Extended Dry Storage Research Articles

Using temperature and flow fields to detect gas leakage from canisters containing spent nuclear fuel: Applications to RAMM-TM

The multi-physics STAR-CCM+ code has been used to simulate the temperature and flow fields in canister gas leakage experiments conducted by using a 1/4.5-scale model storage cask. The simulations were conducted at Argonne National Laboratory’s Laboratory Computing Resource Center, utilizing high-performance computing resources. Development of STAR-CCM+ simulation models for the 1/4.5-scale model cask is described herein, followed by validation of the simulation results against experimental data. Canister depressurization and thermal response during gas leakage are discussed, along with analyses of the leakage path and allowable leakage rate. The insights gained from the STAR-CCM+ simulations and leakage analyses will help guide future experiments and actual industry applications of Argonne’s Remote Area Modular Monitoring system for canister surface temperature measurement (RAMM-TM) to enable effective aging management of spent fuel during extended dry storage, as well as help reduce risks to public safety and health and protect the environment.

Technical basis for extended dry storage of aluminum-clad spent nuclear fuel

This paper presents the technical basis for extended dry storage of aluminum-clad spent nuclear fuel (ASNF). This basis addresses and closes five knowledge gaps defined by the U.S. Department of Energy (DOE) Spent Nuclear Fuel Working Group (SNFWG) in DOE-ID/RPT-1575 “Aluminum-clad Spent Nuclear Fuel: Technical Considerations and Challenges for Extended (>50 Years) Dry Storage.” The SNFWG's primary concern pertaining to dry storage of ASNF is rooted in the presence of (oxy)hydroxide layers adherent to the aluminum cladding of the spent fuel that formed in service, indicating a risk of radiolytic molecular hydrogen (H2) generation in a strong gamma radiation field—a process that can be associated with disintegration of (oxy)hydroxide and the molecular decomposition of chemisorbed and physisorbed water bonded to it. Potential consequences are overpressurization of sealed ASNF dry storage canisters and creation of a flammable atmosphere in sealed and vented canisters. Further, there is the concern that the generation of other chemical species due to chemical reactions, such as nitric acid (HNO3), could lead to canister component corrosion. To address these issues, experimental work was conducted, including investigations of the performance of surrogate aluminum specimens and actual ASNF material featuring adherent (oxy)hydroxide layers during wet or dry storage. Further, a comprehensive characterization of the sample material was completed. Drying experiments were executed, providing better estimations of the amount of residual, chemisorbed, and physisorbed water after ASNF dry storage canister conditioning. These empirical activities allowed for the development of predictive numerical models to simulate the chemical species yield within sealed and vented dry storage canisters for 50 years. The findings of these activities lead to the main conclusion that extending current ASNF dry storage durations by 50 years is both safe and viable.

Modeling of hydrogen behavior in liner claddings

The fuel rod integrity during extended dry storage can be jeopardized by hydrogen-related phenomena such as delayed hydride cracking or embrittlement. In this work, a model for hydrogen behavior in liner claddings is proposed and validated against out-of-pile experiments. Simulations of base irradiation scenarios are carried out. The obtained results are in qualitative agreement with the post-irradiation observations.

Preliminary Modeling of Chloride Deposition on Spent Nuclear Fuel Canisters in Dry Storage Relevant to Stress Corrosion Cracking

This study presents a method that can be used to gain information relevant to determining the corrosion risk for spent nuclear fuel (SNF) canisters during extended dry storage. Currently, it is known that stainless steel canisters are susceptible to chloride-induced stress corrosion cracking (CISCC). However, the rate of CISCC degradation and the likelihood that it could lead to a through-wall crack is unknown. This study uses well-developed computational fluid dynamics and particle-tracking tools and applies them to SNF storage to determine the rate of deposition on canisters. The deposition rate is determined for a vertical canister system and a horizontal canister system, at various decay heat rates with a uniform particle size distribution, ranging from 0.25 to 25 µm, used as an input. In all cases, most of the dust entering the overpack passed through without depositing. Most of what was retained in the overpack was deposited on overpack surfaces (e.g., inlet and outlet vents); only a small fraction was deposited on the canister itself. These results are provided for generalized canister systems with a generalized input; as such, this paper is intended to demonstrate the technique. This study is a part of an ongoing effort funded by the U.S. Department of Energy, Nuclear Energy Office of Spent Fuel Waste Science and Technology, which is tasked with doing research relevant to developing a sound technical basis for ensuring the safe extended storage and subsequent transport of SNF. This work is being presented to demonstrate a potentially useful technique for SNF canister vendors, utilities, regulators, and stakeholders to utilize and further develop for their own designs and site-specific studies.

Safety of Extended Dry Storage of Spent Nuclear Fuel SEDS2020: International online-workshop

Safety of Extended Dry Storage of Spent Nuclear Fuel SEDS2020: International online-workshop

SEDS benchmark for fuel rod behaviour during dry storage – preliminary results

Abstract One of the key aspects for the safety of extended dry storage of used nuclear fuel in casks is the prediction of the fuel rod behavior. A detailed and reliable prediction has to take into account the entire life span of the fuel rod: Service in reactor with the associated radiation history, wet storage in the fuel pool, loading and drying of the cask, and finally the in-cask dry storage itself. Enhancing existing fuel performance codes to include all these steps and the associated phenomena is an ongoing task tackled by several groups. To foster the communication between these groups a benchmark was proposed at the 2019 Safety of Extended Dry Storage (SEDS) workshop. The article at hand summarizes some of the preliminary results which were presented at the 2020 SEDS workshop.

