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

Now only one Dry Storage Facility of Spent Nuclear Fuel (DSFSNF) is operated in Ukraine. It is the facility on Zaporizhska NPP. Many different thermal investigations were done for ventilated containers of DSFSNF. In this study the generalization of scientific approaches to the thermal safety assessment are carried out. The multi-stage approach to the definition of thermal state of containers' group, single container, spent fuel assemblies and fuel rods was developed. Detailed thermal profiles of spent fuel assemblies inside storage container were calculated. With usage of multi-stage approach the thermal simulations of the influence of outer factors onto thermal state of containers was carried out. Results of thermal investigations were generalized and factors, which are influence on thermal state of containers, are detected. The method of spent nuclear fuel thermal state prediction and suggestion for improving the system of thermal monitoring were proposed.

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“…At the next level of calculation procedure this part is simulated in detailed structure. This approach was described in details in [10].…”

Section: Fig 3 Iterative Methodology Of the Snf Thermal State Definitionmentioning

confidence: 99%

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Alyokhina¹,

Kostikov²,

Koriahina³

2020

Problems of Atomic Science and Technology

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“…There is a number of publications on the thermal analysis of the ventilated vertical concrete storage casks for WWER-1000 SNF [11,12,13]. In the modelling multistage approach is used.…”

Section: Introductionmentioning

confidence: 99%

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Poškas

Šimonis

Jouhara

et al. 2019

Energy

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Management of spent nuclear fuel is a very important part in the whole cycle of nuclear energy generation. Ignalina nuclear power plant operated two RBMK-1500 reactors that are now being decommissioned. After careful consideration "dry" storage technology in casks was selected for the interim storage of spent nuclear fuel (SNF) for up to 50 years. SNF after pre-storage time in water pools for not less than 5 years is loaded into cast-iron or metal-concrete casks. In this paper decay heat removal was modeled from specific GNB (Gesellschaft für Nuklear Behälter GmbH) metalconcrete (CONSTOR RBMK-1500) casks for the long-term storage period up to 300 years. The ALGOR code was used for the numerical modeling of the distribution of the heat fluxes and temperatures in a loaded cask placed in an open type storage facility in both summer and winter taking into account local environmental conditions. A local sensitivity analysis of the impact of fuel parameter uncertainties is also performed.

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Three‐dimensional thermal analysis of the repository for high‐level radioactive nuclear waste

Zhou

Zhou²,

2020

Int J Energy Res

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

Cited by 15 publications

References 13 publications

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Three‐dimensional thermal analysis of the repository for high‐level radioactive nuclear waste

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