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At least 325 records · Page 18

Dry heat sterilization as a method to recycle N95 respirator masks: The importance of fit

In times of crisis, including the current COVID-19 pandemic, the supply chain of filtering facepiece respirators, such as N95 respirators, are disrupted. To combat shortages of N95 respirators, many institutions were forced to decontaminate and reuse respirators. While several reports have evaluated the impact on filtration as a measurement of preservation of respirator function after decontamination, the equally important fact of maintaining proper fit to the users’ face has been understudied. In the current study, we demonstrate the complete inactivation of SARS-CoV-2 and preservation of fit test performance of N95 respirators following treatment with dry heat. We apply scanning electron microscopy with energy dispersive X-ray spectroscopy (SEM/EDS), X-ray diffraction (XRD) measurements, Raman spectroscopy, and contact angle measurements to analyze filter material changes as a consequence of different decontamination treatments. We further compared the integrity of the respirator after autoclaving versus dry heat treatment via quantitative fit testing and found that autoclaving, but not dry heat, causes the fit of the respirator onto the users face to fail, thereby rendering the decontaminated respirator unusable. Our findings highlight the importance to account for both efficacy of disinfection and mask fit when reprocessing respirators to for clinical redeployment.

77 NANOSCIENCE AND NANOTECHNOLOGY↗

Transport of French PWR steam generators to very low level waste disposal - 15203

When considering the complexity of IAEA nuclear transport regulations, the transport of a Steam Generator (SG) in one un-packaged block from a dismantling plant to a nuclear waste disposal is a challenge. The choices made, the difficulties encountered and the feedback that has been learnt from it are described. The disposal of decommissioning waste requires taking into account not only the constraints of acceptance of the repository but also the specific constraints of transportation from the dismantling plant to the final disposal site. In France, these criteria and regulations are respectively under the supervision of the French National Radioactive Waste Management Agency (ANDRA) and the French Nuclear Safety Authority (ASN). In the course of the dismantling of the EDF PWR plant Chooz A, the four decontaminated SGs were shipped to the ANDRA Very Low Level Waste (VLLW) repository. After removal, the SGs were decontaminated, allowing them to attain the criteria of VLLW and thus be accepted by the ANDRA. However, to transport these decontaminated SGs as single un-packaged blocks, it was necessary to ensure compliance with the Surface Contaminated Object SCO-I regulation criteria. For this, transport safety files were written and surface contamination and radiation criteria checked. One of the four SGs had to be decontaminated again and another one had to be transported under special arrangement. Due to the exceptional nature of the transportation, specialized means of transport and stowage were also studied. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The spore coat is essential for Bacillus subtilis spore resistance to pulsed light, and pulsed light treatment eliminates some spore coat proteins

Microbial surface contamination of equipment or of food contact material is a recurring problem in the food industry. Spore-forming bacteria are far more resistant to a wide variety of treatments than their vegetative forms. Understanding the mechanisms underlying decontamination processes is needed to improve surface decontamination strategies against endospores potentially at the source of foodborne diseases or food-spoilage. Pulsed light (PL) with xenon lamps delivers high-energy short-time pulses of light with wavelengths in the range 200 nm-1100 nm and a high UV-C fraction. Bacillus subtilis spores were exposed to either PL or to continuous UV-C. Gel electrophoresis and western blotting revealed elimination of various proteins of the spore coat, an essential outer structure that protects spores from a wide variety of environmental conditions and inactivation treatments. Proteomic analysis confirmed the elimination of some spore coat proteins after PL treatment. Transmission electron microscopy of PL treated spores revealed a gap between the lamellar inner spore coat and the outer spore coat. Overall, spores of mutant strains with defects in genes coding for spore coat proteins were more sensitive to PL than to continuous UV-C. This study demonstrates that radiations delivered by PL contribute to specific damage to the spore coat, and overall to spore inactivation. Keywords Decontamination, UV, proteins, proteomics, microscopy Journal Pre-proof

59 BASIC BIOLOGICAL SCIENCES↗

Removal of Chalk River unidentified deposit (CRUD) radioactive waste by enhanced electrokinetic process

