Potential of application of IRT-T research reactor as the solution of the problem of graphite radwaste disposal
Aspects of handling irradiated graphite during decommissioning uranium-graphite reactors (UGR) of different types were investigated. It was demonstrated that handling reactor graphite is complicated by the presence in the composition of graphite of long-lived radionuclides, especially 14C, which may...
Main Authors: | Alexander Pavliuk, Sergey Kotlyarevskiy, Evgeny Bespala, Yuliya Bespala |
---|---|
Format: | Article |
Language: | English |
Published: |
National Research Nuclear University (MEPhI)
2018-11-01
|
Series: | Nuclear Energy and Technology |
Online Access: | https://nucet.pensoft.net/article/30771/download/pdf/ |
Similar Items
-
About chemical form and binding energy of 14C in irradiated graphite of uranium-graphite nuclear reactors
by: Evgeny V. Bespala, et al.
Published: (2018-10-01) -
Heat Transfer During Evaporation of Cesium From Graphite Surface in an Argon Environment
by: Bespala Evgeny, et al.
Published: (2016-01-01) -
Interaction of 137Cs with Sumedang Clay as Natural Barrier of Radwaste Disposal
by: B. Setiawan, et al.
Published: (2019-02-01) -
Modelling migration process of long-lived radionuclides from graphite radioactive waste
by: Alexander Olegovich Pavlyuk, et al.
Published: (2017-08-01) -
Modelling migration process of long-lived radionuclides from graphite radioactive waste
by: Alexander Olegovich Pavlyuk, et al.
Published: (2017-08-01)