Research Article |
Corresponding author: Artem Z. Gayazov ( gaz@sosny.ru ) Academic editor: Yury Korovin
© 2023 Artem Z. Gayazov, Oleg Z. Gaiazov, Viacheslav Yu. Kozlov, Sergey V. Pavlov, Aleksandr A. Samsonov.
This is an open access article distributed under the terms of the Creative Commons Attribution License (CC BY 4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.
Citation:
Gaiazov AZ, Gaiazov OZ, Kozlov VYu, Pavlov SV, Samsonov AA (2023) Calculation and experimental studies for the spent nuclear fuel shipping cask sealing assembly. Nuclear Energy and Technology 9(3): 183-187. https://doi.org/10.3897/nucet.9.113520
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One of the safety requirements regarding the shipping cask for spent nuclear fuel is that its leak-tightness should be maintained by preserving the cask body structural integrity and the sealing system tightness under normal and accident transportation conditions. The cask under design has a cylindrical process penetration (port) in its bottomб which is sealed using a plug with a radial seal composed of two rubber O-rings. The cask sealing assembly design was justified by the ANSYS LS-DYNA code calculation results. In particular, the strains of the cask components were calculated when dropped from a height of 1 m with the sealing assembly hitting a vertical bar. The cask was concluded to be leak-tight or leaky based on the strain nature and amount. To verify the adequacy of the results, computer-aided and realistic simulations were undertaken with a 1/2.5 scale mockup cask dropped on a bar from a height of 1 m. The computational and experimental results show a good agreement in terms of the impact response accelerations (overloads) for the mockup cask and bar collision and in terms of the plastic strains for the key components of the mockup bottom port sealing assembly. This proves the adequacy of the numerical cask model that has been developed and the efficiency of the LS-DYNA simulations. The inner rubber O ring compression is reduced by the plastic strains in the cask’s bottom port area, leading to a loose inner radial seal, as shown by the calculations. But the outer seal remains leak-tight, ensuring so the mockup cask tightness. The physical test results have also confirmed that the mockup cask remains leak-tight.
cask, leak-tightness, tests, numerical simulation, sealing assembly, strain, seal
To design a new cask for transportation of irradiated nuclear fuel, the developers are guided by respective safety regulations (NP-053-16, SSR-6, GOST R 51964-2002, PBYa-06-09-2016, SanPiN 2.6.1.1281-03, SP 2.6.1.2612 10, GOST 9833-73). The ways and methods to justify safety of the new cask structure are strictly regulated and may include both experiments and calculations. They aim to describe how the cask structure and content will behave during routine, normal, and accident conditions of transport.
One of the cask structural safety indicators is that its leak-tightness is maintained, which is achieved by preserving the cask body integrity and the leak-tightness of the cask’s detachable joints. When justifying the cask structural safety by calculations, one can find out if the detachable joints are leak-tight from the results of analyzing the strain of the detachable joint parts and the state of the sealing components (gaskets, seals, etc.), primarily in accidents, such as a drop onto a rigid surface from a regulatory height, a drop on a vertical bar, or a fire (NP-053-16, SSR-6).
The adequacy of such approach to justifying the cask leak-tightness can be proved by full-scale simulations using scale mockups (GOST 9833-73) of the cask under development or a part of it with the sealing assembly of interest.
This paper presents results of computational and experimental studies into the strain and leak-tightness of the cask bottom penetration sealing assembly which is a plug with a radial seal during the drop tests with the mockup cask dropped on a vertical bar from a height of 1 m.
This cask for shipping the nuclear reactor irradiated fuel elements has a cylindrical penetration in its bottom to facilitate withdrawal of the cask content by pushing it through the upper throat and water drainage when drying the full cask (Fig.
A strain to components of the cask bottom penetration sealing assembly can cause distance S to increase, this resulting in a smaller rubber O-ring compression in the radial seal and in the cask leak-tightness being lost.
The most dangerous strains to the cask’s sealing assembly components are likely to occur as the result of accidents in the process of transportation simulated specifically, as defined in regulatory documents NP-053-16 and SSR-6, by dropping the cask with its bottom hitting a bar (Fig.
A strain to the cask bottom penetration sealing assembly was simulated by a numerical method using a multipurpose code, LS-DYNA. To verify the obtained results, numerical and full-scale simulations were undertaken with a 1/2.5 scale cask mockup dropped on a vertical bar of the diameter 60 mm from a height of 1 m.