Decontamination techniques proposed and used to remove Chalk River unidentified deposit (CRUD) in radioactive waste management. In cases of huge volumes of metal or radionuclides contaminated by CRUD, removal of CRUD by mechanical or chemical decontamination is difficult. An advanced electrokinetic process combined with chemical decontamination was applied to remove CRUD and experimentally evaluated. We used oxalic acid for CRUD removal, and cobalt (Co) released from the CRUD was transferred to the cathode in an electrokinetic reactor. Our results indicate that the combined system is efficient for CRUD removal with enhanced, efficiency by use of the cation exchange membrane and zeolite.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

A reductive dissolution study of magnetite

Magnetite dissolution tests using a hydrazine base solution were performed at a temperature range of 90 to 150 deg. C. The dissolution rate of magnetite increased with [N{sub 2}H{sub 4}], time, and temperature. The optimum solution pH in the experimental range was 3. The addition of copper ion to the hydrazine base solution greatly increased the magnetite dissolution rate. This was explained by the complex formation between N{sub 2}H{sub 4} and Cu ions, and the reducing power of the hydrazine-Cu complex to the ferric ions of magnetite. The reductive decontamination solution can be applied below 100 deg. C by the addition of copper ions. The chemical decontamination of a Type 304 stainless steel specimen using a hydrazine base reductive decontamination solution was also performed. The contact dose rate was greatly decreased by the repetitive application of NP and the hydrazine base solution. (authors)

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The involvement of SCK-CEN in decommissioning projects

SCK-CEN is the Belgian Nuclear Research Centre. Founded in the mid-fifties, it has accumulated experience and know-how in all fields of the nuclear power production: in the neutronics calculation, radiation protection, waste management, fuel performance and analysis, nuclear measurements, radiochemistry, reactor technology, etc. Since 1989, SCK-CEN has launched Decommissioning activities to deal with the Technical Liabilities created by 40 years of operation. The main projects started were: - the dismantling of the BR3 PWR reactor; - the dismantling of active laboratories and the decontamination of buildings for unrestricted reuse; - the management of the waste arising from the refurbishment activities of the BR2, especially the management of the high active beryllium matrix. In 1989, the BR3 reactor, a Pressurized Water Reactor, was selected by the European Commission as one of the four pilot dismantling projects in the framework of the EC five year RTD program on dismantling nuclear installations. Through this project, SCK-CEN has built up a broad know-how in dismantling and decommissioning operations. This know how concerns the decontamination for dose rate reduction and/or free release of materials, tele-operated techniques for cutting highly activated components of a reactor, concrete decontamination techniques, characterization techniques of radioactive waste or for free release of components and development of decommissioning management and record-keeping of material streams and of nuclear material accountancy. SCK-CEN is now actively involved in other decommissioning projects in Belgium and in expertise abroad. After giving an overview of the main achievements and the perspectives of the decommissioning of the BR3 reactor, the paper intends to present the involvement of SCK-CEN in the other decommissioning projects and to give an overview of our activities and capacities. (authors)

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Emerging Technologies and Techniques for Wide Area Radiological Survey and Remediation

Technologies to survey and decontaminate wide-area contamination and process the subsequent radioactive waste have been developed and implemented following the Chernobyl nuclear power plant release and the breach of a radiological source resulting in contamination in Goiania, Brazil. These civilian examples of radioactive material releases provided some of the first examples of urban radiological remediation. Many emerging technologies have recently been developed and demonstrated in Japan following the release of radioactive cesium isotopes (Cs-134 and Cs-137) from the Fukushima Dai-ichi nuclear power plant in 2011. Information on technologies reported by several Japanese government agencies, such as the Japan Atomic Energy Agency (JAEA), the Ministry of the Environment (MOE) and the National Institute for Environmental Science (NIES), together with academic institutions and industry are summarized and compared to recently developed, deployed and available technologies in the United States. The technologies and techniques presented in this report may be deployed in response to a wide area contamination event in the United States. In some cases, additional research and testing is needed to adequately validate the technology effectiveness over wide areas. Survey techniques can be deployed on the ground or from the air, allowing a range of coverage rates and sensitivities. Survey technologies also include those useful in measuring decontamination progress and mapping contamination. Decontamination technologies and techniques range from non-destructive (e.g., high pressure washing) and minimally destructive (plowing), to fully destructive (surface removal or demolition). Waste minimization techniques can greatly impact the long-term environmental consequences and cost following remediation efforts. Recommendations on technical improvements to address technology gaps are presented together with observations on remediation in Japan.