Research activities at GRS on fuel rod behaviour during extended dry storage

Abstract As a common part of nuclear waste management strategies, used nuclear fuel is dry stored in casks. After a sufficient time of wet cooling in fuel pools, the fuel assemblies in Germany are dry stored in dual purpose casks mostly on-site until a deep geological repository will be available in the future. In the light of the extended and preliminary not foreseen timescales of up to 100 years of dry storage, open questions arise concerning the long term fuel rod behaviour. Most of these questions are linked to safety criteria e.g. the integrity and fuel encapsulation. Due to the variety of used nuclear fuels and cladding materials in Germany and the additional use of MOX fuels and very high burn-up values of 65 GWd/tHM averaged over a fuel assembly, some of the boundary conditions are unique and specific to the German situation. The GRS has a strong research program to investigate the long term behaviour of fuel assemblies under the German specific conditions of dry storage. Some aspects are presented in the following article.

Open questions on the road to reliable predictions of cladding integrity

Abstract The paper at hands discusses the development of an integrated method to predict the fuel rod behavior of LWR-fuel during extended dry storage scenarios. It is well known that degradation effects exist under certain circumstances and that a fuel rod integrity assessment for long-term storage, handling and transport must take these effects into account. It will be elaborated why a complete coverage of the whole lifetime of the fuel rod is necessary. This includes the fabrication, reactor operation, wet storage, drying process, and the dry storage itself. Regarding this approach, a discussion on open questions and challenges will be given.

Cladding stress during extended storage of high burnup spent nuclear fuel

In an effort to assess the potential for low temperature creep and delayed hydride cracking failures in high burnup spent fuel cladding during extended dry storage, the U.S. NRC analytical fuel performance tools were used to predict cladding stress during a 300year dry storage period for UO2 fuel burned up to 65GWd/MTU. Fuel swelling correlations were developed and used along with decay gas production and release fractions to produce circumferential average cladding stress predictions with the FRAPCON-3.5 fuel performance code. The resulting stresses did not result in cladding creep failures. The maximum creep strains accumulated were on the order of 0.54–1.04%, but creep failures are not expected below at least 2% strain. The potential for delayed hydride cracking was assessed by calculating the critical flaw size required to trigger this failure mechanism. The critical flaw size far exceeded any realistic flaw expected in spent fuel at end of reactor life.

Effects of Extended Dry Storage of Powdered Infant Milk Formula on Susceptibility of Enterobacter sakazakii to Hot Water and Ionizing Radiation

Infant milk formula has been identified as a potential source of Enterobacter sakazakii, which has been implicated in neonatal meningitis and necrotizing enterocolitis. This study was undertaken to determine whether the length of E. sakazakii storage in powdered infant milk formula (PIMF) affected the ability of the pathogen to survive subsequent reconstitution of the powder with hot water or treatment with gamma radiation. Five E. sakazakii strains were mixed individually with PIMF and kept for up to 12 months at 25°C. After storage PIMF was reconstituted with water at 60 to 100°C or was exposed to ≤5 kGy of gamma radiation. Without any treatment secondary to drying, E. sakazakii counts decreased <1 log/g after 1 month but decreased about 4 log/g during storage for 8 to 12 months. Dry storage decreased thermal resistance but increased resistance of E. sakazakii to ionizing radiation in PIMF. Reconstitution of contaminated powder with water at 70°C after 1 month of dry storage reduced E. sakazakii viability slightly, >2 log/g, and after powder was stored for 12 months all E. sakazakii strains were eliminated. In contrast, desiccation substantially increased the resistance of E. sakazakii strains to ionizing radiation. Although the D-value for E. sakazakii IMF1 following overnight storage in PIMF was 0.98 kGy, >4 kGy was required to kill 1.5 log/g of the same strain that had survived 12 months in dry PIMF. Results suggested that low-dose irradiation will more effectively eliminate E. sakazakii from PIMF if the treatment is applied shortly after PIMF manufacture.

Replantation after extended dry storage of avulsed permanent incisors: report of a case

A 15-year-old boy lost his maxillary right and left central incisor teeth in a bicycle accident. He was referred to our clinic 1 week after the injury. The crown-root integrities of both the teeth were not damaged. Although the teeth were stored under dry conditions for 1 week, reimplantation of the teeth was planned to retain the teeth in the mouth for as long a period as possible because of the patient's age. Following the debridement and sterilization of root surfaces in 2.5% NaOCl, root canals were prepared and filled with calcium hydroxide. Then, about 2 mm of the apexes were resected to ensure that the roots easily seated in the alveolar socket and the prepared cavities in root ends were obturated with the amalgam. The teeth were placed into their respective sockets and splinted temporarily. The root canal therapy was completed 5 weeks later. Ankylosis was observed radiographically after 10 months. The patient is now 23 years old and he is still able to use both the central incisors functionally. However, there is a pink appearance on the cervical buccal surface of left central incisor because of progressive replacement resorption. In this case, the new treatment plan is to perform a permanent restoration with dental implants following the extraction of both teeth. Even though the long-term prognosis is uncertain, this treatment technique has provided an advantage for the patient in his adolescent period by maintaining the height of alveolar bone and making the provision of an aesthetically acceptable permanent restoration at a later age possible.

Replantation after extended dry storage of avulsed permanent incisors: report of a case

Replantation after extended dry storage of avulsed permanent incisors: report of a case