WorldWideScience

Sample records for caustic nuclear waste

  1. Influence of microstructure on stress corrosion cracking of mild steel in synthetic caustic-nitrate nuclear waste solution

    International Nuclear Information System (INIS)

    The influence of alloy microstructure on stress corrosion cracking of mild steel in caustic-nitrate synthetic nuclear waste solutions was studied. An evaluation was made of the effect of heat treatment on a representative material (ASTM A 516 Grade 70) used in the construction of high activity radioactive waste storage tanks at Savannah River Plant. Several different microstructures were tested for susceptibility to stress corrosion cracking. Precracked fracture specimens loaded in either constant load or constant crack opening displacement were exposed to a variety of caustic-nitrate and nitrate solutions. Results were correlated with the mechanical and corrosion properties of the microstructures. Crack velocity and crack arrest stress intensity were found to be related to the yield strength of the steel microstructures. Fractographic evidence indicated pH depletion and corrosive crack tip chemistry conditions even in highly caustic solutions. Experimental results were compatible with crack growth by a strain-assisted anodic dissolution mechanism; however, hydrogen embrittlement also was considered possible

  2. POTENTIAL FOR STRESS CORROSION CRACKING OF A537 CARBON STEEL NUCLEAR WASTE TANKS CONTAINING HIGHLY CAUSTIC SOLUTIONS

    Energy Technology Data Exchange (ETDEWEB)

    Lam, P.; Stripling, C.; Fisher, D.; Elder, J.

    2010-04-26

    The evaporator recycle streams of nuclear waste tanks may contain waste in a chemistry and temperature regime that exceeds the current corrosion control program, which imposes temperature limits to mitigate caustic stress corrosion cracking (CSCC). A review of the recent service history found that two of these A537 carbon steel tanks were operated in highly concentrated hydroxide solution at high temperature. Visual inspections, experimental testing, and a review of the tank service history have shown that CSCC has occurred in uncooled/un-stress relieved tanks of similar construction. Therefore, it appears that the efficacy of stress relief of welding residual stress is the primary corrosion-limiting mechanism. The objective of this experimental program is to test A537 carbon steel small scale welded U-bend specimens and large welded plates (30.48 x 30.38 x 2.54 cm) in a caustic solution with upper bound chemistry (12 M hydroxide and 1 M each of nitrate, nitrite, and aluminate) and temperature (125 C). These conditions simulate worst-case situations in these nuclear waste tanks. Both as-welded and stress-relieved specimens have been tested. No evidence of stress corrosion cracking was found in the U-bend specimens after 21 days of testing. The large plate test was completed after 12 weeks of immersion in a similar solution at 125 C except that the aluminate concentration was reduced to 0.3 M. Visual inspection of the plate revealed that stress corrosion cracking had not initiated from the machined crack tips in the weld or in the heat affected zone. NDE ultrasonic testing also confirmed subsurface cracking did not occur. Based on these results, it can be concluded that the environmental condition of these tests was unable to develop stress corrosion cracking within the test periods for the small welded U-bends and for the large plates, which were welded with an identical procedure as used in the construction of the actual nuclear waste tanks in the 1960s. The

  3. SORPTION OF URANIUM, PLUTONIUM AND NEPTUNIUM ONTO SOLIDS PRESENT IN HIGH CAUSTIC NUCLEAR WASTE STORAGE TANKS

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L; Bill Wilmarth, B; David Hobbs, D

    2008-05-30

    Solids such as granular activated carbon, hematite and sodium phosphates, if present as sludge components in nuclear waste storage tanks, have been found to be capable of precipitating/sorbing actinides like plutonium, neptunium and uranium from nuclear waste storage tank supernatant liqueur. Thus, the potential may exists for the accumulation of fissile materials in such nuclear waste storage tanks during lengthy nuclear waste storage and processing. To evaluate the nuclear criticality safety in a typical nuclear waste storage tank, a study was initiated to measure the affinity of granular activated carbon, hematite and anhydrous sodium phosphate to sorb plutonium, neptunium and uranium from alkaline salt solutions. Tests with simulated and actual nuclear waste solutions established the affinity of the solids for plutonium, neptunium and uranium upon contact of the solutions with each of the solids. The removal of plutonium and neptunium from the synthetic salt solution by nuclear waste storage tank solids may be due largely to the presence of the granular activated carbon and transition metal oxides in these storage tank solids or sludge. Granular activated carbon and hematite also showed measurable affinity for both plutonium and neptunium. Sodium phosphate, used here as a reference sorbent for uranium, as expected, exhibited high affinity for uranium and neptunium, but did not show any measurable affinity for plutonium.

  4. Radioactive Demonstration of Caustic Recovery from Low-Level Alkaline Nuclear Waste by an Electrochemical Separation Process

    International Nuclear Information System (INIS)

    Bench-scale radioactive tests successfully demonstrated an electrochemical process for the recovery of sodium hydroxide (caustic) from Decontaminated Salt Solution produced from the In-Tank Precipitation and Effluent Treatment Processes at the Savannah River Site (SRS). This testing evaluated two membranes: an organic-based membrane, Nafion Type 350, manufactured by E. I. duPont de Nemours ampersand Company, Inc. (DuPont) and an inorganic-based membrane, NAS D, being developed by Ceramatec. Both membranes successfully separated caustic from radioactive SRS waste.Key findings of the testing indicate the following attributes and disadvantages of each membrane. The commercially-available Nafion membrane proved highly conductive. Thus, the electrochemical cell can operate at high current density minimizing the number of cells at the desired volumetric processing rate. Testing indicated cesium transported across the Nafion membrane into the caustic product. Therefore, the caustic product will contain low-levels of radioactive cesium due to the presence of 134,137Cs in the waste feed. To meet customer requirements, a post treatment stage may prove necessary to remove radioactive cesium resulting in increased overall process costs and decreased cost savings. In contrast to the Nafion membrane, the NAS D membrane demonstrated the production of caustic with much lower levels of gamma radioactivity (137Cs activity was < 51 dpm/g). Therefore, the caustic product could possibly release for onsite/offsite use without further treatment. The NAS D membrane remains in the development stage and does not exist as a commercial product. Operating costs and long-term membrane durability remain unknown.Caustic recovery has been successfully demonstrated in a bench-scale, 2-compartment electrochemical reactor operated for brief periods of time with simulated and radioactive waste solutions and two different types of membranes. The next phase of testing should be directed at (1

  5. INVESTIGATION OF THE POTENTIAL FOR CAUSTIC STRESS CORROSION CRACKING OF A537 CARBON STEEL NUCLEAR WASTE TANKS

    Energy Technology Data Exchange (ETDEWEB)

    Lam, P.

    2009-10-15

    The evaporator recycle streams contain waste in a chemistry and temperature regime that may be outside of the current waste tank corrosion control program, which imposes temperature limits to mitigate caustic stress corrosion cracking (CSCC). A review of the recent service history (1998-2008) of Tanks 30 and 32 showed that these tanks were operated in highly concentrated hydroxide solution at high temperature. Visual inspections, experimental testing, and a review of the tank service history have shown that CSCC has occurred in uncooled/un-stress relieved F-Area tanks. Therefore, for the Type III/IIIA waste tanks the efficacy of the stress relief of welding residual stress is the only corrosion-limiting mechanism. The objective of this experimental program is to test carbon steel small scale welded U-bend specimens and large welded plates (12 x 12 x 1 in.) in a caustic solution with upper bound chemistry (12 M hydroxide and 1 M each of nitrate, nitrite, and aluminate) and temperature (125 C). These conditions simulate worst-case situations in Tanks 30 and 32. Both as-welded and stress-relieved specimens have been tested. No evidence of stress corrosion cracking was found in the U-bend specimens after 21 days of testing. The large plate test is currently in progress, but no cracking has been observed after 9 weeks of immersion. Based on the preliminary results, it appears that the environmental conditions of the tests are unable to develop stress corrosion cracking within the duration of these tests.

  6. Strontium removal from caustic carbonate waste solutions using carrier coprecipitation

    International Nuclear Information System (INIS)

    A carrier coprecipitation procedure has been developed for the radioactive strontium from caustic liquid low-level waste (LLLW) generated at Oak Ridge National Laboratory. The from caustic liquid low-level waste (LLLW) generated at Oak two-step treatment process involves the addition of normal Sr (as SrCl2) to the waste matrix, which is composed primarily of 0.3 M NAOH and 0.6 M Na2CO3. The active Sr equilibrates with the normal Sr carrier and coprecipitates as SrCO3 at pH 13. A liquid/solid separation is made before the pH of the supernate is reduced to pH 8 with sulfuric acid. During the neutralization step, the aluminum in the waste precipitates as Al(OH)3 Further Sr decontamination is achieved as traces of active Sr sorb to the Al(OH)3 that precipitates during the neutralization step. A final liquid/solid separation is made at pH 8 to remove the sorbed active Sr

  7. Biosorption of Copper Ions by Caustic Treated Waste Baker's Yeast Biomass

    OpenAIRE

    Göksungur, Yekta; ÜREN, Sibel; Güvenç, Ulgar

    2003-01-01

    Waste baker's yeast (Saccharomyces cerevisiae) was used as a biosorbent for Cu+2 biosorption. The yeast cells were treated with caustic soda, ethanol and heat to increase their biosorption capacity. Among the treatment methods used, the highest copper uptake (21.1 mg g-1) was obtained with the caustic treatment of baker's yeast. The effect of initial copper concentration and pH on biosorption for caustic treated yeast was studied. The highest Cu+2 uptake (120.7 mg g-1) was obtained ...