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Assessment of Contaminated Brine Fate and Transport in MB139 at WIPP

Following the radionuclide release event of February 14, 2014 at the Waste Isolation Pilot Plant (WIPP), actinide contamination has been found on the walls and floor in Panel 7 as a result of a release in Room 7 of Panel 7. It has been proposed to decontaminate Panel 7 at the WIPP by washing contaminated surfaces in the underground with fresh water. A cost-effective cleanup of this contamination would allow for a timely return to waste disposal operations at WIPP. It is expected that the fresh water used to decontaminate Panel 7 will flow as contaminated brine down into the porosity of the materials under the floor – the run-of-mine (ROM) salt above Marker Bed 139 (MB139) and MB139 itself – where its fate will be controlled by the hydraulic and transport properties of MB139. Due to the structural dip of MB139, it is unlikely that this brine would migrate northward towards the Waste-Handling Shaft sump. A few strategically placed shallow small-diameter observation boreholes straddling MB139 would allow for monitoring the flow and fate of this brine after decontamination. Additionally, given that flow through the compacted ROM salt floor and in MB139 would occur under unsaturated (or two-phase) conditions, there is a need to measure the unsaturated flow properties of crushed WIPP salt and salt from the disturbed rock zone (DRZ).

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Iodine Adsorption by Ag-Aerogel under Prototypical Vessel Off-Gas Conditions

U.S. regulations will require the removal of 129 I from the off-gas streams of any used nuclear fuel (UNF) reprocessing plant prior to discharge of the off-gas to the environment. The required plant decontamination factor for iodine will vary based on fuel burnup, cooling time, and other factors but is very likely to be >1000 and could be as high as 8000. Multiple off-gas streams within a UNF reprocessing plant combine prior to environmental release, and each of these streams contains some amount of iodine. To achieve the decontamination factors (DFs) that are likely to be required by regulations, iodine removal from the vessel off-gas will be necessary. The vessel off-gas contains iodine at very dilute concentrations (ppb levels), and will also contain water vapor. Iodine species present are likely to include both elemental and organic iodides. There will also be solvent vapors and volatile radiolysis products. The United States has considered the use of silver-based sorbents for removal of iodine from UNF off-gas streams, but little is known about the behavior of those sorbents at very dilute iodine concentrations. The purpose of this study was to expose silver-functionalized silica aerogel (AgAerogel) to a prototypical vessel off-gas stream containing 40 ppb methyl iodide to obtain information about organic iodine capture by silver-sorbents at very low iodine concentrations. The design of this extended duration testing was such that information about the rate of adsorption, the penetration of the iodine species, and the overall system DF could be obtained. Results show that CH 3 I penetrates into a AgAerogel sorbent bed to a depth of 3.9 cm under prototypical vessel off-gas conditions. An iodine loading of 22 mg I/g AgAerogel was observed in the first 0.3 cm of the bed. Of the iodine delivered to the system, 48% could not be accounted for, and future efforts will investigate this concern. Direct calculation of the decontamination factor is not possible, as no iodine was observed to break through the sorbent beds. Continued studies on the adsorption of iodine from prototypical vessel off-gas streams by silver-based sorbents will attempt to resolve some of the questions raised here, both regarding mass balance and the effect of aging on iodine adsorption by AgAerogel from a dilute gas stream. Additionally, the adsorption of different iodine species, such as I 2 and C 12 H 25 I will be studied. Other variables that merit examination are the gas velocity of the test and the dependence of the observed results on the inlet iodine concentration. Finally, longer duration testing should be considered in an effort to determine the mass transfer zone associated with iodine adsorption by AgAerogel under prototypical vessel off-gas conditions. The estimation of mass transfer zone is required for any future industrial implementation.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

The 1976 Hanford Americium Accident: Then and Now

The 1976 chemical explosion of an 241Am ion exchange column at a Hanford Site waste management facility resulted in the extreme contamination of a worker with 241Am, nitric acid and debris. The worker underwent medical treatment for acid burns, as well as wound debridement, extensive personal skin decontamination and long-term DTPA chelation therapy for decorporation of americium-241. Because of the contamination levels and prolonged decontamination efforts, care was provided for the first three months at the unique Emergency Decontamination Facility with gradual transition to the patient’s home occurring over another two months. The medical treatment, management, and dosimetry of the patient have been well documented in numerous reports and journal articles. The lessons learned with regard to patient treatment and effectiveness of therapy still form the underlying philosophy of treatment for contaminated injuries. Changes in infrastructure and facilities as well as societal expectations make for interesting speculation as to how responses might differ today.

