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Processing of Solid Low Level Alpha Suspected Radioactive Waste

M.N. Maes、Thomas Huys、Jeroen Rommes 等 5 位作者2013-09-08OpenAlex

Incineration of low active waste is the most efficient way to obtain high volume reduction factors. Although the initial scenario for processing low active alpha suspected waste (α-activity ≤ 400MBq/m3) in Belgium was supercompaction, incineration was eventually chosen for various benefits concerning volume reduction…

Nuclear Physics and ApplicationsGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Graphite Waste Pit Cleanup

V. Thiébaut、Jean-Luc Gerber2013-09-08OpenAlex

The UP1 plant in Marcoule reprocessed nearly 20,000 tons of used natural uranium gas cooled reactor fuel coming from the first generation of civil nuclear reactors in France. During more than 40 years, the decladding operations produced thousands of tons of processed waste, mainly magnesium and graphite fragments. In…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Upstream Optioneering: Optimising Higher Activity Waste Management

Jennifer McTeer、Jenny Morris、Stephen M. Wickham 等 6 位作者2013-09-08OpenAlex

The Upstream Optioneering project was created by the Nuclear Decommissioning Authority (NDA) Radioactive Waste Management Directorate (RWMD) to support the development and implementation of opportunities to optimise the management of UK higher activity waste, spent fuel and other materials that may be disposed of in a…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studiesMarine and Offshore Engineering Studies

The Role of Large Scale Demonstration Experiments in Supporting the Implementation of a High Level Waste Programme

Kenichi Yoshimura、Irina Gaus、Kazuya Kaku 等 6 位作者2013-09-08OpenAlex

Large scale demonstration experiments in underground research laboratories (both onsite and off-site) are currently undertaken by most high level radioactive waste management organisations. The decision to plan and implement prototype experiments, which might have a life of several decades, has both important strategi…

Nuclear Materials and PropertiesGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

D&D Knowledge Management Information Tool: A Web Based System Developed to Share D&D Knowledge Worldwide

Leonel Lagos、Himanshu Upadhyay、P. Shoffner2013-09-08OpenAlex

Deactivation and decommissioning (D&D) work is a high-risk and technically challenging enterprise within the U.S. Department of Energy complex. During the past three decades, the DOE’s Office of Environmental Management has been in charge of carrying out one of the largest environmental restoration efforts in the worl…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studiesMarine and Offshore Engineering Studies

Application of PHADEC Method for the Decontamination of Radioactive Steam Piping Components

Rosa Lo Frano、F. Pilo、Donato Aquaro2013-09-08OpenAlex

The dismantling of nuclear plants is a complex activity that originates often a large quantity of radioactive contaminated residue. In this paper the attention was focused on the PHADEC (PHosphoric Acid DEContamination) plant adopted for the clearance of Caorso NPP (in Italy) metallic systems and components contaminat…

Nuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Dose Rate Profile Surrounding a Repository

J. Parson、A. Brandl、N. Zoeger 等 4 位作者2013-09-08OpenAlex

The focus of this research was to analyze the dose rate profile around a waste repository using Monte Carlo techniques. Dose rates at various heights and distances were analyzed outside of the waste repository using MCNPX [1]. The heights measured extended the height of the building and the distances varied between 0…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Applicability of Iron Phosphate Glass Medium for Loading NaCl Originated From Seawater Used for Cooling the Stricken Power Reactors

Hidekazu Kobayashi、Ippei Amamoto、Takuma Yokozawa 等 9 位作者2013-09-08OpenAlex

As the part of investigation for immobilization of the sludge as one of the radioactive wastes arising from the treatment of contaminated water at Fukushima Dai-ichi nuclear power plant, applicability of vitrification method has been evaluated as a candidate technique. The aim of this study is to evaluate the influenc…

Glass properties and applicationsNuclear materials and radiation effectsChemical Synthesis and Characterization

Developing a Concept for a National Used Fuel Interim Storage Facility in the United States

Donald W. Lewis2013-09-08OpenAlex

In the United States (U.S.) the nuclear waste issue has plagued the nuclear industry for decades. Originally, spent fuel was to be reprocessed but with the threat of nuclear proliferation, spent fuel reprocessing has been eliminated, at least for now. In 1983, the Nuclear Waste Policy Act of 1982 [1] was established,…

Radioactive contamination and transferGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

The Simulation of Decontamination Works in Premises of the Research Reactor in NRC “Kurchatov Institute”

A. S. Danilovich、О. П. Иванов、V. N. Potapov 等 5 位作者2013-09-08OpenAlex

Application of remote sensing methods using a spectrometric collimated system allows obtaining information about features of a formation of radiation fields in contaminated premises. This information helps in a preparation of a phased plan for dismantling of contaminated equipment. When the survey of technological pre…

Graphite, nuclear technology, radiation studies

Production of an Impermeable Composite of Irradiated Graphite and Glass by Hot Isostatic Pressing as a Long Term Leach Resistant Waste Form

