An analysis of the commercial waste characterisation in a tourism city in Vietnam

Management of solid mine wastes requires detailed material characterisation at the start of a project to minimize opportunities for the generation of acid and metalliferous drainage (AMD). Mine planning must focus on obtaining a thorough understanding of the environmental properties of the future waste rock materials. Using drill core obtained from a porphyry Cu project in Northern Europe, this study demonstrates the integrated application of mineralogical and geochemical data to enable the construction of enviro-geometallurgical models. Geoenvironmental core logging, static chemical testing, bulk- and hyperspectral mineralogical techniques, and calculated mineralogy from assay techniques were used to critically evaluate the potential for AMD formation. These techniques provide value-adding opportunities to existing datasets and provide robust cross-validation methods for each technique. A new geoenvironmental logging code and a new geoenvironmental index using hyperspectral mineralogical data (Hy-GI) were developed and embedded into the geochemistry-mineralogy-texture-geometallurgy (GMTG) approach for waste characterisation. This approach is recommended for new mining projects (i.e., early life-of-mine stages) to ensure accurate geoenvironmental forecasting, therefore facilitating the development of an effective waste management plan that minimizes geoenvironmental risks posed by the mined materials.

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RTS - 1 - Galilei Decommissioning Project

9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3 ◽

10.1115/icem2003-4661 ◽

2003 ◽

Author(s):

A. Boschi ◽

E. Cimini ◽

F. Pagni ◽

L. Parracone ◽

M. Pocai ◽

...

Keyword(s):

Research Reactor ◽

Thermal Flux ◽

Spent Fuel ◽

Radiological Risk ◽

Radioactive Materials ◽

Thermal Output ◽

Protective Custody ◽

First Time ◽

Waste Characterisation

The RTS-1 “Galileo Galilei” is an open pool research reactor light water moderated and cooled. It had a maximum thermal output of 5 MWth and an average thermal flux of 5 E+13 n/cm2sec. It became critical for the first time on April 1963 and it was definitely shutdown in March 1980. The reactor is situated at CISAM (Joint Centre of Studies and Military Application - Italian Ministry of Defence), S. Piero a Grado, Pisa, Italy, and its decommissioning is in progress. In this paper the strategy adopted to achieve the green status of the reactor site is discussed, with particular attention on the different steps to be done according to the national laws. Emphasis is placed on the characteristics of two different conditions required, namely Passive Protective Custody, which is a step necessary to allow the decay of the radioactive materials present into the plant to decrease the radiological risk to operate safely, and Unconditioned Release, in which all the materials can be released without radiological restrictions. Another aspect discussed in this paper is the effort spent on the determination of the radioisotopic abundance of the reactor components, the personal dose evaluation due to the necessary activities to achieve two different status of “Passive Protective Custody” and “Unconditioned Release” and the waste characterisation. The necessary authorisations to start decommissioning has been obtained as far as concern the removal of spent fuel and the dismantling of some experimental equipments.

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Setting-to-Work a State-of-the-Art Solid Waste Characterisation Facility at JRC Ispra

9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3 ◽

10.1115/icem2003-5024 ◽

2003 ◽

Author(s):

Ilpo Huhtiniemi ◽

Massimo Anselmi ◽

Gary Vassallo ◽

Flaviano Bruno ◽

Giulio Panini

Keyword(s):