accident↗

Development and Qualification of Advancements in Submersible Transfer Pump Performance and Life, and Implications for Advancing and Supporting Processing Options - 13343

From the 1950's through the 1990's, relatively inexpensive, 'off-the-shelf' type, vertical turbine pumps (VTP) were used to transfer Hanford waste. The technology of those pumps was rooted primarily in the mining and agricultural (irrigation) industries. HNF-3218, Double Shell Tank (DST) Transfer Pump History and Reliability Report, 1998, provides a summary of Hanford DST pump history to that date. Such pumps operated in the Hanford radioactive waste environment for an average of only 400 hours before failure. However, at that time, operating life was not a driving criteria within the Department of Energy (DOE) complex, as the failure of transfer pumps represented a relatively low replacement and disposal cost. The Environmental Protection Agency (EPA) issuance of the 'Debris Rule' in 1992, which mandated that mixed radioactive waste contaminated equipment be decontaminated to a 'low level waste' category prior to burial, elevated the significance of transfer pump reliability and decontamination capability as life-cycle cost criteria. Minimizing the frequency of transfer pump failures and design for decontamination became significantly important and served to drive the need toward specific, designed for application pumps to meet this challenge. To this end, Washington River Protection Solutions (WRPS) and the supplier, Curtiss-Wright EMD (EMD), have recently collaborated on an intense program to further transfer pump technology and performance. (authors)

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Dismantling of Loop-Type Channel Equipment of MR Reactor in NRC 'Kurchatov Institute' - 13040

In 2009 the project of decommissioning of MR and RTF reactors was developed and approved by the Expert Authority of the Russian Federation (Gosexpertiza). The main objective of the decommissioning works identified in this project: - complete dismantling of reactor equipment and systems; - decontamination of reactor premises and site in accordance with the established sanitary and hygienic standards. At the preparatory stage (2008-2010) of the project the following works were executed: loop-type channels' dismantling in the storage pool; experimental fuel assemblies' removal from spent fuel repositories in the central hall; spent fuel assembly removal from the liquid-metal-cooled loop-type channel of the reactor core and its placement into the SNF repository; and reconstruction of engineering support systems to the extent necessary for reactor decommissioning. The project assumes three main phases of dismantling and decontamination: - dismantling of equipment/pipelines of cooling circuits and loop-type channels, and auxiliary reactor equipment (2011-2012); - dismantling of equipment in underground reactor premises and of both MR and RTF in-vessel devices (2013-2014); - decontamination of reactor premises; rehabilitation of the reactor site; final radiation survey of reactor premises, loop-type channels and site; and issuance of the regulatory authorities' de-registration statement (2015). In 2011 the decommissioning license for the two reactors was received and direct MR decommissioning activities started. MR primary pipelines and loop-type facilities situated in the underground reactor hall were dismantled. Works were also launched to dismantle the loop-type channels' equipment in underground reactor premises; reactor buildings were reconstructed to allow removal of dismantled equipment; and the MR/RTF decommissioning sequence was identified. In autumn 2011 - spring 2012 results of dismantling activities performed are: - equipment from underground rooms (No. 66, 66A, 66B, 72, 64, 63) - as well as from water and gas loop corridors - was dismantled, with the total radwaste weight of 53 tons and the total removed activity of 5,0 x 10{sup 10} Bq; - loop-type channel equipment from underground reactor hall premises was dismantled; - 93 loop-type channels were characterized, chopped and removed, with radwaste of 2.6 x 10{sup 13} Bq ({sup 60}Co) and 1.5 x 10{sup 13} Bq ({sup 137}Cs) total activity removed from the reactor pool, fragmented and packaged. Some of this waste was placed into the high-level waste (HLW) repository of the Center. Dismantling works were executed with application of remotely operated mechanisms, which promoted decrease of radiation impact on the personnel. The average individual dose for the personnel was 1.9 mSv/year in 2011, and the collective dose is estimated as 0.0605 man x Sv/year. (authors)

