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All sourcesNASA NTRSDOE OSTI
DOE OSTI2015

NPP financial and regulatory risks-Importance of a balanced and comprehensive nuclear law for a newcomer country considering nuclear power programme

The nature of Nuclear Power Plant (NPP) projects are: long duration (10-15 years for new build), high capital investment, reasonable risks and highly regulated industries to meet national and international requirement on Safety, Security, Safeguards (3S) and Liabilities. It requires long term planning and commitment from siting to final disposal of waste/spent fuel. Potential financial and regulatory risks are common in massive NPP projects and will be magnified in the case of using unproven technology. If the risks are not properly managed, it can lead to high project and operation costs, and, fail to fulfil its objectives to provide compatible electricity prices and. energy security. To ensure successful, the government and investors need to ensure that the NPP project is bankable with low cost of project and funding, have fair treatment and proper risk mitigation, and able to complete on time with no cost overrun. One of the requirements as prerequisite for the development of NPP as stipulated by the International Atomic Energy Agency (IAEA) is the establishment of a Legal and Regulatory Framework. The main objective of nuclear law is to ensure that the activities and projects carried-out in the country are legal and compliant to national and international requirements. The law should also be able to provide fair treatment of risks on its activities that is acceptable to investors. The challenge for a newcomer country is to develop a balanced and comprehensive national nuclear law that meet these objectives while taking into consideration various stakeholders’ interest without compromising on safety, security, safeguard, liability requirements and other international obligations. This paper highlights the nature of NPP projects, its potential and associated financial and regulatory risks, and its major concerns and challenges. It proposes possible risks treatment and mitigation through the formulation of a balanced and comprehensive legislation by clear understanding of various requirements of public, regulators, investors, financial institutions, international community, operator and other important stakeholders. Ambiguities and uncertainties, especially with regards to certain conditions and requirements should be minimised by emulating good practices of experienced nuclear regulators. The imposition of various financial requirements such as funds for decommissioning, radioactive waste management, financial security, nuclear liabilities and licensing fees are necessary, but at the same time the quantum needs to be clearly defined. Concerns on absolute liability of the operators need to be addressed through a creation of necessary and proper nuclear insurance legislations to mitigate operator S nuclear liability obligations and other financial risks. Another major risk to investors is the possibility of public resistance which will not only can hinder the construction but can also stop operation of the nuclear power plant which will contribute to huge losses to investors and countries. This may require a provision in the legislation that provide proper compensation for these situations and at the same time to allow operators to engage in nuclear promotional activities, such as community benefit and public consultation as voluntary initiatives. Through proper planning, research, consultation and execution, the proposed nuclear law shall be able to promote good regulatory practices for public and investors’ confidence and benefit. Early involvement of various stakeholders is essential as a platform for regular communications between regulators and interested parties. Stakeholders’ participation in the NPP programme and law developments will also promote transparency of the projects while upholding the independency of the regulators.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Preliminary Insights on Potential Transitions to Closed Thorium-Based Fuel Cycles

Closed fuel cycles with comprehensive recycle strategies are often regarded as the logical and desired end-states of long-term nuclear energy strategies; such options offer potential improvements in terms of resource supply and sustainability, waste management, and potentially nuclear security. In the DOE-NE Fuel Cycle Option Campaign report, systems with closed recycle strategies (both uranium- and thorium-based) generally dominated strategies with less comprehensive recycle approaches across many performance metrics. That being said, developing momentum to transition from the current global implementation of once-through fuel cycles has proven challenging. Intermediate paths en route to closed fuel cycles have not been readily elucidated; this is especially true for thorium-based options. A comparatively extensive amount of work has been conducted on transitions to closed fuel cycles based on uranium and plutonium, generally based on an endpoint of sodium-cooled fast reactors (SFRs). In contrast, corresponding analyses for thorium-based options are limited. Early estimates, without the benefit of full-scale modeling, were performed in conjunction with the Molten Salt Fast Reactor (MSFR) design. There is some transition analysis work associated with the Japanese THORIMS-NES molten salt design, but the scope of this work was not directly comparable with the SFR-oriented analyses and considered the thorium fission reactors as an intermediate state en route to the global deployment of accelerator-driven systems. Others have considered thorium recently, but not in a closed-recycle context. To begin to resolve this gap, this paper describes a high-level analysis and initial perspectives on the topic of transitions to closed thorium-based cycles. The emphasis on this paper is not on the specific quantitative results that are described, although some of the overall takeaways from these trends may still be useful. Instead, this paper describes the need for such analyses to be conducted, describes the methodologies by which this can be accomplished, and reports an initial demonstration of these methodologies for a specific transition candidate scenario. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Development of an Experimental Approach for Thermal Testing in Bedded Salt - 19431