J. Fachinger、Walter H. Müller、Eric Marsat 等 8 位作者2013-09-08OpenAlex

Around 250,000 tons of irradiated graphite (i-graphite) exists worldwide and can be considered as a current waste or future waste stream. The largest national i-graphite inventory is located in UK (∼ 100,000 tons) with significant quantities also in Russia and France [5]. Most of the i-graphite remains in the cores of…

Recycling and Waste Management TechniquesGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Activities ONDRAF/NIRAS Related to the Decommissioning of Nuclear Facilities

Jacques Cantarella、R. Simenon、Marnix Braeckeveldt2013-09-08OpenAlex

Since 1980, the Agency is responsible by law for the safe management of all radioactive waste produced in Belgium, including decommissioning wastes. By the law of 11 January 1991 and the implementing Royal Decree of 16/10/1991, ONDRAF/NIRAS has been entrusted with a mission concerning the decommissioning of nuclear fa…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studiesMarine and Offshore Engineering Studies

“Strategy is a Commodity, Implementation is an Art”: 2 Years of Implementation of the UK National LLW Strategy

Helen Cassidy、David Rossiter2013-09-08OpenAlex

The Low Level Waste Repository (LLWR) is the primary facility for disposal of Low Level Waste (LLW) in the United Kingdom (UK), serving the UK nuclear industry and a diverse range of other sectors. Management of LLW in the UK historically was dominated by disposal to the LLWR. The value of the LLWR as a national asset…

Recycled Aggregate Concrete PerformanceGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Deterioration of Diesel Particulate Filters in Relation to CI Engine Fueled with Biodiesel

Casper Raahede、Henrik I. Christensen2013-09-08SAE technical papers on CD-ROM/SAE technical paper series

The paper presents results illustrating the effect on Diesel particulate filters (DPF) in relation to rapeseed methyl ester (RME) and animal tallow methyl ester (TME) compared to Diesel (EN590). Measurements were performed in an engine test cell using a modern common rail light duty CI engine running at five different…

Advanced Combustion Engine TechnologiesCatalytic Processes in Materials ScienceBiodiesel Production and Applications

Treatment of Irradiated Graphite From French Bugey Reactor

Howard N.E. Stevens、Gérard Laurent2013-09-08OpenAlex

In 2008, following the general French plan for nuclear waste management, Électricité de France attempted to find for irradiated graphite an alternative solution to direct storage at the low-activity long-life storage center in France managed by the national agency for wastes (ANDRA). EDF management requested that its…

Recycling and Waste Management TechniquesGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

Radioactive Waste Characterization and Tracking System at the French Atomic Energy Commission

Hervé Lamotte、Luc Torreblanca、Suzel Vilarel2013-09-08OpenAlex

CARAIBES is the traceability information system in radioactive solid waste management of the French Atomic Energy Commission, (CEA). Initially developed for the reprocessing facility of low and intermediate level waste of the centre of Cadarache, it has been gradually enhanced to manage very low level waste and the fa…

Radioactive element chemistry and processingGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

An Overview of the Draft of ‘Nuclear Materials and Radioactive Waste Management Act’

Huan Lin、Tai-Wei Lan、Min-Tsang Chang 等 4 位作者2013-09-08OpenAlex

The “Nuclear Materials and Radioactive Waste Management Act” (NMRWMA) in Taiwan has been in use since 2002. To promote further administrative efficiency and improve regulatory capacity, an amendment of the act has been initiated by the Atomic Energy Council (AEC). It is now being reviewed by outside experts and relate…

Graphite, nuclear technology, radiation studiesInternational Environmental Law and PoliciesNuclear and radioactivity studies

Decommissioning the Belgonucleaire Dessel MOX Plant: Presentation of the Project and Situation End August 2013

J. M. Cuchet、H. Libon、C. Verheyen 等 7 位作者2013-09-08OpenAlex

BELGONUCLEAIRE has been operating the Dessel MOX plant at an industrial scale between 1986 and 2006. During this period, 40 metric tons of plutonium (HM) have been processed into 90 reloads of MOX fuel for commercial light water reactors. The decision to stop the production in 2006 and to decommission the MOX plant wa…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studiesMarine and Offshore Engineering Studies

Impact of Recent Developments on the Status of Commercial Nuclear Power and Reactor Decommissioning in the United States

J.S. Devgun2013-09-08OpenAlex

This paper examines the impact of three recent developments on the commercial nuclear power in the United States. These developments include: Yucca Mountain closure and issues related to SNF; actions in response to Fukushima Diaiichi accident, and; energy economics. All of these have had a significant impact on the co…

Graphite, nuclear technology, radiation studiesNuclear and radioactivity studies

ISO Standardization of Theoretical Activity Evaluation Method for Low and Intermediate Level Activated Waste Generated at Nuclear Power Plants

Makoto Kashiwagi、Mike Garamszeghy、B. Lantes 等 8 位作者2013-09-08OpenAlex

Disposal of low- and intermediate-level activated waste generated at nuclear power plants is being planned or carried out in many countries. The radioactivity concentrations and/or total quantities of long-lived, difficult-to-measure nuclides (DTM nuclides), such as C-14, Ni-63, Nb-94, α emitting nuclides etc., are of…

Nuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies