Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel

Pitting corrosion resistance and passive films of Fe balance -18Cr-12Ni-1.5Mn-0.07C-based alloys containing 0.19, 0.78, and 1.76 wt% B were investigated through potentiodynamic polarization tests and scanning transmission electron microscopy-energy dispersive spectroscopy analyses, respectively, in NaCl and H 3 BO 3 solutions. The addition of B lowered the resistance to pitting corrosion due to the increase in the volume fraction of (Cr,Fe) 2 B. For the alloy with a large volume fraction of (Cr,Fe) 2 B, the resistance to pitting corrosion in the NaCl solution was improved due to the addition of H 3 BO 3 , as H 3 BO 3 assisted passivation and raised the Cr fraction in the passive film.

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Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask

Leotlela¹,

Petr²,

Mathye

2020

Kerntechnik

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An essential component of safety analyses is the investigation of accident scenarios. In this paper water ingress scenarios of spent fuel containers, as they may occur during transport or storage, are examined. In the main body of this paper, a number of paths are studied through which water can gain access to the spent fuel cask and eventually reach the fuel pellet, potentially resulting in an increase in reactivity as a result of over-moderation. The primary objective of this project was to perform an assessment of what, in the unlikely event of a Fukushima- type accident, the impact would be on the reactivity of the cask by analyzing a gradual increase in water level in the spent fuel casks. In addition, the way the keff of the system responds to such an increase is discussed. The paper also provides the results of an assessment of the reactivity effect of water ingress via various pathways/channels.

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Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel

Cited by 3 publications

References 59 publications

A High-Assay Low-Enriched Uranium Fuel Transportation Concept

A High-Assay Low-Enriched Uranium Fuel Transportation Concept

Pitting Corrosion and Passive Behavior of Type AISI 304-based Borated Stainless Steels in a Boric Acid Solution

Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask

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