known data on the spent nuclear fuel heat dissipation. Approach described in this work can be used for fast estimation of change in the quality of radioactive waste (RAW) in the long-term storage without recycling, for different initial isotopic composition. Obtained results were analyzed on the matter of change in gamma-radiation of RAW.
topic radioactive waste, dose rate, long terms storage, concrete protection, isotopic composition
url https://periodicals.karazin.ua/eejp/article/view/10747
work_keys_str_mv AT msmalovytsia changeofqualityofaradioactivewasteunderlongstoreterms
AT sapismenetskiy changeofqualityofaradioactivewasteunderlongstoreterms
AT gshrushch changeofqualityofaradioactivewasteunderlongstoreterms
AT opshchus changeofqualityofaradioactivewasteunderlongstoreterms
_version_ 1725954409413738496