  8. Nuclear waste

    International Nuclear Information System (INIS)

    This chapter present a brief overview of the current situation of siting radioactive wastes. This is followed by an overview of various psychological approaches attempting to analyse public reactions to nuclear facilities. It will be argued that public reactions to nuclear waste factilities must be seen in the context of more general attitudes toward nuclear energy. The latter are not only based upon perceptions of the health and environmental risks but are built on values, and sets of attributes which need not be similar to the representations o the experts and policy-makers. The issue of siting nuclear waste facilities is also embedded in a wider moral and political domain. This is illustrated by the importance of equity issues in siting radioactive wastes. In the last section, the implications of the present line of argument for risk communication and public participation in decisions about siting radioactive wastes will be briefly discussed. (author). 49 refs

  9. Nuclear waste

    International Nuclear Information System (INIS)

    Radioactive waste at U.S. nuclear power plants is mounting at a rate of more than 2,000 metric tons a year. Yet the Department of Energy (DOE) does not expect a geologic repository to be available before 2010. In response to concerns about how best to store the waste until a repository is available, GAO reviewed the alternatives of continued storage at utilities' reactor sites or transferring waste to a monitored retrievable storage facility. This paper assesses the likelihood of a monitored retrievable storage facility operating by 1990, legal implications if DOE is unable to take delivery of wastes in 1998, propriety of using the Nuclear Waste Fund from which DOE's waste program costs are paid to pay utilities for on-site storage capacity added after 1998, the ability of utilities to store their waste on-site until a repository is operating, and relative costs and safety of the two storage alternatives

  10. DEVELOPMENT OF A KINETIC MODEL OF BOEHMITE DISSOLUTION IN CAUSTIC SOLUTIONS APPLIED TO OPTIMIZE HANFORD WASTE PROCESSING

    International Nuclear Information System (INIS)

    Boehmite (e.g., aluminum oxyhydroxide) is a major non-radioactive component in Hanford and Savannah River nuclear tank waste sludge. Boehmite dissolution from sludge using caustic at elevated temperatures is being planned at Hanford to minimize the mass of material disposed of as high-level waste (HLW) during operation of the Waste Treatment Plant (WTP). To more thoroughly understand the chemistry of this dissolution process, we have developed an empirical kinetic model for aluminate production due to boehmite dissolution. Application of this model to Hanford tank wastes would allow predictability and optimization of the caustic leaching of aluminum solids, potentially yielding significant improvements to overall processing time, disposal cost, and schedule. This report presents an empirical kinetic model that can be used to estimate the aluminate production from the leaching of boehmite in Hanford waste as a function of the following parameters: (1) hydroxide concentration; (2) temperature; (3) specific surface area of boehmite; (4) initial soluble aluminate plus gibbsite present in waste; (5) concentration of boehmite in the waste; and (6) (pre-fit) Arrhenius kinetic parameters. The model was fit to laboratory, non-radioactive (e.g. 'simulant boehmite') leaching results, providing best-fit values of the Arrhenius A-factor, A, and apparent activation energy, EA, of A = 5.0 x 1012 hour-1 and EA = 90 kJ/mole. These parameters were then used to predict boehmite leaching behavior observed in previously reported actual waste leaching studies. Acceptable aluminate versus leaching time profiles were predicted for waste leaching data from both Hanford and Savannah River site studies.

  11. DEVELOPMENT OF A KINETIC MODEL OF BOEHMITE DISSOLUTION IN CAUSTIC SOLUTIONS APPLIED TO OPTIMIZE HANFORD WASTE PROCESSING

    Energy Technology Data Exchange (ETDEWEB)

    DISSELKAMP RS

    2011-01-06

    Boehmite (e.g., aluminum oxyhydroxide) is a major non-radioactive component in Hanford and Savannah River nuclear tank waste sludge. Boehmite dissolution from sludge using caustic at elevated temperatures is being planned at Hanford to minimize the mass of material disposed of as high-level waste (HLW) during operation of the Waste Treatment Plant (WTP). To more thoroughly understand the chemistry of this dissolution process, we have developed an empirical kinetic model for aluminate production due to boehmite dissolution. Application of this model to Hanford tank wastes would allow predictability and optimization of the caustic leaching of aluminum solids, potentially yielding significant improvements to overall processing time, disposal cost, and schedule. This report presents an empirical kinetic model that can be used to estimate the aluminate production from the leaching of boehmite in Hanford waste as a function of the following parameters: (1) hydroxide concentration; (2) temperature; (3) specific surface area of boehmite; (4) initial soluble aluminate plus gibbsite present in waste; (5) concentration of boehmite in the waste; and (6) (pre-fit) Arrhenius kinetic parameters. The model was fit to laboratory, non-radioactive (e.g. 'simulant boehmite') leaching results, providing best-fit values of the Arrhenius A-factor, A, and apparent activation energy, E{sub A}, of A = 5.0 x 10{sup 12} hour{sup -1} and E{sub A} = 90 kJ/mole. These parameters were then used to predict boehmite leaching behavior observed in previously reported actual waste leaching studies. Acceptable aluminate versus leaching time profiles were predicted for waste leaching data from both Hanford and Savannah River site studies.

  12. Nuclear waste

    International Nuclear Information System (INIS)

    This extract from the House of Commons Hansard publication for Wednesday 12th July 1995 considers the current debate on the desirability or otherwise of disposing of low level radioactive waste in landfill sites. It covers wastes generated both by the nuclear industry and by medical processes in local hospitals, and the transport of such waste from source to disposal site. The questions raised lead to a debate about plans to sell off commercially desirable aspects of the nuclear electric generation industry while leaving the costs associated with decommissioning of Magnox reactors as a liability on the public purse. (UK)

  13. Nuclear waste

    International Nuclear Information System (INIS)

    Radioactive waste is mounting at U.S. nuclear power plants at a rate of more than 2,000 metric tons a year. Pursuant to statute and anticipating that a geologic repository would be available in 1998, the Department of Energy (DOE) entered into disposal contracts with nuclear utilities. Now, however, DOE does not expect the repository to be ready before 2010. For this reason, DOE does not want to develop a facility for monitored retrievable storage (MRS) by 1998. This book is concerned about how best to store the waste until a repository is available, congressional requesters asked GAO to review the alternatives of continued storage at utilities' reactor sites or transferring waste to an MRS facility, GAO assessed the likelihood of an MRSA facility operating by 1998, legal implications if DOE is not able to take delivery of wastes in 1998, propriety of using the Nuclear Waste Fund-from which DOE's waste program costs are paid-to pay utilities for on-site storage capacity added after 1998, ability of utilities to store their waste on-site until a repository is operating, and relative costs and safety of the two storage alternatives

  14. Nuclear waste

    International Nuclear Information System (INIS)

    This book discusses the GAO's work on the Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). As is known, DOE is seeking legislation permanently withdrawing the WIPP site, located on federal land near Carlsbad, New Mexico, from public use. Because DOE wants to begin storing a limited amount of nuclear waste in WIPP for tests, action on land withdrawal, either through legislation or administrative action by the Secretary of the Interior, is necessary to authorize such storage

  15. Nuclear waste

    International Nuclear Information System (INIS)

    DOE estimates that disposing of radioactive waste from civilian nuclear power plants and its defense-related nuclear facilities could eventually end up costing $32 billion. To pay for this, DOE collects fees from utilities on electricity generated by nuclear power plants and makes payments from its defense appropriation. This report states that unless careful attention is given to its financial condition, the nuclear waste program is susceptible to future shortfalls. Without a fee increase, the civilian-waste part of the program may already be underfunded by at least $2.4 billion (in discounted 1988 dollars). Also, DOE has not paid its share of cost-about $480 million-nor has it disclosed this liability in its financial records. Indexing the civilian fee to the inflation rate would address one major cost uncertainty. However, while DOE intends to do this at an appropriate time, it does not use a realistic rate of inflation as its most probable scenario in assessing whether that time has arrived

  16. Nuclear waste

    International Nuclear Information System (INIS)

    The Department of Energy plans to award a contract to Bechtel Systems Management, Inc. to manage and operate the federal government's nuclear waste repository. The proposed management and operating contract is likely to substantially affect program operations and costs. This paper reports on a GAO report. A major concern is the degree to which the selected contractor might replace, or possibly duplicate, the efforts now being carried out by DOE's current contractors. It is questionable whether the contract will result in a more efficient and effective program. DOE officials have had to divert their attention from program operations to develop the contract proposal and participate in legal proceedings related to a bid protest. GAO and the DOE inspector general have reported on problems and issues involving DOE's administration of management and operating contracts, including some companies which participate in the nuclear waste program. Many of the resulting recommendations have yet to be implemented. Implementation of these recommendations could help ensure that the nuclear waste program is operated in a more cost-effective manner

  17. Effect of solvent addition sequence on lycopene extraction efficiency from membrane neutralized caustic peeled tomato waste.

    Science.gov (United States)

    Phinney, David M; Frelka, John C; Cooperstone, Jessica L; Schwartz, Steven J; Heldman, Dennis R

    2017-01-15

    Lycopene is a high value nutraceutical and its isolation from waste streams is often desirable to maximize profits. This research investigated solvent addition order and composition on lycopene extraction efficiency from a commercial tomato waste stream (pH 12.5, solids ∼5%) that was neutralized using membrane filtration. Constant volume dilution (CVD) was used to desalinate the caustic salt to neutralize the waste. Acetone, ethanol and hexane were used as direct or blended additions. Extraction efficiency was defined as the amount of lycopene extracted divided by the total lycopene in the sample. The CVD operation reduced the active alkali of the waste from 0.66 to Extraction efficiency varied from 32.5% to 94.5%. This study demonstrates a lab scale feasibility to extract lycopene efficiently from tomato processing byproducts. PMID:27542486

  18. Nuclear waste

    International Nuclear Information System (INIS)

    The Department of Energy is awarding grants to the state of Nevada for the state's participation in DOE's program to investigate Yucca Mountain as a possible site for the disposal of civilian nuclear waste. This report has found that DOE's financial assistance budget request of $15 million for Nevada's fiscal year 1990 was not based on the amount the state requested but rather was derived by increasing Nevada's grant funds from the previous year in proportion to the increase that DOE requested for its own activities at the Nevada site. DOE's evaluations of Nevada's requests are performed too late to be used in DOE's budget formulation process because Nevada has been applying for financial assistance at about the same time that DOE submits its budget request to Congress

  19. Nuclear waste

    International Nuclear Information System (INIS)

    The state of Nevada opposed DOE's development of a nuclear waste repository at Yucca Mountain. As a result, disputes have arisen over how Nevada has spent financial assistance provided by DOE to pay the state's repository program costs. This report reviews Nevada's use of about $32 million in grant funds provided by DOE through June 1989 and found that Nevada improperly spent about $1 million. Nevada used as much as $683,000 for lobbying and litigation expenses that were unauthorized or were expressly prohibited by law, court decision, or grant terms; exceeded a legislative spending limit on socioeconomic studies by about $96,000; and used, contrary to grant terms, about $275,000 from one grant period to pay expenses incurred in the prior year. Also, Nevada did not always exercise adequate internal controls over grant funds, such as timely liquidation of funds advanced to contractors. A permissive approach to grant administration by DOE contributed to Nevada's inappropriate use of grant funds

  20. Nuclear wastes

    International Nuclear Information System (INIS)

    Here is made a general survey of the situation relative to radioactive wastes. The different kinds of radioactive wastes and the different way to store them are detailed. A comparative evaluation of the situation in France and in the world is made. The case of transport of radioactive wastes is tackled. (N.C.)

