Heat removal verification tests using concrete casks under normal condition

The effect of prior cold work on the chloride stress corrosion cracking of 304L austenitic stainless steel under atmospheric conditions

“…It is worth noting that dry storage containers, for nuclear fuel, are usually in contact with the atmosphere, without any filtering of the sea air [8][9][10][11]. The temperatures will also slowly change during their design lives as the decay heat from the fuel exponentially decays [9,12]. The containers surfaces will be reasonably hot at the start of life (~100 °C) [10,12], and, considering the typical burn-up of a LWR and its decay heat, transition through all temperatures until reaching temperatures of ~40°C at 100 years [13].…”

“…The temperatures will also slowly change during their design lives as the decay heat from the fuel exponentially decays [9,12]. The containers surfaces will be reasonably hot at the start of life (~100 °C) [10,12], and, considering the typical burn-up of a LWR and its decay heat, transition through all temperatures until reaching temperatures of ~40°C at 100 years [13]. As the temperature decreases below 100 °C, progressively more salt will be able to deposit on the cask surface and the potential for SCC will arise [14].…”

Simulation of thermal state of containers with spent nuclear fuel: multistage approach

“…The Grashof number [17,19] reaches up to 3.54°10 6 (the average distance between the inner basket surface and fuel assemblies is used as reference parameter). The maximum temperatures in each fuel assembly are given in Table II.…”

“…Because of slow changes of decay heat of spent fuel assemblies during the storage, the modelling of thermal processes inside containers with spent nuclear fuel is generally accepted to carry out in the quasi-static formulation [5][6][7][8][9][10]. The system of quasi-static differential equations that describes the conjugate heat transfer problem consists of the following equations [15][16][17]: -Continuity equation:…”

“…Unfortunately, all existing known works in field of thermal simulation at dry spent nuclear fuel storage have some limitations. For example, the moving of filled medium inside storage basket is not considered [5,6], or the problem was solved in two-dimensional formulation [7][8][9]. There are some researches that use simplified geometry structure and equivalent thermal properties for CFD simulation [9,10], but this way of investigations does not allow to obtain the detailed information about thermal processes inside storage containers even with usage of CFD methodology.…”