The Social Impact of the Chernobyl Disaster

Marples, David R.

doi:10.1007/978-1-349-19428-5

Cited by 67 publications

(25 citation statements)

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“…In the UK, the high level waste (HLW) arising from reprocessing of spent nuclear fuel is vitrified in an alkali 81 borosilicate glass at the Sellafield Waste Vitrification Plant (WVP), similar to that operated at Cap de la Hague 82 in France [1]. In this process, a nitric acid solution of HLW is partially denitrated in a rotary calciner and the 83 product is combined with an alkali borosilicate frit, and then vitrified in an induction melter operating at 84 ~1060 °C .…”

Section: Takedownmentioning

confidence: 99%

Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes

Zhang

Corkhill

Heath

et al. 2015

Journal of Nuclear Materials

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Article available under the terms of the CC-BY-NC-ND licence (https://creativecommons.org/licenses/by-nc-nd/4.0/) eprints@whiterose.ac.uk https://eprints.whiterose.ac.uk/ Reuse This article is distributed under the terms of the Creative Commons Attribution-NonCommercial-NoDerivs (CC BY-NC-ND) licence. This licence only allows you to download this work and share it with others as long as you credit the authors, but you can't change the article in any way or use it commercially. More information and the full terms of the licence here: https://creativecommons.org/licenses/ Takedown If you consider content in White Rose Research Online to be in breach of UK law, please notify us by emailing eprints@whiterose.ac.uk including the URL of the record and the reason for the withdrawal request. alter the glass structure, with changes identified in both borate and silicate glass networks using Raman 50 spectroscopy. In particular, these glasses were characterised by a significantly higher Q 3 species, which we 51 attribute to Si-O-Zn linkages; addition of ZnO and CaO to the glass composition therefore enhanced glass 52 network polymerisation. The increase in network polymerisation, and the presence of spinel crystallites, were 53 found to increase the glass viscosity of the ZnO / CaO modified base glass; however the viscosities were within 54 the accepted range for nuclear waste glass processing. The ZnO / CaO modified glass compositions were 55 observed to be significantly more durable than the Na 2 O / Li 2 O base glass up to 28 days, due to a combination 56 of the enhanced network polymerisation and the formation of Ca / Si containing alteration layers.

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Section: Takedownmentioning

confidence: 99%

Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes

Zhang

Corkhill

Heath

et al. 2015

Journal of Nuclear Materials

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“…Generally this is an unacceptable approximation for nuclear waste glasses because they always are surface contaminated. Decontamination, which is a removal of surface-bonded radionuclides, is a routine operation in nuclear waste vitrification plants [54], it however never involves the removal of surface contamination from any piece of glass in a canister. Moreover the near surface layers of any solid including glass are different from the bulk [55] hence generally the concentration of species in the near surface layers is not equal exactly to the average concentration, C i .…”

Section: Mechanisms Of Cation Releasementioning

confidence: 99%

Corrosion of alkali–borosilicate waste glass K-26 in non-saturated conditions

Ojovan

Hand

Ojovan³

et al. 2005

Journal of Nuclear Materials

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“…At Chernobyl, the low power at which the reactor was operated by the test personnel combined with full use of the cooling water circulation pumps generated enough steam production for the reactor to run away and finally explode. According to Marples (1988), the Chernobyl explosion in April 1986 was caused partly by several errors made by the test personnel:…”

Section: Risks and Errors In The Nuclear Industrymentioning

confidence: 99%

Human error driving the development of a checklist for foreign material exclusion in the nuclear industry

Kenger

Karlsson

2007

Hum Ftrs & Erg Mfg Svc

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In this article we describe an approach to develop a checklist for foreign material exclusion. Foreign material is material that should not be part of, or supplied with, the product because it can affect the performance of, for example, nuclear fuel rods of nuclear plants. The research itself was initiated by the presence of different types of human errors. Specifically in the nuclear industry, where there is zero tolerance for errors, work to continuously improve safety and quality is of major importance. Our approach should support such work. As a theoretical base, we have considered team errors as well as individual errors. The suggested practical approach is based on foreign materials that originate in or are introduced into a product or a process.

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The Social Impact of the Chernobyl Disaster

Cited by 67 publications

References 0 publications

Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes

Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes

Corrosion of alkali–borosilicate waste glass K-26 in non-saturated conditions

Human error driving the development of a checklist for foreign material exclusion in the nuclear industry

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