  1. Laboratory Demonstration of the Pretreatment Process with Caustic and Oxidative Leaching Using Actual Hanford Tank Waste

    Energy Technology Data Exchange (ETDEWEB)

    Fiskum, Sandra K.; Billing, Justin M.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Snow, Lanee A.

    2009-01-01

    This report describes the bench-scale pretreatment processing of actual tank waste materials through the entire baseline WTP pretreatment flowsheet in an effort to demonstrate the efficacy of the defined leaching processes on actual Hanford tank waste sludge and the potential impacts on downstream pretreatment processing. The test material was a combination of reduction oxidation (REDOX) tank waste composited materials containing aluminum primarily in the form of boehmite and dissolved S saltcake containing Cr(III)-rich entrained solids. The pretreatment processing steps tested included • caustic leaching for Al removal • solids crossflow filtration through the cell unit filter (CUF) • stepwise solids washing using decreasing concentrations of sodium hydroxide with filtration through the CUF • oxidative leaching using sodium permanganate for removing Cr • solids filtration with the CUF • follow-on solids washing and filtration through the CUF • ion exchange processing for Cs removal • evaporation processing of waste stream recycle for volume reduction • combination of the evaporated product with dissolved saltcake. The effectiveness of each process step was evaluated by following the mass balance of key components (such as Al, B, Cd, Cr, Pu, Ni, Mn, and Fe), demonstrating component (Al, Cr, Cs) removal, demonstrating filterability by evaluating filter flux rates under various processing conditions (transmembrane pressure, crossflow velocities, wt% undissolved solids, and PSD) and filter fouling, and identifying potential issues for WTP. The filterability was reported separately (Shimskey et al. 2008) and is not repeated herein.

  2. Laboratory Demonstration of the Pretreatment Process with Caustic and Oxidative Leaching Using Actual Hanford Tank Waste

    International Nuclear Information System (INIS)

    This report describes the bench-scale pretreatment processing of actual tank waste materials through the entire baseline WTP pretreatment flowsheet in an effort to demonstrate the efficacy of the defined leaching processes on actual Hanford tank waste sludge and the potential impacts on downstream pretreatment processing. The test material was a combination of reduction oxidation (REDOX) tank waste composited materials containing aluminum primarily in the form of boehmite and dissolved S saltcake containing Cr(III)-rich entrained solids. The pretreatment processing steps tested included: caustic leaching for Al removal; solids crossflow filtration through the cell unit filter (CUF); stepwise solids washing using decreasing concentrations of sodium hydroxide with filtration through the CUF; oxidative leaching using sodium permanganate for removing Cr; solids filtration with the CUF; follow-on solids washing and filtration through the CUF; ion exchange processing for Cs removal; evaporation processing of waste stream recycle for volume reduction; and combination of the evaporated product with dissolved saltcake. The effectiveness of each process step was evaluated by following the mass balance of key components (such as Al, B, Cd, Cr, Pu, Ni, Mn, and Fe), demonstrating component (Al, Cr, Cs) removal, demonstrating filterability by evaluating filter flux rates under various processing conditions (transmembrane pressure, crossflow velocities, wt% undissolved solids, and PSD) and filter fouling, and identifying potential issues for WTP. The filterability was reported separately (Shimskey et al. 2008) and is not repeated herein

  3. Sub-grain scale mineralogy of Hanford sand after reaction with caustic tank wastes

    Science.gov (United States)

    Crandell, L. E.; Peters, C. A.; Um, W.; Lindquist, W.

    2010-12-01

    Reactions of caustic tank waste with vadose-zone sediments at the DOE Hanford, WA site cause dissolution of quartz and aluminosilicate minerals and precipitation of secondary minerals, sodalite and cancrinite. In this study, Hanford sediments from reactive column experiments were examined using 2-D imaging technologies. Mineralogy was examined at the sub-grain scale through image analysis of SEM backscattered electron (BSE) images supplemented with elemental mapping from energy-dispersive X-ray spectroscopy (EDS). The thin sections were made from cross-sections of epoxied sediments in the experimental columns, before and after reaction with simulated tank waste leachate. The image analysis method developed for this work identifies the important minerals and quantifies their accessibility to pore fluids, information that may be used to improve reactive transport modeling of water-rock reactions. Current reactive transport models use mineralogical information obtained through X-ray diffraction (XRD) analysis of crushed samples. Such analysis provides reliable information on the relative quantities of minerals present in macroscopic samples. However, the absence of information on sub-grain scale mineralogy may lead to erroneous interpretation in the context of reactive transport. Preliminary findings indicate the presence of grain inclusions and secondary mineral coatings which may significantly impact the accessibility of minerals to pore waters and thus alter the predicted water -rock reactions.

  4. Nuclear wastes

    International Nuclear Information System (INIS)

    While evoking the effects of radioactivity, this publication issued by religious authorities first presents the different radioactive wastes (low level, low or medium level and short life, medium level and long life, high level and long life) and indicates their respective origins. It proposes a brief overview of solutions adopted for the storage of high level-long life radioactive wastes in different countries. It presents the French political and regulatory framework for such storage, indicates the envisaged solutions (deep geological storage, separation and transmutation, packaging and long duration surface or underground warehousing), discusses the content of the debate which took place before the adoption of the law of June 2006, and evokes the notion of reversibility. The next part addresses issues related to public information, and evokes public opinion regarding this storage issue. Some other issues are then discussed within the Church's perspective: the responsibility towards future generations, the transmission of a secured heritage to future generations, the research effort, dialog and transparency

  5. Characterization of nuclear waste

    International Nuclear Information System (INIS)

    Nuclear wastes which are logical candidates for deep geologic disposal include commercial (spent fuel, reprocessing) and defense wastes. It is expected that the 5250 metric tons of spent fuel discharged through the end of 1978 would increase to about 100,000 tons by the end of 2000. The individual characteristics of each waste type (spent fuel, solidified waste, defense wastes) are described in turn

  6. The chemistry of sludge washing and caustic leaching processes for selected Hanford tank wastes

    International Nuclear Information System (INIS)

    A broad-based study on washing and caustic leaching of Hanford tank sludges was performed in FY 1995 to gain a better understanding of the basic chemical processes that underlie this process. This approach involved testing of the baseline sludge washing and caustic leaching method on several Hanford tank sludges, and characterization of the solids both before and after testing by electron microscopy, X-ray diffraction, and X-ray absorption spectroscopy. A thermodynamically based model was employed to help understand the factors involved in individual specie distribution in the various stages of the sludge washing and caustic leaching treatment. The behavior of the important chemical and radiochemical components throughout the testing is summarized and reviewed in this report

  7. Electrochemical treatment of alkaline nuclear wastes

    International Nuclear Information System (INIS)

    Large quantities of highly radioactive waste have been generated throughout the Department of Energy complex over the past 50 years as a result of the production of special nuclear materials for defense and space programs. These wastes have been stored in underground tanks. Some of the tanks have developed cracks that have allowed waste to leak out of the primary tank. Many of the tanks are operating beyond their design life. Processes are being developed to remove the waste from the storage tanks and permanently dispose of it in engineered wasteforms. The bulk of the radioactivity will be concentrated into approximately 1% of the total waste volume and vitrified. The highly radioactive borosilicate glass wasteform will be placed in the federal repository. The remaining waste, which still contains low concentrations of radioactivity, will be incorporated into a low-level wasteform (e.g., cement, glass, ceramic, polymer, etc.) and placed in a near surface facility at the DOE site. Electrochemical-based processes are being evaluated to destroy organic compounds that impact radionuclide separations processes, to destroy or to remove hazardous species in the waste such as nitrates, nitrites, hazardous metals, and radionuclides that can impact wasteform production and characteristics, recovery chemicals of value such as sodium hydroxide (caustic) that can be recycled. Major benefits of such processes include the destruction or removal of hazardous species, waste volume reduction and the recovery of valuable chemicals contained in the waste

  8. Nuclear waste management

    International Nuclear Information System (INIS)

    The Canadian Nuclear Association has specific views on the following aspects of waste management: a) public information and public participation programs should be encouraged; b) positive political leadership is essential; c) a national plan and policy are necessary; d) all hazardous materials should receive the same care as radioactive wastes; e) power plant construction need not be restricted as long as there is a commitment to nuclear waste management; f) R and D should be funded consistently for nuclear waste management and ancillary topics like alternative fuel cycles and reprocessing. (E.C.B.)