Safe and permanent isolation of used nuclear fuel (UNF) and high-level nuclear waste (HLW) is an integral component of the cradle-to-grave philosophy of radioactive waste management. Out of the multitude of rock types considered for the permanent deep disposal of nuclear waste (tuff, shale, granite, clay, and salt), salt has received significant interest particularly because of the advantage offered by salt as an impermeable and dry medium with self-sealing properties. The concept of HLW disposal in salt has been investigated through several testing campaigns in the U.S. and in Germany. Serval knowledge gaps still exist in our understanding of how brine is generated and how it transports under heat generating conditions. These knowledge gaps limit our ability to build a robust safety case for the disposal of heat generating waste in salt. The current manuscript reports on efforts performed to develop a field-testing campaign to study brine and water vapor migration in heated salt. The paper summarizes initial work done in a phased thermal testing program in bedded salt at the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico. The testing to date has been focused on existing boreholes and is being used to 'shakedown' the process for implementation of a more refined testing program that will be implemented in freshly drilled boreholes planned for FY2019. We designed and deployed a heater assembly that consisted of a packer, borehole deformation gauge, heater block, a network of thermocouples, and a pressure transducer setup to measure in situ temperature and pressure. The assembly was deployed in an existing borehole and several heating and cooling experiments were performed to test the performance of the different instruments fielded. We report on the results obtained for brine generation as a function of time and heating and cooling cycles and temperature evolution in the rock salt. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2025

Spent nuclear fuel receipt rate analysis within an integrated waste management system (IWMS) architecture that includes consolidated storage

A key parameter in analyzing the performance of an integrated waste management system (IWMS) architecture for the disposition of spent nuclear fuel (SNF) is the SNF receipt rate from reactor and other custodian sites. Receipt rate in this paper means how much SNF is accepted per year for transport in the IWMS from such sites. Introducing one or more federal consolidated interim storage facilities (CISFs) into the IWMS architecture can potentially accelerate the receipt rate profile over time relative to system architectures without a CISF. This raises the question of what an optimal SNF receipt rate profile for an IWMS architecture might be in view of practical constraints and desired system performance attributes and associated metrics. This paper describes a sensitivity study on SNF receipt rates and the associated results for a selected set of IWMS scenarios aimed at informing near-term planning for interim storage capabilities and transportation assets. Two different strategies for CISF operation while awaiting availability of a disposal system to receive SNF are compared: one that relatively quickly fills an initial CISF and then idles the transportation system; and another that aims for more continuous use of transportation assets and receipt capabilities at the CISF. This study examines cost considerations and other factors, such as the timing of clearing reactor sites of SNF, efficient use of capital assets, and some other metrics that might be important to a CISF host community. Based on the analysis, an initial approach is presented that targets a continuous receipt strategy while maintaining the flexibility to step up receipt capabilities to a reasonable degree when needed and beneficial, within overall system constraints.

11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2013

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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DOE OSTI2019

Dissolved Air Flotation for Rapid Dewatering and Separation of Legacy Sludge Wastes - 19065

As a low footprint, high efficiency separation process, Dissolved Air Floatation (DAF) could effectively be retrofitted into existing waste management facilities at nuclear sites such Sellafield and Hanford to rapidly separate particulates from aqueous suspensions. The simplicity (no moving parts) and size of this technology coupled with low cost of construction and reagent purchase would also be ideal for ease of facility decommissioning with minimum impact to secondary waste generation. For this study, methyl isobutyl carbinol (MIBC) was used in this research as a frothing agent to produce a preferable stable foam. Mg(OH){sub 2} was selected as a test material as it is the result of long term corrosion of Magnox fuel in UK nuclear fuel storage ponds. Due to the cationic nature of the Mg(OH){sub 2} test material, the anionic surfactant, Sodium Dodecyl Sulphate (SDS) was used as collector to modify the surface properties to increase hydrophobicity. The performance of anionic SDS in floating 2.5%v/v Mg(OH){sub 2} was compared to the adsorption isotherm of SDS on Mg(OH){sub 2} to determine monolayer coverage surfactant dose which was investigated using Total Organic Carbon (TOC). SDS was found to increase particulate recovery to 93% with some water carry-over observed and it was found that particle bubble attachment was optimum for a select particle size distribution. This study proved that potential application of flotation as an efficient viable dewatering technique for common magnesium hydroxide based legacy wastes, using cheap, readily available collector and frother agents. (authors)

