
doi: 10.2172/814306
Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of the VVER-1000 reactor are considered in the view of 3 MOX LTAs introduction into the core. The precise code MCU that realizes the Monte Carlo method is used for calculations.
Mixed Oxide Fuels, Radiation Protection, 42 Engineering, Casks, Storage, Transport, Novovoronezh-5 Reactor, Monte Carlo Method
Mixed Oxide Fuels, Radiation Protection, 42 Engineering, Casks, Storage, Transport, Novovoronezh-5 Reactor, Monte Carlo Method
| selected citations These citations are derived from selected sources. This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically). | 0 | |
| popularity This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network. | Average | |
| influence This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically). | Average | |
| impulse This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network. | Average |