  9. Nuclear waste packaging facility

    International Nuclear Information System (INIS)

    A nuclear waste packaging facility comprising: (a) a first section substantially surrounded by radiation shielding, including means for remotely handling waste delivered to the first section and for placing the waste into a disposal module; (b) a second section substantially surrounded by radiation shielding, including means for handling a deformable container bearing waste delivered to the second section, the handling means including a compactor and means for placing the waste bearing deformable container into the compactor, the compactor capable of applying a compacting force to the waste bearing containers sufficient to inelastically deform the waste and container, and means for delivering the deformed waste bearing containers to a disposal module; (c) a module transportation and loading section disposed between the first and second sections including a means for handling empty modules delivered to the facility and for loading the empty modules on the transport means; the transport means moving empty disposal modules to the first section and empty disposal modules to the second section for locating empty modules in a position for loading with nuclear waste, and (d) a grouting station comprising means for pouring grout into the waste bearing disposal module, and a capping station comprising means for placing a lid onto the waste bearing grout-filled disposal module to completely encapsulate the waste

  10. Politics of nuclear waste

    International Nuclear Information System (INIS)

    In November of 1979, the Program in Science, Technology and Humanism and the Energy Committee of the Aspen Institute organized a conference on resolving the social, political, and institutional conflicts over the permanent siting of radioactive wastes. This book was written as a result of this conference. The chapters provide a comprehensive and up-to-date overview of the governance issues connected with radioactive waste management as well as a sampling of the diverse views of the interested parties. Chapter 1 looks in depth of radioactive waste management in the United States, with special emphasis on the events of the Carter Administration as well as on the issues with which the Reagen administration must deal. Chapter 2 compares waste management policies and programs among the industralized countries. Chapter 3 examines the factional controversies in the last administration and Congress over nuclear waste issues. Chapter 4 examines the complex legal questions involved in the federal-state conflicts over nuclear waste management. Chapter 5 examines the concept of consultation and concurrence from the perspectives of a host state that is a candidate for a repository and an interested state that has special concerns regarding the demonstration of nuclear waste disposal technology. Chapter 6 examines US and European perspectives concerning public participation in nuclear waste management. Chapter 7 discusses propaganda in the issues. The epilogue attempts to assess the prospects for consensus in the United States on national policies for radioactive waste management. All of the chapter in this book should be interpreted as personal assessments

  11. Nuclear Waste and Ethics

    Energy Technology Data Exchange (ETDEWEB)

    Damveld, Herman [Groningen (Netherlands)

    2003-10-01

    In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible.

  12. Nuclear Waste and Ethics

    International Nuclear Information System (INIS)

    In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible

  13. Cleaning up nuclear waste

    International Nuclear Information System (INIS)

    Willem Verboom, associate professor of organic chemistry at the University of Twente, The Netherlands, considers some of the latest advances in separating highly radioactive components of nuclear waste. (author)

  14. High level nuclear wastes

    International Nuclear Information System (INIS)

    The transformations involved in the nuclear fuels during the burn-up at the power nuclear reactors for burn-up levels of 33.000 MWd/th are considered. Graphs and data on the radioactivity variation with the cooling time and heat power of the irradiated fuel are presented. Likewise, the cycle of the fuel in light water reactors is presented and the alternatives for the nuclear waste management are discussed. A brief description of the management of the spent fuel as a high level nuclear waste is shown, explaining the reprocessing and giving data about the fission products and their radioactivities, which must be considered on the vitrification processes. On the final storage of the nuclear waste into depth geological burials, both alternatives are coincident. The countries supporting the reprocessing are indicated and the Spanish programm defined in the Plan Energetico Nacional (PEN) is shortly reviewed. (author) 8 figs., 4 tabs

  15. Nuclear waste management programme 1996

    International Nuclear Information System (INIS)

    Nuclear Waste Commission of Finnish Power Companies (YJT) founded by nuclear energy producing Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (TVO), coordinates the research work of the companies on nuclear waste management. In YJT's Nuclear Waste Management Programme 1995, an account of the nuclear waste management measures of IVO and TVO is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, the nuclear waste management situation and the programme of activities are reported. The nuclear waste management research programme for the year 1996 and more generally for the years 1997-2000 is presented. (1 fig., 1 tab.)

  16. Nuclear Waste Management Programme 1993

    International Nuclear Information System (INIS)

    Nuclear Waste Commission of Finnish Power Companies (YJT), founded by nuclear energy producing Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), coordinates the research work of the companies on nuclear waste management. In YJT's Nuclear Waste Management Programme 1993, an account of the nuclear waste management measures of IVO and TVO is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, the nuclear waste management situation and the programme of activities are reported. Then the nuclear waste management research programme for the year 1993 and more generally for the years 1994-1997 is presented

  17. Nuclear waste management programme 1994

    International Nuclear Information System (INIS)

    Nuclear Waste Commission of Finnish Power Companies (YJT), founded by nuclear energy producing Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (TVO), coordinates the research work of the companies on nuclear waste management. In YJT's Nuclear Waste Management Programme 1994, an account of the nuclear waste management measures of IVO and TVO is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, the nuclear waste management situation and the programme of activities are reported. The the nuclear waste management research programme for the year 1994 and more generally for the years 1995-1997 is presented. (2 figs., 1 tab.)

  18. Nuclear Waste Management Programme 1992

    International Nuclear Information System (INIS)

    Nuclear Waste Commission of Finnish Power Companies (YJT), founded by nuclear energy producing Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (TVO), coordinates the research work of the companies on nuclear waste management. In YJT's Nuclear Waste Management Programme 1992, an account of the nuclear waste management measures of IVO and TVO is given as required by the Sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, the nuclear waste management situation and the programme of activities are reported. Then the nuclear waste management research programme for the year 1992 and more generally for the years 1993 - 1996 is presented. (author)

  19. Managing nuclear waste

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Acts (NWPA) of 1982 provide a plan for the nation's first permanent repository for spent reactor fuel. The legislation authorizes DOE to plan and build the first permanent geologic repository for commercial nuclear waste in the US by 1998. The entire $20 billion-plus cost will fall to the ratepayers of those electric utilities that own and operate nuclear power plants. An interview with James B. Hall, Program Manager of the Utility Nuclear Waste Management Group (UNWMG) explores problems with having the law codify geologic disposal technology and with DOE mission plans. Hall describes the site selection process, the likely public protest over safety and financing, UNWMG cooperation and interaction with DOE on the project, and technological needs. 2 figures

  20. Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center FY-2001 Status Report

    International Nuclear Information System (INIS)

    The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates

  1. Environmental Hazards of Nuclear Wastes

    Science.gov (United States)

    Micklin, Philip P.

    1974-01-01

    Present methods for storage of radioactive wastes produced at nuclear power facilities are described. Problems arising from present waste management are discussed and potential solutions explored. (JP)

  2. Swedish nuclear waste efforts

    International Nuclear Information System (INIS)

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981

  3. Encapsulation of nuclear wastes

    International Nuclear Information System (INIS)

    Intermediate-level radioactive wastes produced in the day-to-day operation of a nuclear power plant may be incorporated into a thermosettable resin by mixing aqueous wastes with a vinyl ester resin, an unsaturated polyester resin, or a mixture of the two, and curing the resulting water-in-oil emulsion at temperatures below 1000C. The wastes may be either solutions or suspensions of inorganic or organic compounds derived from evaporation, flocculation, coagulation, filtration, ion exchange, or other treatment processes. (LL)

  4. Ten questions on nuclear wastes

    International Nuclear Information System (INIS)

    The authors give explanations and answers to ten issues related to nuclear wastes: when a radioactive material becomes a waste, how radioactive wastes are classified and particularly nuclear wastes in France, what are the risks associated with radioactive wastes, whether the present management of radioactive wastes is well controlled in France, which wastes are raising actual problems and what are the solutions, whether amounts and radio-toxicity of wastes can be reduced, whether all long life radionuclides or part of them can be transmuted, whether geologic storage of final wastes is inescapable, whether radioactive material can be warehoused over long durations, and how the information on radioactive waste management is organised

  5. Attitudes to nuclear waste

    International Nuclear Information System (INIS)

    This is a study of risk perception and attitudes with regard to nuclear waste. Two data sets are reported. In the first set, data were obtained from a survey of the general population, using an extensive questionnaire. The second set constituted a follow-up 7 years later, with a limited number of questions. The data showed that people considered the topic of nuclear waste risks to be very important and that they were not convinced that the technological problems had been solved. Experts associated with government agencies were moderately trusted, while those employed by the nuclear industry were much distrusted by some respondents, and very much trusted by others. Moral obligations to future generations were stressed. A large portion (more than 50 per cent) of the variances in risk perception could be explained by attitude to nuclear power, general risk sensitivity and trust in expertise. Most background variables, except gender, had little influence on risk perception and attitudes. The follow-up study showed that the attitude to nuclear power had become more positive over time, but that people still doubted that the problems of nuclear waste disposal had been solved. 49 refs

  6. Nuclear Waste Fund management

    International Nuclear Information System (INIS)

    The need for the incorporation of cost controls into the DOE nuclear waste management program is discussed. It is suggested that the mission plan include the kind of cost data DOE plans to use in preparing the annual cost estimates required by the Act, and that specific budget limits and specific task schedules be included so that any corrective action warranted can be taken

  7. Nuclear waste management

    International Nuclear Information System (INIS)

    Passage of the Nuclear Waste Policy Act by the Congress, December 20, 1982, in the waning hours of the 97th Congress, was a major milestone in the management of the Nation's spent fuel and high-level radioactive waste. The Congress -- and, subsequently, the President -- made a tough decision that this generation must bite the bullet and proceed with the development of a permanent waste disposal system for the protection of future generations. The Act was a result of several attempts by the Congress over a number of years to move to action on this important subject. President Reagan added his leadership to the task through his 1981 Nuclear Policy Statement. Today, the author proposes to briefly summarize some of the significant achievements concerning implementation of the NWPA, and to direct your attention to courses of action they have placed before the States and Indian Tribes for comment and about which they will formally seek Congressional direction

  8. Who wants nuclear waste

    International Nuclear Information System (INIS)