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DOE OSTI2013

Safety and Security of Radioactive Sealed and Disused/Orphan Sources in Ukraine - German Contribution - 13359

Within the scope of 'Nuclear Security of Radioactive Sources', the German government implemented the modernization of Ukrainian State Production Company's transport and storage facility for radioactive sources (TSF) in Kiev. The overall management of optimizing the physical protection of the storage facility (including the construction of a hot cell for handling the radioactive sources) is currently carried out by the German Federal Foreign Office (AA). AA jointly have assigned Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Germany's leading expert institution in the area of nuclear safety and waste management, to implement the project and to ensure transparency by financial and technical monitoring. Sealed radioactive sources are widely used in industry, medicine and research. Their life cycle starts with the production and finally ends with the interim/long-term storage of the disused sources. In Ukraine, IZOTOP is responsible for all radioactive sources throughout their life cycle. IZOTOP's transport and storage facility (TSF) is the only Ukrainian storage facility for factory-fresh radioactive sources up to an activity of about 1 million Ci (3.7 1016 Bq). The TSF is specially designed for the storage and handling of radioactive sources. Storage began in 1968, and is licensed by the Ukrainian state authorities. Beside the outdated state of TSF's physical protection and the vulnerability of the facility linked with it, the lack of a hot cell for handling and repacking radioactive sources on the site itself represents an additional potential hazard. The project, financed by the German Federal Foreign Office, aims to significantly improve the security of radioactive sources during their storage and handling at the TSF site. Main tasks of the project are a) the modernization of the physical protection of the TSF itself in order to prevent any unauthorized access to radioactive sources as well as b) the construction of a hot cell to reduce the number of transports of radioactive sources within the city of Kiev. In future, the new established hot cell at IZOTOP's transport and storage facility will be useful for identification and characterization of orphan/disused radioactive sources. The projects implemented are performed in accordance with international recommendations (e. g. IAEA) and national normative documents and will make a crucial contribution towards an improved safety and security management of radioactive sources in Ukraine. (authors)

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DOE OSTI1996

Nuclear Safety [Vol. 37, No. 1, January-March 1996]

Nuclear Safety is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Table of Contents for this issue follows. GENERAL SAFETY CONSIDERATIONS: 1 A Decision Support System for Maintenance Management of a Boiling-Water Reactor Power Plant, J. H. Shen, A. Ray, and S. Levine; ACCIDENT ANALYSIS: 12 On Prediction of the Ignition Potential of Uranium Metal and Hydride, M. Epstein, W. Luangdilok, M. G. Plys, and H. K. Fauske; 26 An Overview of the Primary Parameters and Methods for Determining Condensation Heat Transfer to Containment Structures, J. Green and K. Almenas; DESIGN FEATURES: 49 Modem Tornado Design of Nuclear and Other Potentially Hazardous Facilities, J. D. Stevenson and Y. Zaho; U.S. NUCLEAR REGULATORY COMMISSION INFORMATION AND ANALYSES: 73 1994 Accident Sequence Precursor Program Results, R. J. Belles, J. W. Cletcher, D. A. Coplnger, B. W. Dolan, J. W. Minarick, and P. D. O'Reilly; ANNOUNCEMENTS: 93 American Institute of Chemical Engineers (AlChE) Spring 1997 National Meeting; 94 European Safety and Reliability Association International Conference on Safety and Reliability ESREL ’97; 95 Criticality Safety Challenges in the Next Decade; 96 21st International Symposium on the Scientific Basis for Nuclear Waste Management; 84 The Authors; 88 Letter to the Editor; 90 Indexes to Nuclear Safety, Volume 36.

05 NUCLEAR FUELS↗
DOE OSTI1996

Nuclear Safety [Vol. 37, No. 1, January-March 1996]

Nuclear Safety is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Table of Contents for this issue follows. GENERAL SAFETY CONSIDERATIONS: 1 A Decision Support System for Maintenance Management of a Boiling-Water Reactor Power Plant, J. H. Shen, A. Ray, and S. Levine; ACCIDENT ANALYSIS: 12 On Prediction of the Ignition Potential of Uranium Metal and Hydride, M. Epstein, W. Luangdilok, M. G. Plys, and H. K. Fauske; 26 An Overview of the Primary Parameters and Methods for Determining Condensation Heat Transfer to Containment Structures, J. Green and K. Almenas; DESIGN FEATURES: 49 Modem Tornado Design of Nuclear and Other Potentially Hazardous Facilities, J. D. Stevenson and Y. Zaho; U.S. NUCLEAR REGULATORY COMMISSION INFORMATION AND ANALYSES: 73 1994 Accident Sequence Precursor Program Results, R. J. Belles, J. W. Cletcher, D. A. Copinger, B. W. Dolan, J. W. Minarick, and P. D. O'Reilly; ANNOUNCEMENTS: 93 American Institute of Chemical Engineers (AlChE) Spring 1997 National Meeting; 94 European Safety and Reliability Association International Conference on Safety and Reliability ESREL ’97; 95 Criticality Safety Challenges in the Next Decade; 96 21st International Symposium on the Scientific Basis for Nuclear Waste Management; 84 The Authors; 88 Letter to the Editor; 90 Indexes to Nuclear Safety, Volume 36.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