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D and D: Dismantling and Release of Large Components at the GNS Premises in Duisburg on the Example of a CASTOR S1 Container - 13536

There are a lot of metallic large components for the transport of radioactive waste in Germany. Some of these large components like for example the Castor S1 with 82 Mg are so old, that the transport via streets is not possible because the permission is not valid anymore. The application for a new permission is economically not reasonable. Out of this reason the large components need to be decontaminated and recycled to use them again in the economic cycle. Decontamination of large components by cleaning/removing the surface for example with beam technology is a very time-consuming release procedure. Manufacturing a specialized machine for decontamination and creation of a new surface was the intention of this project. The objective was to save interim storage and final repository volume and costs as well as developing a process that is nationally and internationally usable. 90% of the volume/mass of waste could be released and therefore possibly re-used. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Agricultural approaches of remediation in the outside of the Fukushima Daiichi nuclear power plant

This paper outlines agricultural approaches of remediation activity done in contaminated areas around the Fukushima Daiichi Nuclear Power Plant. About the decontamination examination of contaminated areas, we have tried the land scale test of a rice field before and after planting by the use of currently recommended methods. Since farmers would carry out the land preparation by themselves, generation of secondary radioactive waste should be as low as possible through the decontamination works. For the radioactive nuclide migration control of rice by wet rice production, several types of decontamination methods such as zeolite addition and potassium fertilization in the soil have been examined. The results are summarized in the 4 following points. 1) Plowing and water discharge are effective for removing radioactive cesium from rice field. 2) Additional potassium fertilization is effective for reducing cesium radioactivity in the product. 3) No significant difference is observed with or without the zeolite addition. 4) Very low transfer factor of cesium from soil to brown rice has been obtained compared with literature values.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Preparing for safe and compliant open air demolition at Hanford's plutonium finishing plant - 15100

The Plutonium Finishing Plant (PFP), located in the 200 West Area of the U.S. Department of Energy (DOE) Hanford Site, began operations in 1949 and produced plutonium metal during the Cold War. Production was stopped in 1989, the facility was formally shut-down in 1996, and material stabilization completed in 2004. DOE contractor CH2M HILL Plateau Remediation Company (CH2M HILL) is tasked with the plant's deactivation, decommissioning, decontamination and demolition, to be completed by September 30, 2016. The project team, partnering with DOE-Richland Operations Office (DOE-RL), is exploring, evaluating and implementing efficiencies to safely and compliantly prepare the facility for demolition. Since 2008, employees have prepared approximately 75 percent of the complex for demolition. More than 90 percent of the 232 glove boxes have been removed from ventilation and more than 80 percent of pencil tank units have been dispositioned. As decontamination, deactivation and removal nears completion on the remaining glove boxes, pencil tanks and other radiological and chemical processing infrastructure, CH2M HILL and DOE-RL are making preparations to demolish PFP itself, a Hazardous Category II nuclear facility (HazCat II). Conventional techniques used to demolish buildings heavily contaminated with radiological hazards typically involve extensive hands-on work to remove Material at Risk (MAR) and decontaminate the building to low levels before conventional demolition techniques can be used to remove the building. A safe and more cost effective approach is packaging MAR located in hard to access areas of the plant and removing it during demolition. That process, combined with affixing remaining contamination to walls, floors and equipment, performing detailed air dispersion modeling before demolition and air monitoring and dust suppression during demolition, will reduce employee risk and is more efficient in demolishing a HazCat II facility. (authors)

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Considerations for recovery of large areas of a nuclear facility for re-use - 15147