    The criteria involved in selecting sites for disposal of low and short-lived intermediate-level radioactive wastes are explained. The wastes and the sources are identified and the current procedure for their disposal, at Drigg, next to the Sellafield reprocessing plant, is given. If alternative sites could be found for non-Sellafield-produced wastes the lifetime of the Drigg site could be extended. The sites chosen by NIREX (Nuclear Industry Radioactive Waste Executive) have to be cost effective. Indeed, those identified are conveniently situated and would not incur excessive transport costs. However, more remote sites may have to be chosen, even at greater transport cost, because of public protests. Even this may not be satisfactory because the transportation itself incurs risks. (UK)

  9. Commercial nuclear-waste management

    International Nuclear Information System (INIS)

    This report is primarily concerned with nuclear waste generated by commercial power operations. It is clear, however, that the total generation of commercial nuclear waste does not tell the whole story, there are sizeable stockpiles of defense nuclear wastes which will impact areas such as total nuclide exposure to the biosphere and the overall economics of waste disposal. The effects of these other nuclear waste streams can be factored in as exogenous inputs. Their generation is essentially independent of nuclear power operations. The objective of this report is to assess the real-world problems associated with nuclear waste management and to design the analytical framework, as appropriate, for handling nuclear waste management issues in the International Nuclear Model. As such, some issues that are not inherently quantifiable, such as the development of environmental Impact Statements to satisfy the National Environmental Protection Act requirements, are only briefly mentioned, if at all

  10. Ceramics in nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T D; Mendel, J E [eds.

    1979-05-01

    Seventy-three papers are included, arranged under the following section headings: national programs for the disposal of radioactive wastes, waste from stability and characterization, glass processing, ceramic processing, ceramic and glass processing, leaching of waste materials, properties of nuclear waste forms, and immobilization of special radioactive wastes. Separate abstracts were prepared for all the papers. (DLC)

  11. Nuclear waste vs. democracy

    International Nuclear Information System (INIS)

    In the United States the storage and disposal of high-level nuclear waste is a highly contentious issue because under current plans the public is subjected to unaccepted, involuntary risks. The proposed federal policy includes the forced siting of a repository and interim storage facilities in Nevada, and the transport of waste across the entire nation through large cities and within 2 mile of over 50 million people. At its destination in Nevada, the residents would face coexistence with a facility housing highly radioactive wastes that remain dangerous for many thousands of years. Scientific predictions about the performance and safety of these facilities is highly uncertain and the people foresee possibly catastrophic threats to their health, safety and economic well-being for generations to come. The public sees this currently proposed plan as one that seeks to maximise the profits of the commercial nuclear industry through imposing risk and sacrifice to communities who reap no benefit. And there is no evidence that this plan is actually a solution to the problem. The American public has never had the opportunity to participate in the nuclear waste debate and government plans are presented to people as being necessary and inevitable. To allow democracy into the decisions could be costly to the nuclear industry and it might thwart the government program, but that is the nature of democracy. If the utilities are established to provide a public service, and the government is founded on the principle of public representation, then the nuclear waste debate must conform to those requirements. What we see in this case is a continuing change of rule and law to accommodate a corporate power and the subrogation of national principle. The result of this situation has been that the public exercises its only option - which is obstructing the federal plan. Because the odds are so heavily stacked in favour of government and industry and average citizens have so little access

  12. Problems of nuclear waste

    International Nuclear Information System (INIS)

    An enormous stockpile of nuclear weapons was reduced during the Cold War as a result of frantic Soviet-US competition, accompanied by considerable radioactive pollution of the environment. This pollution was inevitable. Former adversaries began to sober only recently. As a result, areas of weapons complexes both in the USA (Hanford, Savannah, Oak Ridge) and in Russia (Chelyabinsk-65, Tomsk-7, Krasnoyarsk-25) look like battlefields of the Cold War. A Nuclear weapon-free world will only be achieved (if at all) after reaching changes in the principles that guide state policies and actions. A nuclear-waste-free world implies that the environment's radioactive pollution of a military nature would be eliminated and all potential dangers from civil nuclear energy prevented. This can be attained after solution of some economic, political and social problems

  13. Caustic Recycle from Hanford Tank Waste Using NaSICON Ceramic Membrane Salt Splitting Process

    Energy Technology Data Exchange (ETDEWEB)

    Fountain, Matthew S.; Kurath, Dean E.; Sevigny, Gary J.; Poloski, Adam P.; Pendleton, J.; Balagopal, S.; Quist, M.; Clay, D.

    2009-02-20

    A family of inorganic ceramic materials, called sodium (Na) Super Ion Conductors (NaSICON), has been studied at Pacific Northwest National Laboratory (PNNL) to investigate their ability to separate sodium from radioactively contaminated sodium salt solutions for treating U.S. Department of Energy (DOE) tank wastes. Ceramatec Inc. developed and fabricated a membrane containing a proprietary NAS-GY material formulation that was electrochemically tested in a bench-scale apparatus with both a simulant and a radioactive tank-waste solution to determine the membrane performance when removing sodium from DOE tank wastes. Implementing this sodium separation process can result in significant cost savings by reducing the disposal volume of low-activity wastes and by producing a NaOH feedstock product for recycle into waste treatment processes such as sludge leaching, regenerating ion exchange resins, inhibiting corrosion in carbon-steel tanks, or retrieving tank wastes.

  14. Nuclear waste vault sealing

    International Nuclear Information System (INIS)

    A nuclear waste vault must be designed and built to ensure adequate isolation of the nuclear wastes from human contact. Consequently, after a vault has been fully loaded, it must be adequately sealed off to prevent radionuclide migration which may be provided by circulating groundwater. Vault sealing entails four major aspects, i.e.: (a) vault grouting; (b) borehole sealing; (c) buffer packing; and (d) backfilling. Of particular concern in vault sealing are the physical and chemical properties of the sealing material, its long-term durability and stability, and the techniques used for its emplacement. Present sealing technology and sealing materials are reviewed in terms of the particular needs of vault sealing. Areas requiring research and development are indicated

  15. Final Report: Caustic Waste-Soil Weathering Reactions and Their Impacts on Trace Contaminant Migration and Sequestration

    International Nuclear Information System (INIS)

    The principal goal of this project was to assess the molecular nature and stability of radionuclide (137-Cs, 90-Sr, and 129-I) immobilization during weathering reactions in bulk Hanford sediments and their high surface area clay mineral constituents. We focused on the unique aqueous geochemical conditions that are representative of waste-impacted locations in the Hanford site vadose zone: high ionic strength, high pH and high Al concentrations. The specific objectives of the work were to (i) measure the coupling of clay mineral weathering and contaminant uptake kinetics of Cs+, Sr2+ and I-; (ii) determine the molecular structure of contaminant binding sites and their change with weathering time during and after exposure to synthetic tank waste leachate (STWL); (iii) establish the stability of neoformed weathering products and their sequestered contaminants upon exposure of the solids to more ''natural'' soil solutions (i.e., after removal of the caustic waste source); and (iv) integrate macroscopic, microscopic and spectroscopic data to distinguish labile from non-labile contaminant binding environments, including their dependence on system composition and weathering time. During this funding period, we completed a large set of bench-scale collaborative experiments and product characterization aimed at elucidating the coupling between mineral transformation reactions and contaminant sequestration/stabilization. Our experiments included three representative Hanford sediments: course and fine sediments collected from the Hanford Formation and Ringold Silt, in addition to investigations with specimen clay minerals illite, vermiculite, smectite and kaolinite. These experiments combined macroscopic measurements of element release, contaminant uptake and subsequent neoformed mineral dissolution behavior, with detailed studies of solid phase products using SEM and TEM microscopy, NMR, XAS and FTIR spectroscopy. Our studies have shown direct coupling between mineral

  16. Risks from nuclear waste

    International Nuclear Information System (INIS)

    The first part of this review discusses the importance of risk. If there is any relation between the emotional and rational risk perceptions (for example, it is believed that increased knowledge will decrease emotions), it will be a desirable goal for society, and the nuclear industry in particular, to improve the understanding by the laymen of the rational risks from nuclear energy. This review surveys various paths to a more common comprehension - perhaps a consensus - of the nuclear waste risks. The second part discusses radioactivity as a risk factor and concludes that it has no relation in itself to risk, but must be connected to exposure leading to a dose risk, i.e. a health detriment, which is commonly expressed in terms of cancer induction rate. Dose-effect relations are discussed in light of recent scientific debate. The third part of the report describes a number of hazard indexes for nuclear waste found in the literature and distinguishes between absolute and relative risk scales. The absolute risks as well as the relative risks have changed over time due to changes in radiological and metabolic data and by changes in the mode of calculation. To judge from the literature, the risk discussion is huge, even when it is limited to nuclear waste. It would be very difficult to make a comprehensive review and extract the essentials from that. Therefore, we have chosen to select some publications, out of the over 100, which we summarize rather comprehensively; in some cases we also include our remarks. 110 refs, 22 figs

  17. Risks from nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Liljenzin, J.O.; Rydberg, J. [Radiochemistry Consultant Group, Vaestra Froelunda (Sweden)

    1996-11-01

    The first part of this review discusses the importance of risk. If there is any relation between the emotional and rational risk perceptions (for example, it is believed that increased knowledge will decrease emotions), it will be a desirable goal for society, and the nuclear industry in particular, to improve the understanding by the laymen of the rational risks from nuclear energy. This review surveys various paths to a more common comprehension - perhaps a consensus - of the nuclear waste risks. The second part discusses radioactivity as a risk factor and concludes that it has no relation in itself to risk, but must be connected to exposure leading to a dose risk, i.e. a health detriment, which is commonly expressed in terms of cancer induction rate. Dose-effect relations are discussed in light of recent scientific debate. The third part of the report describes a number of hazard indexes for nuclear waste found in the literature and distinguishes between absolute and relative risk scales. The absolute risks as well as the relative risks have changed over time due to changes in radiological and metabolic data and by changes in the mode of calculation. To judge from the literature, the risk discussion is huge, even when it is limited to nuclear waste. It would be very difficult to make a comprehensive review and extract the essentials from that. Therefore, we have chosen to select some publications, out of the over 100, which we summarize rather comprehensively; in some cases we also include our remarks. 110 refs, 22 figs.