State Of The Art ◽

Selection Process ◽

Nuclear Research ◽

Lessons Learned ◽

Process Automation ◽

Contractor Selection ◽

Industrial Environment ◽

Research Activities ◽

Significant Interest ◽

Waste Characterisation

This paper reviews the experience gained when setting-to-work a state-of-the-art waste characterisation facility that will be a fundamental element in the JRC’s strategy to characterise radioactive wastes originating from four decades of nuclear research activities conducted at the Ispra Site. In a previous paper at ICEM ’01, the authors described the specifications for the principal components of a Waste Characterisation System (WCS) and the ensuing contractor selection process via a public tendering procedure. The present paper has a broader perspective by addressing the whole waste characterisation facility of which the WCS forms a part. In the opening section, the main constituents of the facility are reviewed, and their optimised integration to respect emerging Italian standards, conventional safety principles, ALARA and operational efficiency, are discussed. The second part of the paper examines the analyses required for the licensing of the waste characterisation facility. Finally, the paper concludes with a summary of the lessons learned from the setting-to-work phase of the facility. Since the facility combines a state-of-the-art NDA solution with comprehensive process automation in an industrial environment, the experience is expected to be of significant interest to the radioactive waste management community.

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Integrating Waste Characterisation into Landform Design for Low-Risk and Low-Cost Mine Closure

Proceedings of the First International Seminar on Mine Closure ◽

10.36487/acg_repo/605_46 ◽

2006 ◽

Author(s):

David Jasper ◽

Matthew Braimbridge ◽

Harley Lacy ◽

Michael Russell

Keyword(s):

Low Cost ◽

Low Risk ◽

Mine Closure ◽

Waste Characterisation

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Polypropylene Contamination in Post-Consumer Polyolefin Waste: Characterisation, Consequences and Compatibilisation

Polymers ◽

10.3390/polym13162618 ◽

2021 ◽

Vol 13 (16) ◽

pp. 2618

Author(s):

Erdal Karaagac ◽

Mitchell P. Jones ◽

Thomas Koch ◽

Vasiliki-Maria Archodoulaki

Keyword(s):

Mechanical Properties ◽

Environmental Sustainability ◽

Rapid Expansion ◽

Low Density Polyethylene ◽

Low Density ◽

Plastic Recycling ◽

Band Ratios ◽

Ft Ir ◽

Waste Characterisation ◽

Recycled Material

Plastic recycling strikes a balance between functional, mass producible products and environmental sustainability and is pegged by governments for rapid expansion. However, ambitious targets on recycled material adoption across new markets are at odds with the often heterogenous properties of contaminated regranulates. This study investigated polypropylene (PP) contamination in post-consumer low-density polyethylene (PE-LD) and mixed polyolefin (PO) regranulates. Calibration curves were constructed and PP content, its effect on mechanical properties and property recovery in compatibilised material assessed. FT-IR band ratios provided more reliable estimations of PP content than DSC melt enthalpy, which suffered considerable error for PP copolymers. PE-LD regranulates contained up to 7 wt.% PP contamination and were considerably more brittle than virgin PE-LD. Most mixed PO regranulates contained 45–95 wt.% PP and grew more brittle with increasing PP content. Compatibilisation with 5 wt.% ethylene-based olefin block copolymer resulted in PE-LD blends resembling virgin PE-LD and considerable improvements in the properties of mixed PO blends. These results illustrate the prevalence of PP in recycled PE, challenges associated with its quantification, effect on mechanical properties, and compatibilisation viability, thereby representing an important step towards higher quality regranulates to meet the recycling demands of tomorrow.

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Plasma source mass spectrometry for radioactive waste characterisation in support of nuclear decommissioning: a review

Journal of Analytical Atomic Spectrometry ◽

10.1039/c6ja00334f ◽

2017 ◽

Vol 32 (3) ◽

pp. 494-526 ◽

Cited By ~ 36

Author(s):

Ian W. Croudace ◽

Ben C. Russell ◽

Phil W. Warwick

Keyword(s):

Nuclear Waste ◽

Plasma Source ◽

Waste Materials ◽

Significant Challenge ◽

Nuclear Decommissioning ◽

Nuclear Site ◽

Icp Ms ◽

Complex Sample ◽

Waste Characterisation

The efficient characterization of nuclear waste materials represents a significant challenge during nuclear site decommissioning, with a range of radionuclides requiring measurement in varied and often complex sample matrices. ICP-MS is increasingly a practicable alternative to radiometric methods for medium to long-lived radionuclides.

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