International Network for Nuclear Waste Characterization (IAEA-Labonet) - Facts and Future - 18566

LABONET was launched early 2011 by the International Atomic Energy Agency (IAEA) as an international network on nuclear waste characterization. Its objective is to improve the quality of, and harmonize, activities related to the radioactive waste characterization in IAEA Member States. It is widely accepted that proper characterization of radioactive waste through its entire flow-sheet is a key activity. In particular the needs and problems in radioactive waste characterization in the participating countries are a main concern within LABONET, as the programs are not elaborated to the same level in the various countries. LABONET wants to facilitate the exchange of international experience in the application of proven, quality assured practices for the characterization of waste and waste packages. This will be beneficial for the less developed countries. The objectives of LABONET are achieved via different actions: a) exchanging information and expertise via presentations and discussions at technical meetings; b) expert meetings on particular topics of interest, for instance e-learning and e-platforms; c) training sessions in less developed countries, for instance, on non-destructive assay of waste packages; d) facilitate the exchange of information amongst its members; and e) assist member states in establishing characterization plans that are cost effective and of good quality. LABONET is continuously encouraging institutions or professionals who need some assistance or can help in solving questions about characterization to be a member. Currently, LABONET is preparing for its future, including projects addressing common problems of its members. Aiming at the dissemination of this important network for the professionals involved in radioactive waste characterization, this paper will discuss the following issues: (1) the objectives of LABONET, (2) its structure, membership and organization of meetings, (3) some achievements, and (4) plans for the future. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Regulatory Compliance Strategy For Recovery-Driven Underground Ventilation System Changes - 16355

The Waste Isolation Pilot Plant (WIPP) facility is managed and operated by Nuclear Waste Partnership LLC (NWP) for the U.S Department of Energy (DOE). On February 14, 2014, a radiological event occurred in the WIPP facility underground repository, which resulted in the release of transuranic isotopes contaminating a portion of the underground primarily along the ventilation path from Panel 7, the location of the incident. The release was initially detected by an underground continuous air monitor (CAM) which caused an automatic switch of the ventilation system to filtration mode and ventilation was directed through high-efficiency particulate air (HEPA) filtration banks located in the surface exhaust building. When the HEPA filtration was engaged, the underground normal ventilation was reduced from 425,000 standard cubic feet per minute (scfm) to 60,000 scfm. Since the event, all exhaust air is filtered through HEPA filters at 60,000 scfm to minimize the possibility of exposure to workers, the public and the environment. Ventilation of fresh air to the WIPP underground is a primary limitation to performing underground recovery activities; therefore, recovery-driven ventilation changes are needed. The safe recovery of the WIPP facility and resumption of normal waste emplacement activities require an increase in ventilation capacity to be accomplished in three phases: 1) Interim Ventilation System, 2) Supplemental Ventilation System and 3) Permanent Ventilation System. Each phase adds increased air flow to the underground and allows for underground activities to be performed concurrently. The regulatory strategy for ventilation recovery focuses on ensuring that needed changes to the WIPP facility are protective of human health and the environment. Recovery-driven ventilation changes are implemented using the procedures, processes, and regulations that are required by the two primary regulatory agencies for the WIPP facility: the U.S. Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) as well as DOE requirements. Regulatory compliance is being achieved for the three ventilation phases to restore underground ventilation by providing the regulators and stakeholders opportunities for involvement during the design and development processes. A strategy for a tiered NMED permitting process and a plan for developing required EPA documentation are under consideration. The Project's objective is to resume normal waste emplacement activities with safety, protection of the public, the worker and the environment as the highest priorities. Important elements of ensuring that WIPP facility recovery and future waste emplacement activities occur as planned are transparency and communication with the regulatory community. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2012

Preparing Los Alamos National Laboratory's Waste Management Program for the Future - 12175