  18. Causticizing process

    Energy Technology Data Exchange (ETDEWEB)

    Engdal, H.

    1987-03-10

    This invention seeks to provide a method in which the soda lye obtained as a result of cellulose cooking process and unslaked lime are used for producing white liquor which can be re-used in the cooking process. In this method, the heat released by the slaking of lime with soda lye is recovered by a high pressure slaking process wherein the heat is transferred, either to the steam separating from the lye, which steam is then led to the desired application, or to some other medium to be heated. The invention is characterized in that the soda lye to be causticized is divided into two parts, one of which is used for the slaking of lime by adding to it all the unslaked lime needed for the causticizing process, and that, following slaking, the two volumes are brought together for the actual causticizing reaction involving the total amount of lye needed. This invention provides the advantage that the amount of lye needed is smaller, and so the temperature can be increased.

  19. Nuclear waste: the political realities

    International Nuclear Information System (INIS)

    The land dumping of nuclear waste has again come to the attention of anti-nuclear groups, environmentalists and the media, following the announcement of the proposed sites for intermediate-level nuclear waste at Billingham and Bedford. Opposition has already surfaced on a large scale, with public meetings in both areas and a revitalisation of the waste dumping network. This article explains some of the political realities in the nuclear debate, and suggests how we can tackle the issue of waste dumping, remembering that, even if the industry closes tomorrow, there are vast quantities of waste which must be safely and democratically dealt with. (author)

  20. Nuclear waste management: a perspective

    International Nuclear Information System (INIS)

    The scope of our problems with nuclear waste management is outlined. Present and future inventories of nuclear wastes are assessed for risk. A discussion of what is presently being done to solve waste management problems and what might be done in the future are presented

  1. Extraction of long-lived radionuclides from caustic Hanford tank waste supernatants

    International Nuclear Information System (INIS)

    A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as 99Tc and 129I, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO4- and I- are selectively transferred to the less dense PEG-rich aqueous phase. The partition coefficients for a wide range of inorganic cations and anions, such as sodium, potassium, aluminum, nitrate, nitrite, and carbonate, are all less than one. The partition coefficients for pertechnetate ranged from 12 to 50, depending on the choice of waste simulant and temperature. The partition coefficient for iodide was about 5, while that of iodate was about 0.25. Irradiation of the PEG phase with gamma-ray doses up to 20 Mrad had no detectable effect on the partition coefficients. The most selective extraction systems examined were those based on PPGs, which exhibited separation factors in excess of 3000 between TcO4- and NO3-/NO2-. An advantage of the PPG-based system is minimization of secondary waste production. These studies also highlighted the need for exercising great care in extrapolating the partitioning behavior with tank waste simulants to actual tank waste

  2. Intragranular porosity in Hanford sand grains after reaction with caustic tank wastes: Quantification and implications for reactive transport

    Science.gov (United States)

    Crandell, L. E.; Peters, C. A.; Um, W.; Jones, K. W.; Lindquist, W. B.

    2011-12-01

    Reactions of caustic tank waste with sediments in the 200 East Area of the Hanford site cause quartz and primary aluminosilicate minerals to dissolve. Secondary minerals of sodalite and cancrinite have been shown to nucleate on, and cement together, quartz grains. These secondary precipitates have been found to uptake radionuclides in their network of channels and cages. In this work, thin sections from unreacted and reacted column experiments packed with Hanford sand grains were imaged using 2D Scanning Electron Microscopy (SEM). SEM image analysis reveals large amounts of intragranular pore space in both the reacted and unreacted sands. Grayscale Backscattered Electron (BSE) images were thresholded to separate grain and pore pixels. To quantify the amount of intragranular pore space, a set of images were manually created with the intragranular pore space removed, or the grains filled-in. Porosity, and intragranular porosity, was determined by counting and comparing the number of pore pixels in each pair of images. Intragranular pore space accounts for up to 14% of total porosity. Quartz dissolution in intragranular regions increases the proportion of intragranular pore space in reacted samples. Diffusion of tank waste into these free silica rich areas provides a favorable environment for cancrinite precipitates to form and a potential significant trapping mechanism for radionuclides. Part of this work was to quantify where, within a single pore and a network of pores, precipitation occurred. While the bulk amount of cancrinite precipitation occurred on grain surfaces, cancrinite precipitates were also found in intragranular pore spaces. Up to 10% of total precipitation occurred in intragranular pore space. However, as the system recovers and clean water flow returns, radionuclides incorporated into precipitates in intragranular regions may act as a secondary long term leaching source for contaminants. To determine the trapping or leaching potential from

  3. Partitioning of Tank Waste Sludge in a 5-cm Centrifugal Contactor Under Caustic-Side Solvent Extraction Conditions

    International Nuclear Information System (INIS)

    A test program has been performed to evaluate the effect of solids on the hydraulic performance of a 5-cm centrifugal contactor under conditions present in the extraction section of the Caustic-Side Solvent Extraction (CSSX) process. In addition to determining if the ability to separate the aqueous and organic phases is affected by the presence of solids in a feed solution, the extent to which solids are accumulated in the contactor was also assessed. The reported task was motivated by the need to determine if removal of cesium from Savannah River Site tank waste can be performed using a contactor-based CSSX process without first removing sludge that is suspended in the feed solution. The ability to pass solids through the CSSX process could facilitate placement of CSSX upstream of a process in which alpha-decaying actinides and strontium are removed from the waste stream by precipitation with monosodium titanate (MST). This relative placement of the CSSX and MST processes is desirable because removal of cesium would greatly reduce the activity level of the feed stream to the MST process, thereby reducing the level of shielding needed and mitigating remote maintenance design features of MST equipment. Both results would significantly reduce the cost of the Salt Processing Project. Test results indicate conclusively that a large fraction of suspended sludge that enters the centrifugal contactor remains inside. It is expected that extended operation would result in continued accumulation of solids and that hydraulic performance would be adversely affected. Results also indicate that a fraction of the solids partitions to the phase boundary and could affect phase separation as contactor operations progress

  4. Nuclear waste - perception and reality

    International Nuclear Information System (INIS)

    The author addresses the perceptual gap between the general public's attitude to nuclear waste disposal and British Nuclear Fuel Limited's (BNFL) effort to convey the measures actually being taken and the scale of the problem. It is a matter of real concern to BNFL that as much as 80% of the British population believe there is no safe way to dispose of nuclear waste. By comparing the volumes of low-intermediate -and high-level radioactive wastes produced annually to those for industrial waste in general, the nuclear waste issue is shown to represent only a very small fraction of the national toxic waste issue. The building of specific plants for high-and low-level waste disposal is described as is a public relations programme undertaken in 1990 to improve awareness and factual information available about BNFL's commitment to safe waste disposal. The campaign targeted the West Cumbrian region and BNFL employees and has proved successful. U.K

  5. Nuclear Waste Fund management

    International Nuclear Information System (INIS)

    The Nuclear Waste Fund involves a number of features which make it a unique federal program. Its primary purpose is to finance one of the largest and most controversial public works programs in the history of the United States. Despite the program's indicated size and advance publicity, no one knows exactly where the anticipated projects will be built, who will construct them, what they will look like when they are done or how they will be operated and by whom. Implimentation of this effort, if statutory targets are actually met, covers a 16-year period. To cover the costs of the program, the Federal Government will tax nuclear power at the rate of 1 mil per kilowatt hour generated. This makes it one of the biggest and longest-lived examples of advance collections for construction work in progress in the history of the United States. While the Department of Energy is authorized to collect funds for the program the Nuclear Regulatory Commission has the authority to cut off this revenue stream by the shutdown of particular reactors or particular reactor types. If all goes well, the Federal Government will begin receiving spent nuclear fuel by 1998, continuing to assess a fee which will cover operating and maintenance costs. If all does not go well, the Federal Government and/or utilities will have to take other steps to solve the problem of permanent disposal. Should the latter circumstance prevail, presumably not only used to date but the $7.5 billion would be spent. The Nuclear Waste Policy Act of 1982, contains no clear provision for utility refunds in that case

  6. Whither nuclear waste disposal?

    International Nuclear Information System (INIS)

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

  7. Underground nuclear waste containments

    International Nuclear Information System (INIS)

    In the United States, about a hundred million gallons of high-level nuclear waste are stored in underground containments. Basically, these containments are of two different designs: single-shell and double-shell structures. The single-shell structures consist of reinforced concrete cylindrical walls seated on circular mats and enclosed on top with torispherical domes or circular flat roofs. The walls and the basemats are lined with carbon steel. The double-shell structures provide another layer of protection and constitute a completely enclosed steel containment within the single-shell structure leaving an annular space between the two walls. Single-shell containments are of earlier vintage and were built in the period 1945-1965. Double-shell structures were built through the 1960s and 1970s. Experience gained in building and operating the single-shell containments was used in enhancing the design and construction of the double-shell structures. Currently, there are about 250 underground single-shell and double-shell structures containing the high-level waste with an inventory of about 800 million curies. During their service lives, especially in early stages, these structures were subjected to thermal excursions of varying extents; also, they have aged in the chemical environment. Furthermore, in their remaining service lives, the structures may be subjected to loads for which they were not designed, such as larger earthquakes or chemical explosions. As a result, the demonstration of safety of these underground nuclear containments poses a challenge to structural engineers, which increases with time. Regardless of current plans for gradual retrieval of the waste and subsequent solidification for disposal, many of these structures are expected to continue to contain the waste through the next 20-40 years. In order to verify their structural capabilities in fulfilling this mission, several studies were recently performed at Brookhaven National Laboratory

  8. Nuclear wastes management

    International Nuclear Information System (INIS)

    This document is the proceedings of the debate that took place at the French Senate on April 13, 2005 about the long-term French policy of radioactive wastes management. The different points tackled during the debate concern: the 3 axes of research of the 1991 law, the public acceptance about the implementation of repositories, the regional economic impact, the cost and financing, the lack of experience feedback, the reversibility or irreversibility of the storage, the share of nuclear energy in the sustainable development policy, the European Pressurized Reactor (EPR) project, the privatization of Electricite de France (EdF) etc. (J.S.)