The mockup cask for numerical and full-scale simulations is a steel cylinder with a diameter of 316 mm, a length of 2197 mm, and a weight of 1217 kg. Its inner space is filled with helium and sealed at the bottom with a plug and a radial seal (two O-rings of standard size 020-024-25-2 (GOST 9833-73) made of rubber mix under TU 2531-002-2894 3826-009. The cask bottom and the plug are made of 12Cr18Ni10Ti steel (GOST 5632-2014). The plug is attached to the cask bottom with eight M6 bolts of 14Cr17Ni2-grade steel (GOST 5632-2014).
The seal leak-tightness is controlled by the mass spectrometer method (GOST R 50.05.01-2018) based on the helium pressure drop rate inside the mockup cask; it amounts to 3.9·10-7 Pa·m3·s-1 in the initial (pre-test) state which is several times smaller than the allowable value of 1·10-6 Pa·m3·s-1 adopted for the design.
The cask mockup and bar collision was simulated numerically using a code for analyzing highly linear dynamic processes in solid body mechanics problems, ANSYS LS-DYNA (
The simulation of the cask mockup collision on a vertical bar involved several stages:
The 3D geometrical model of the mockup cask was made in accordance with the cask design documentation. The finite element mesh was built with a built-in mesh generator of the ANSYS code’s Workbench pre-postprocessor (Barulina MA 2012). A hexahedral Lagrange mesh was used, and the total number of elements in the computational model was nearly 2 million.
The numerical simulation of the mockup cask collision on a vertical bar used the following assumptions:
To take into account the own weight of all computational model parts when simulating the mockup cask drop on a bar, all nodes in the finite element mesh were in the gravity acceleration field. As the initial condition, all cask model nodes were assigned initial rate V0 at the time the collision with the bar starts (t0 = 0), which is computed from the energy conservation law:
V 0 = (2·g·h)1/2 ≈ 4.43 m/s, (1)
where g = 9.806 m/s2 is the gravity acceleration; and h = 1 m is the height of the drop on the bar.
The stress-strained state of the computational model was analyzed as of the time the cask starts to bounce off the bar surface.
A dedicated bench (Fig.
The numerical simulation results have agreed satisfactorily with full-scale simulation results.
Fig.
Fig.
Therefore, the coned shape of the bottom penetration that results from the mockup cask impact on the bar leads to a reduction in the rubber O-ring compression forces expected to lead, in turn, to the loss of the mockup cask integrity.
Fig.
The figure demonstrates that the internal seal has fully lost its leak-tightness since the penetration surface does not exert any pressure on the O-ring. The gap between the O-ring and the sealing surfaces is ~0.6 mm, while the external gasket (as the calculation results show) is expected to remain leak-tight since the three above-mentioned criteria are fulfilled.
This conclusion obtained as the result of the computer simulation was confirmed experimentally by measuring the helium pressure drop rate inside the mockup cask after the drop tests. The helium pressure drop rate was 3.9·10-7 Pa·m3·s-1, which coincides with the pre-test pressure drop rate and indicates that the mockup cask remains leak tight.
After the mockup cask drop tests, the cask bottom penetration sealing assembly was dismantled, and the dimensions of the plug components (Fig.
An analysis of the data in the Table
Typical dimensions of the mockup cask end components after the drop on the bar from a height of 1 m obtained from the calculation and tests
Dimension as in Fig. |
Dimension value before testing (mm) | Experiment | Calculation | Relative deviation of calculated value from dimension value after testing (%) | ||
---|---|---|---|---|---|---|
Dimension value after testing (mm) | Change in value after testing(mm) | Dimension value before testing (mm) | Change in value after testing (mm) | |||
(a) | 20.3 | 20.3 | 0.00 | 20.3 | 0.00 | 0 |
(b) | 23.8 | 23.82 | +0.02 | 23.92 | +0.12 | 0.42 |
(c) | 6.0 | 6.0 | 0.00 | 6.0 | 0.00 | 0 |
(d) | 5.0 | 5.0 | 0.00 | 5.0 | 0.00 | 0 |
(e) | 11.0 | 16.8 | +5.80 | 19.52 | +8.52 | 16.19 |
(f) | 24.0 | 23.9 | -0.10 | 23.92 | -0.08 | 0.08 |
(g) | 24.0 | 28.3 | +4.30 | 28.92 | +4.92 | 2.19 |
The ANSYS LS-DYNA code was used to simulate numerically the drop of a spent nuclear fuel cask mockup on a vertical bar from a height of 1 m. Specifically, the collision of the mockup cask penetration sealing assembly on the bar was simulated, which is the most dangerous event during drop tests leading potentially to the loss of the cask pressure.
To verify adequacy of the numerical model and the drop test computer simulation results, a mockup cask was manufactured with the sealing assembly under study. The full-scale tests included the mockup cask dropping on a vertical bar from a height of 1 m with its sealing assembly hitting the bar. The comparison between the calculated and experimental data resulted in the following conclusions: