SOARCA uncertainty analysis of a short-term station blackout accident at the Sequoyah nuclear power plant

Bixler, Nathan E.; Dennis, Matthew L.; Ross, Kyle; Osborn, Douglas; Gauntt, Randall O.; Wagner, Kenneth Charles; Ghosh, S. Tina; Hathaway, A.G.; Esmaili, Hossein

doi:10.1016/j.anucene.2020.107495

Cited by 3 publications

(4 citation statements)

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“…The study recommended that, to maintain the safety of the storage facility, heat should be effectively removed from the fuel storage cask. Bixler et al [3] analyzed the pressure and temperature distributions in an ice condenser plant at a nuclear power generation facility during a short-term station blackout. Wataru et al [4] performed a heat removal verification test of full-scale concrete cask and concrete-filled steel cask (CFS).…”

Section: Introductionmentioning

confidence: 99%

Post-Blackout Response of Backup Power Supply on the Safety of Nuclear Fuel Storage Vault

Mishra¹,

Panda²,

Sen³

et al. 2022

International Conference on Fluid Flow, Heat and Mass Transfer

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Thermal analysis of nuclear fuel storage vault post-blackout scenario and the response from different backup power supply systems have been carried out numerically. The thermal aspects of the blackout scenario with backup power supply and its effect on the rise in temperature of the blanket and fuel containers and their enclosures are presented. The airflow inside the vault is analyzed using predicted data from the simulations. The safety of the vault was analyzed in terms of inside air temperature distributions and the temperature rise of fuels after the failure of suction blowers. The reduction in air circulation resulted in the rise in the temperature of fuels and concrete walls of the vault. The temperatures of the fuel subassemblies and magazines increase immediately after the failure of suction blowers and rise in temperature of cooling air. The repeated failure of blowers led to a fluctuation in average fuel temperature. The present study will help identify different safety measures of nuclear fuel storage systems.

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Section: Introductionmentioning

confidence: 99%

Post-Blackout Response of Backup Power Supply on the Safety of Nuclear Fuel Storage Vault

Mishra¹,

Panda²,

Sen³

et al. 2022

International Conference on Fluid Flow, Heat and Mass Transfer

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“…However, radioiodine also can be released from a nuclear power plant (NPP) during a severe accident but under harsher conditions. − Iodine is a major contributor to the radioactivity and dose if released into the environment during a nuclear severe accident. 131 I decays rapidly ( t 1/2 = 8.02 d) with high radiation.…”

Section: Introductionmentioning

confidence: 99%

“…Although occurrence is extremely rare, a nuclear severe accident accompanies temperatures of the generated steam in the reactor vessel lower head spiking above 1500–1800 K . Although the temperature of the steam decreases substantially as it moves away from the reactor vessel into the primary coolant system, containment, steam generator, and the environment, its temperature as being in a dry or superheated state is still expected to be so much higher than that of the off-gas streams under typical reprocessing conditions.…”

Section: Introductionmentioning

confidence: 99%

“…Although the temperature of the steam decreases substantially as it moves away from the reactor vessel into the primary coolant system, containment, steam generator, and the environment, its temperature as being in a dry or superheated state is still expected to be so much higher than that of the off-gas streams under typical reprocessing conditions. For example, in an unmitigated thermally induced steam generator tube rupture accident, the temperature at the interface between the steam generator and the hot stream may reach well above 600–800 K. , The steam containing radioactive materials may pass through the failed steam generator tube under these temperature conditions. Although the steam temperature gradually decreases while traveling through the pipelines before being released into the environment, the temperature can still reach above 600 K when being released outside in this accident scenario …”

Section: Introductionmentioning

confidence: 99%

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Feasibility Study of Using Bi-mna Metal–Organic Frameworks as Adsorbents for Radioiodine Capture at High Temperature

Jung

Kang

Yim

2021

Ind. Eng. Chem. Res.

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In this study, a bismuth-based metal−organic framework (Bi-MOF) was investigated in its applicability as an iodine adsorbent at high temperatures for possible applications under severe accidents in a nuclear power plant. Bi-mna was selected among Bi-MOF candidates based on its thermodynamic characteristics, which expected to allow chemisorption of iodine by bismuth. Its iodine adsorption performance was compared with zeolitic imidazolate framework-8 and Cu-BTC and other MOFs which were chosen due to their diversity in iodine adsorption mechanisms. Bi-mna was synthesized at the laboratory scale, and the aforementioned three MOFs were tested for iodine adsorption at various temperatures from 350 to 600 K. The adsorption mechanism of Bi-mna was investigated by conducting various analyses including thermogravimetric analysis, X-ray diffraction, X-ray photoelectron spectroscopy, and Brunauer−Emmett−Teller. The results showed that Bi-mna has good adsorption performance (700 mg-I/g-adsorbent) while maintaining good thermal stability even at a high temperature (up to 575−600 K). The iodine capture performance of Bi-mna is better, especially at high temperature, in comparison with those of non-MOF adsorbents such as silver-exchanged zeolites and bismuth-embedded SBA-15. Analysis results confirmed that Bi-mna chemically captured iodine by breaking bonds between bismuth and sulfur to form new chemical bonds between iodine and the bismuth in Bi-mna. The results indicate that Bi-mna has the potential to be used in capturing radioiodine at high-temperature environments, such as during nuclear severe accident management. Its use should also be considered as a potential candidate for waste form development.

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Integration of Level 3 probabilistic risk assessment for nuclear power plants with transportation simulation considering earthquake hazards

Shimada,

Sakurahara,

Farshadmanesh

et al. 2024

Annals of Nuclear Energy

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SOARCA uncertainty analysis of a short-term station blackout accident at the Sequoyah nuclear power plant

Cited by 3 publications

References 0 publications

Post-Blackout Response of Backup Power Supply on the Safety of Nuclear Fuel Storage Vault

Post-Blackout Response of Backup Power Supply on the Safety of Nuclear Fuel Storage Vault

Feasibility Study of Using Bi-mna Metal–Organic Frameworks as Adsorbents for Radioiodine Capture at High Temperature

Integration of Level 3 probabilistic risk assessment for nuclear power plants with transportation simulation considering earthquake hazards

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