  9. Caustic Precipitation of Plutonium Using Gadolinium as the Neutron Poison for Disposition to High Level Waste

    International Nuclear Information System (INIS)

    Nuclear Materials Management Division (NMMD) has proposed that up to 100 kg of the plutonium (Pu) solutions stored in H-Canyon be precipitated with a nuclear poison and dispositioned to H-Area Tank Farm. The use of gadolinium (Gd) as the poison would greatly reduce the number of additional glass logs resulting from this disposition. This report summarizes the characteristics of the precipitation process and addresses criticality concerns in the Nuclear Criticality Safety Evaluation. No problems were found with the nature of the precipitate or the neutralization process

  10. Nuclear waste processing

    International Nuclear Information System (INIS)

    This report is composed with a view to the discussions around the selection of a site in F.R.Germany near the Netherlands' border for a fuel reprocessing plant. Most of the scientific data available are placed side by side, especially those which are contradictory in order to promote better judgement of affairs before governmental decisions are made. The report comprises a brief introduction to nuclear power plants, fuel cycle, radioactive materials and their properties. Next the transportation of wastes from the nuclear power plants to the reprocessing plants is dealt with more extensively, including the processing and the effluents of as well as the experiences with operational reprocessing plants. The hazards from manipulation of radioactive materials accidents and theft are outlined in each case, followed by a problem discussion. The appendix illustrates the German concept of 'industrial park for after-treatment and disposal'

  11. Separation of technetium from nuclear waste stream simulants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strauss, S.H. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Chemistry

    1995-09-11

    The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering {sup 99}TcO{sub 4}{sup {minus}} from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO{sub 4}{sup {minus}}), a stable (non-radioactive) chemical surrogate for {sup 99}TcO{sub 4}{sup {minus}}. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO{sub 4}{sup {minus}} and TcO{sub 4}{sup {minus}}.

  12. Separation of technetium from nuclear waste stream simulants. Final report

    International Nuclear Information System (INIS)

    The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering 99TcO4- from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO4-), a stable (non-radioactive) chemical surrogate for 99TcO4-. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO4- and TcO4-

  13. Electrochemical generation of fentons reagent to treat spent caustic wastewater

    International Nuclear Information System (INIS)

    An important wastewater stream from oil refineries is the spent caustic. Caustic solutions are used as scrubbing agent during the desulphurization process to eliminate sulphur an mercaptans from oil and gasses. Spent caustic is classified as DOO3 (reactive sulphide) hazardous waste under the US Resource Conservation and Recovery Act (RCRA). (Author)

  14. Caustic Recycle from Hanford Tank Waste Using Large Area NaSICON Structures (LANS)

    Energy Technology Data Exchange (ETDEWEB)

    Fountain, Matthew S.; Sevigny, Gary J.; Balagopal, S.; Bhavaraju, S.

    2009-03-31

    This report presents the results of a 5-day test of an electrochemical bench-scale apparatus using a proprietary (NAS-GY) material formulation of a (Na) Super Ion Conductor (NaSICON) membrane in a Large Area NaSICON Structures (LANS) configuration. The primary objectives of this work were to assess system performance, membrane seal integrity, and material degradation while removing Na from Group 5 and 6 tank waste from the Hanford Site.

  15. Recycling of aluminum and caustic soda solution from waste effluents generated during the cleaning of the extruder matrixes of the aluminum industry

    International Nuclear Information System (INIS)

    Anodising industries use a concentrated caustic soda solution to remove aluminum from extruder matrixes. This procedure produces very alkaline effluents containing high amounts of aluminum. The work reported here was focussed on recycling aluminum, as aluminum hydroxide, from these effluents and regenerating an alkaline sodium hydroxide solution. Briefly, the method comprises a dilution step (necessary for reducing the viscosity of the effluent and allowing the subsequent filtration) followed by a filtration to eliminate a substantial amount of the insoluble iron. Then, sulphuric acid was added to neutralize the waste solution down to pH 12 and induce aluminum precipitation. The purity of the aluminum salt was improved after washing the precipitate with deionised water. The characterization of the solid recovered, performed by thermogravimetric analysis, Fourier transform infrared spectroscopy and X-ray diffraction, indicated characteristics typical of bayerite. The proposal method allowed recovering 82% of the aluminum present in the wastewater with high purity (99.5%). Additionally, a sufficiently concentrated caustic soda solution was also recovered, which can be reused in the anodising industries. This procedure can be easily implemented and ensures economy by recycling reagents (concentrated caustic soda solution) and by recovering commercial by-products (aluminum hydroxide), while avoiding environmental pollution.

  16. Science, society, and America's nuclear waste: Unit 1, Nuclear waste

    International Nuclear Information System (INIS)

    This is unit 1 in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  17. Public opinion and nuclear waste

    International Nuclear Information System (INIS)

    Surveys and opinion polls regularly reinforce the belief that nuclear waste is one of the general public greatest fears. Their results reflect the way this theme is handled by the media, often in a negative or controversial light. Closer examination of these surveys, however, reveals that the apparently delicate situation of nuclear waste in public opinion deserves a more subtle, qualified approach. (author)

  18. Concepts for nuclear waste disposal

    International Nuclear Information System (INIS)

    Continuing an article from the May issue, this article deals with the waste management concepts in the rest of the countries utilizing nuclear power (Latin America, Eastern European countries, Asia, South Africa). This completes the documentation of the waste management side of the nuclear fuel cycle within the framework of an international survey. (orig./HP)

  19. Geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    Fourteen papers dealing with disposal of high-level radioactive wastes are presented. These cover disposal in salt deposits, geologic deposits and marine disposal. Also included are papers on nuclear waste characterization, transport, waste processing technology, and safety analysis. All of these papers have been abstracted and indexed

  20. Glasses for nuclear waste immobilization

    International Nuclear Information System (INIS)

    Vitrification of nuclear wastes is attractive because of its flexibility, the large number of elements which can be incorporated in the glass, its high corrosion durability and the reduced volume of the resulting waste form. Vitrification is a mature technology and has been used for high level nuclear waste (HLW) immobilisation for more than 40 years in France, Germany and Belgium, Russia, UK, Japan and the USA. Vitrification involves melting of waste materials with glass-forming additives so that the final vitreous product incorporates the waste contaminants in its macro- and micro-structure. Hazardous waste constituents are immobilised either by direct incorporation into the glass structure or by encapsulation when the final glassy material can be in form of a glass composite material (GCM). Both borosilicate and phosphate glasses are currently used to immobilise nuclear wastes, moreover in addition to relatively homogeneous glasses novel GCM are used to immobilise problematic waste streams. The spectrum of wastes which are currently vitrified increases from HLW to low and intermediate wastes (LILW) such as legacy wastes in Hanford, USA and nuclear power plant operational wastes in Russia and Korea. (authors)

  1. The wastes of nuclear fission

    International Nuclear Information System (INIS)

    In this paper the author presents the problems of the radioactive wastes generated by the nuclear fission. The first part devoted to the fission phenomenon explains the incident neutron energy and the target nuclei role. The second part devoted to the nuclear wastes sources presents the production of wastes upstream of the reactors, in the reactors and why these wastes are dangerous. The third part discusses the radioactive wastes management in France (classification, laws). The last part details the associated research programs: the radionuclides separation, the disposal, the underground storage, the transmutation and the thorium cycle. (A.L.B.)

  2. Environmental geotechnics and nuclear waste

    OpenAIRE

    Gens Solé, Antonio

    2011-01-01

    The paper presents an overview of nuclear waste management and disposal relevant to the field of Envrronmental Geotechnics. Issues associated with storage and disposal of low-level and medium-level waste are discussed first. Subsequently, the paper focuses on the deep geological disposal of high-level nuclear waste. General strategies and features are presented as well as some considerations concerning suitable geological host media. The topics associated with the design and construction o...

  3. The problematic of nuclear wastes

    International Nuclear Information System (INIS)

    Within the frame of a project of modification of radioactive waste storage installations, and of refurbishing the Gentilly-2 nuclear plant (Quebec, Canada), the author first gives an overview and comments assessments of the volume and nature of nuclear wastes produced by Canadian nuclear power plants. He presents the Canadian program of nuclear waste management (history, Seaborn assessment Commission, mission of the SGDN-NWMO). He discusses the relationship between risk and dose, the risk duration, and the case of non radioactive wastes. He discusses energy challenges in terms of CO2 emissions and with respect to climate change, proposes an alternative scenario on a long term, compares nuclear energy and wind energy, and discusses the nuclear technology evolution

  4. Nuclear wastes: lets talk about

    International Nuclear Information System (INIS)

    This colloquium is entirely devoted to the problem of nuclear wastes management and to the anxiety of the French public opinion with respect to radioactive wastes in general. Nuclear wastes, generally are perceived as the unique problem of nuclear industry and as a new and unknown problem for which no solutions have been proposed so far. The aim of this colloquium is to demonstrate that such solutions exist and that, probably, they have been more thoroughly examined than in other industrial sectors. The two first talks give the inventory of possible solutions and the policy followed by nuclear operators for the conditioning and packaging of radioactive wastes. The other talks give the point of view of the producers and of the managers of nuclear wastes and the legal aspects of the management and storage of nuclear wastes, in particular the December 30, 1991 law. A particular attention is given to the importance of communication and public information in the successful management of nuclear wastes. (J.S.)