This paper highlights a number of factors an organization might consider for recovery of a facility, using a successful example from the UK. In 2013 a power failure led to the shutdown of the ventilation system that caused loose contamination to be deposited over large sections of man-accessible areas of plant after the evacuation of personnel. The successful initiation of emergency Command and Control arrangements during the Response phase, saw several key responders brought together to offer technical direction across many disciplines. The actions of the Command and Control unit prevented any further spread contamination to other areas of the facility and any external release. This enabled the return of the plant to an operational status which forms an important mission enabler for the site hazard reduction programme. Intervention at an early stage during the Response phase of the incident saw the cessation of traditional dilute chemical wet decontamination approach that would otherwise leave a legacy of slow leaching contamination; to that of containment and ultimate removal of loose contamination using strippable coatings. Doing so established a more rapid and reliably 'clean' access or pathway into the plant to establish the full extent of the situation. The scale and scope of the decontamination requirement was steadily revealed through a number of controlled re-entries to the plant. A number of other techniques were considered and employed to address the different areas making use of available plant resources to deliver the successful 'self-help' recovery of the plant using multi-disciplinary teams. As Response switched to Recovery, it was important to set out and agree which strategic option should be adopted to return the facility to normal operation. Equally, it was necessary to verify which equipment had been affected by the power outage and repair as required. Furthermore, equipment with designated safety functions had to be maintained alongside the Recovery activities. A careful balance of priorities demanded an unparalleled depth of plant knowledge to address this, whilst still keeping site and external stakeholders informed. The engagement by the plant workforce to take on the decontamination challenge to enable recovery of their plant supported by other teams formed a critical step in the speed of recovery. (authors)

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The potential of high-frequency forced pulsed water jet for nuclear decommissioning - 15367

Forced Pulse Water Jetting (FPWJ) has been demonstrated in other works as a credible and consistent method for removing coatings or otherwise preparing surfaces across numerous industries. Its applicability to the nuclear industry as a powerful tool for decommissioning and waste treatment has only recently being recognized and underpinning study is required before any deployment can be considered. Use of FPWJ within the nuclear sector for decommissioning and waste treatment, requires a different degree of surface finish to achieve a decontamination effect or an assured performance. This necessitates a greater erosion of the base metal than in other industries. The addition of a Forced Pulse Modulation Unit (FPMU) to a high pressure water jetting system offers performance shifts akin to the differences between High Pressure (HP) and Ultra High Pressure (UHP) water jets. Trials have been undertaken in a controlled environment to establish the number of cycles to achieve a given mass loss and or depth of penetration that would otherwise provide decontamination of mostly flat or simple geometry surfaces using a robotic arm for consistency and safety. It has also been shown that metalwork can be readily penetrated without risk of explosion, for example to allow draining of a gas cylinder. Most nuclear facilities have a plethora of pipe systems spanning various diameters. A considerable portion of the UK Sellafield site has 2 inch bore pipe. The FPMU technology is being adapted to consider applications in enclosed systems, such as decontamination of pipes. Exploratory works to date show there to be many physical attributes that influence performance that include, standoff of the jet, established propagated forced pulse jet length, interference from resultant water spray and angle of attack. Comparatively small changes to these parameters can have a profound effect on performance. The process is capable of removing 10's microns to several mms of metal progressively and repeatedly. This enables a credible potential treatment of plant and equipment at Intermediate Level Waste and High Level Waste thresholds. In considering this as a treatment method, a balance between performance, cost and environmental impact of effluents must be made and will be studied further during future active trials. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

A 'Method Based Survey' Succeeds in a Spanish Scrap Clearance Project - 15664

During the last years, a Waste Minimization Project has been implemented in Cofrentes NPP in a collaborative effort performed by IBERDROLA and ENRESA. The final result has been more than 760 t of metallic scrap including containerised materials but also massive surface contaminated objects have been managed and finally cleared. The initial project scope included 10 spent fuel pool racks weighting 130 tones but limited testing demonstrated they presented high contamination levels and were managed as radwaste including down-sizing and conditioning in ENRESA standard radwaste containers for metallic scrap (CMT's). This project started in 2008 and finished just in the summer of 2014. During these years planning and licensing, procurement, execution, including, a huge effort in decontamination and clearance measurement, was developed. The project closure is developing actually. The residual materials were stored and initially characterized previously its down-sizing and decontamination using chemical baths (warm diluted sulfuric acid and ultrasounds) , blasting (water jetting with iron grit) and in special cases mopping using industrial cleaners). Some big items were decontaminated previously its down-sizing. The materials were cleared using an approach similar to MARSAME approach based in MARSSIM guidelines. The 160 containers needed six in situ gamma spectrometry measurements each and 115 massive (from 0.45 t to 13.7 t) items need at least so many measurements as total surface in square meters. In total 763 t were cleared with only 0.6 t rejected and treated as radwaste. (authors)

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