The waste management program at Los Alamos National Laboratory (LANL) is undergoing significant transition to establish a lean highly functioning waste management program that will succeed the large environmental cleanup waste management program. In the coming years, the environmental cleanup activities will be mostly completed and the effort will change to long-term stewardship. What will remain in waste management is a smaller program focused on direct off-site shipping to cost-effectively enable the enduring mission of the laboratory in support of the national nuclear weapons program and fundamental science and research. It is essential that LANL implement a highly functioning efficient waste management program in support of the core missions of the national weapons program and fundamental science and research - and LANL is well on the way to that goal. As LANL continues the transition process, the following concepts have been validated: - Business drivers including the loss of onsite disposal access and completion of major environmental cleanup activities will drive large changes in waste management strategies and program. - A well conceived organizational structure; formal management systems; a customer service attitude; and enthusiastic managers are core to a successful waste management program. - During times of organizational transition, a project management approach to managing change in a complex work place with numerous complex deliverables is successful strategy. - Early and effective engagement with waste generators, especially Project Managers, is critical to successful waste planning. - A well-trained flexible waste management work force is vital. Training plans should include continuous training as a strategy. - A shared fate approach to managing institutional waste decisions, such as the LANL Waste Management Recharge Board is effective. - An efficient WM program benefits greatly from modern technology and innovation in managing waste data and reports. - Use of six-sigma tools can help improve the quality and efficiency of waste management processes. - A fair, easy to understand, transparent, and well-overseen process for distributing the cost of waste disposal and waste program oversight is essential. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

The Cementitious Barriers Partnership (CBP) Software Toolbox Capabilities In Assessing The Degradation Of Cementitious Barriers

The Cementitious Barriers Partnership (CBP) Project is a multi-disciplinary, multi-institutional collaboration supported by the U.S. Department of Energy (US DOE) Office of Tank Waste and Nuclear Materials Management. The CBP program has developed a set of integrated tools (based on state-of-the-art models and leaching test methods) that help improve understanding and predictions of the long-term structural, hydraulic and chemical performance of cementitious barriers used in nuclear applications. Tools selected for and developed under this program have been used to evaluate and predict the behavior of cementitious barriers used in near-surface engineered waste disposal systems for periods of performance up to 100 years and longer for operating facilities and longer than 1000 years for waste disposal. The CBP Software Toolbox has produced tangible benefits to the DOE Performance Assessment (PA) community. A review of prior DOE PAs has provided a list of potential opportunities for improving cementitious barrier performance predictions through the use of the CBP software tools. These opportunities include: 1) impact of atmospheric exposure to concrete and grout before closure, such as accelerated slag and Tc-99 oxidation, 2) prediction of changes in Kd/mobility as a function of time that result from changing pH and redox conditions, 3) concrete degradation from rebar corrosion due to carbonation, 4) early age cracking from drying and/or thermal shrinkage and 5) degradation due to sulfate attack. The CBP has already had opportunity to provide near-term, tangible support to ongoing DOE-EM PAs such as the Savannah River Saltstone Disposal Facility (SDF) by providing a sulfate attack analysis that predicts the extent and damage that sulfate ingress will have on the concrete vaults over extended time (i.e., > 1000 years). This analysis is one of the many technical opportunities in cementitious barrier performance that can be addressed by the DOE-EM sponsored CBP software tools. Modification of the existing tools can provide many opportunities to bring defense in depth in prediction of the performance of cementitious barriers over time.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Solidification technology for organic liquid waste combined with solid materials from Cernavoda NPP, Romania - 16453

Canadian Deuterium Uranium (CANDU{sup R}) reactor designs were initially developed in the late 1950's and 1960's by the Atomic Energy of Canada Limited (AECL) in partnership with Ontario Power Generation. CANDU{sup R} 6 reactors are Pressurized Heavy Water Reactors (PHWRs), with an integrated containment system and are designed as either multi or single unit systems. Two single CANDU 6 systems are currently operating at Cernavoda with an additional two units expected to be brought online in the near future. The radioactive waste produced by the plant is currently stored in a waste interim storage facility located on-site. The main sources of radioactive waste in a CANDU plant are: - Primary Heat Transport (PHT) systems, - Moderator systems, - Other sources of radionuclides. The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. During the operation of the Cernavoda NPP, a series of waste streams have been generated for waste treatment purposes. One important waste stream is the combination of solid materials and liquid organic waste, creating flammable solids. Flammable solids represent solid materials, such as cloth, plastic, contaminated with oil containing gamma nuclides and H-3 from maintenance activities. This paper explores a method to solve the problem of liquid residues on solid materials by the application of absorbent materials. The existence of liquid residues on solid materials is a common problem at nuclear power stations globally. The primary issue centers on an effective method of eliminating the liquid to allow for the final acceptance and disposal of the solid waste by regulators. (authors)

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