  5. Aspects of nuclear waste management

    International Nuclear Information System (INIS)

    Six areas of concern in nuclear waste management have been dealt with in a four-year Nordic research programme. They include work in two international projects, Hydrocoin dealing with modelling of groundwater flow in crystalline rock, and Biomovs, concerned with biosphere models. Geologic questions of importance to the prediction of future behaviour are examined. Waste quantities from the decommissioning of nuclear power stations are estimated, and total amounts of waste to be transported in the Nordic countries are evaluated. Waste amounts from a hypothetical reactor accident are also calculated. (au)

  6. Progress in nuclear waste disposal

    International Nuclear Information System (INIS)

    Nuclear waste disposal - this is the term or slogan around which turns the continued controversial discussion on power generation in nuclear reactors. The dispute's core is whether the problem of radioactive waste disposal is solved or not. The Federal Government's report on the disposal of radioactive was, passed on the 24. August 1983 says that solutions are available for all partial steps - and plants of nuclear waste disposal. Some of them have proved themselves to be reliable throughout years in industry, or are sufficiently developed, investigated and tried as to present no further obstacle to realisation. (orig.)

  7. Nuclear waste transmutation

    International Nuclear Information System (INIS)

    A deep repository for safe long-term storage of long-lived radioactive materials (waste) arising from nuclear fuel irradiation in reactors is a need generally accepted, whatever the strategy envisaged for further use of the irradiated fuel (e.g.: reprocessing and re-use of uranium and plutonium; no reprocessing and final disposal). To assess the impact on the environment of a waste repository, one is lead naturally to consider the impact of radiation on man and to define the radiotoxicity of the different isotopes. The toxicity of the materials stored in a repository is function of time and at a given time is the sum of the activities of each radionuclide multiplied by appropriate danger coefficients. This time dependent sum R, is a source of 'potential' radiotoxicity. It has been pointed out (in reference 1), that R does not measure 'risk', which has to take into account 'actual pathways and probability of radioactive release to the biosphere'. It is well understood that (e.g. in the case of spent PWR fuel) the main contributor to R are actinides, Pu being the main component (see table I). In the case of risk, the situation is by far more complex and dependent on the modeling of different geological environments. In the analysis made in reference 1 the predominant role of Tc-99, I-129 and Cs-135 has been pointed out. The same analysis also stresses that actinides will be by far less relevant with respect to the highly soluble and mobile fission products. (authors). 13 refs., 2 tabs., 2 figs

  8. Nuclear wastes; Dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Here is made a general survey of the situation relative to radioactive wastes. The different kinds of radioactive wastes and the different way to store them are detailed. A comparative evaluation of the situation in France and in the world is made. The case of transport of radioactive wastes is tackled. (N.C.)

  9. Encapsulation of nuclear wastes

    International Nuclear Information System (INIS)

    Toxic waste materials are encapsulated by the method wherein the waste material in liquid or finely divided solid form is uniformly dispersed in a vinyl ester resin or an unsaturated polyester and the resin cured under conditions that the exotherm does not rise above the temperature at which the integrity of the encapsulating material is destroyed

  10. Storage - Nuclear wastes are overflowing

    International Nuclear Information System (INIS)

    This article highlights that the dismantling of French nuclear installations will generate huge volumes of radioactive wastes and that France may lack space to store them. The Cigeo project (underground storage) only concerns 0.2 per cent of the nuclear waste volume produced by France in 50 years. If storage solutions exist for less active wastes, they will soon be insufficient, notably because of the quantity of wastes produced by the dismantling of existing reactors and fuel processing plants. Different assessments of these volumes are evoked. In order to store them, the ANDRA made a second call for innovating projects which would enable a reduction of this volume by 20 to 30 per cent. The article also evokes projects selected after the first call for projects. They mainly focus on nuclear waste characterization which will result in a finer management of wastes regarding their storage destination. Cost issues and the opposition of anti-nuclear NGOs are still obstacles to the development of new sites

  11. Glasses and nuclear waste vitrification

    International Nuclear Information System (INIS)

    Glass is an amorphous solid material which behaves like an isotropic crystal. Atomic structure of glass lacks long-range order but possesses short and most probably medium range order. Compared to crystalline materials of the same composition glasses are metastable materials however crystallisation processes are kinetically impeded within times which typically exceed the age of universe. The physical and chemical durability of glasses combined with their high tolerance to compositional changes makes glasses irreplaceable when hazardous waste needs immobilisation for safe long-term storage, transportation and consequent disposal. Immobilisation of radioactive waste in glassy materials using vitrification has been used successfully for several decades. Nuclear waste vitrification is attractive because of its flexibility, the large number of elements which can be incorporated in the glass, its high corrosion durability and the reduced volume of the resulting wasteform. Vitrification involves melting of waste materials with glass-forming additives so that the final vitreous product incorporates the waste contaminants in its macro- and micro-structure. Hazardous waste constituents are immobilised either by direct incorporation into the glass structure or by encapsulation when the final glassy material can be in form of a glass composite material. Both borosilicate and phosphate glasses are currently used to immobilise nuclear wastes. In addition to relatively homogeneous glasses novel glass composite materials are used to immobilise problematic waste streams. (author)

  12. French people and nuclear wastes

    International Nuclear Information System (INIS)

    On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

  13. Equity and nuclear waste disposal

    International Nuclear Information System (INIS)

    Following the recommendations of the US National Academy of Sciences and the mandates of the 1987 Nuclear Waste Policy Amendments Act, the US Department of Energy has proposed Yucca Mountain, Nevada as the site of the world's first permanent repository for high-level nuclear waste. The main justification for permanent disposal (as opposed to above-ground storage) is that it guarantees safety by means of waste isolation. This essay argues, however, that considerations of equity (safer for whom?) undercut the safety rationale. The article surveys some prima facie arguments for equity in the distribution of radwaste risks and then evaluates four objections that are based, respectively, on practicality, compensation for risks, scepticism about duties to future generations, and the uranium criterion. The conclusion is that, at least under existing regulations and policies, permanent waste disposal is highly questionable, in part, because it fails to distribute risk equitably or to compensate, in full, for this inequity

  14. Ethical aspects on Nuclear Waste

    International Nuclear Information System (INIS)

    In an ethical assessment of how we shall deal with nuclear waste, one of the chief questions that arises is how to initiate action while at the same time taking into consideration uncertainties which are unavoidable seen from a long-term perspective. By means of different formulation and by proceeding from various starting-points, a two edged objective is established vis-a-vis repository facilities: safety in operation combined with reparability, with controls not necessary, but not impossible. Prerequisites for the realization of this objective are the continued advancement of knowledge and refinement of the qualifications required to deal with nuclear waste. The ethical considerations above could be the bases for the future legislation in the field of nuclear energy waste. (author)

  15. Nuclear power and radioactive waste

    International Nuclear Information System (INIS)

    The gap between the relative perceptions in the area of nuclear waste is wide. The broad view of the industry is that the disposal of nuclear waste is not a serious technical problem, and that solutions are already available to provide safe disposal of all our waste. The broad view of those who oppose the industry is that radioactive waste is so unpleasant, and will remain lethal for so long, that no acceptable policy will ever be developed, and so production of such waste (except, oddly, the significant amounts arising from uses of radioactive materials in medicine, agriculture, industrial safety research, etc) should stop immediately. This booklet will not attempt to describe in great detail the technicalities of the United Kingdom nuclear industry's current approach to radioactive waste: such issues are described in detail in other publications, especially those by Nirex. It is our intention to outline some of the main issues involved, and to associate these issues with the divergence in perceptions of various parties. (author)

  16. Regulating nuclear fuel waste

    International Nuclear Information System (INIS)

    When Parliament passed the Atomic Energy Control Act in 1946, it erected the framework for nuclear safety in Canada. Under the Act, the government created the Atomic Energy Control Board and gave it the authority to make and enforce regulations governing every aspect of nuclear power production and use in this country. The Act gives the Control Board the flexibility to amend its regulations to adapt to changes in technology, health and safety standards, co-operative agreements with provincial agencies and policy regarding trade in nuclear materials. This flexibility has allowed the Control Board to successfully regulate the nuclear industry for more than 40 years. Its mission statement 'to ensure that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment' concisely states the Control Board's primary objective. The Atomic Energy Control Board regulates all aspects of nuclear energy in Canada to ensure there is no undue risk to health, safety, security or the environment. It does this through a multi-stage licensing process

  17. The Public and Nuclear Waste Management.

    Science.gov (United States)

    Zinberg, Dorothy

    1979-01-01

    Discusses the public's negative attitude towards nuclear energy development. Explains the perceptions for the nuclear waste disposal problem, and the concern for the protection of the environment. (GA)

  18. The Geopolitics of Nuclear Waste.

    Science.gov (United States)

    Marshall, Eliot

    1991-01-01

    The controversy surrounding the potential storage of nuclear waste at Yucca Mountain, Nevada, is discussed. Arguments about the stability of the site and the groundwater situation are summarized. The role of the U.S. Department of Energy and other political considerations are described. (CW)

  19. Nuclear waste materials

    International Nuclear Information System (INIS)

    Ion beam techniques were very helpful to gain a better understanding of the behaviour of waste matrices, both glasses and ceramics, under conditions of aqueous corrosion (leaching) and radiation damage. Due to the ease of varying dose, dose rate, energy and type of damaging ions, and due to the powerful nature of ion beam techniques for nondestructive analyses of complex surface layers, ion beams were frequently and successfully applied to matrices for safe long-time storage of radioactive waste. Rutherford-backscattering, elastic recoil detection and reactions with high energy N-beams helped to better understand the chemistry of leaching, to detect enrichment and depletion of glass components and waste at the leached surfaces and to follow synergistic effects in leaching in the near-field of the final repository, hence in the presence of e.g. rock salt and container materials. Radiation effects were simulated with ion beams and interesting results were obtained, in particular on mechanical behaviour of damaged glasses and ceramics, their fracture behaviour etc

  20. Laser induced nuclear waste transmutation

    CERN Document Server

    Hirlimann, Charles

    2016-01-01

    When producing electricity that collects the mass energy that is available at the time of the induced disintegration of radioactive elements, other unstable elements are produced with half-life span durations ranging from less than one second to hundreds of thousands of years and which are considered as waste. Managing nuclear waste with a half-life of less than 30 years is an easy task, as our societies clearly know how to keep buildings safe for more than a century, the time it takes for the activity to be divided by a factor of 8. High-activity, long-lasting waste that can last for thousands of years or even longer, up to geological time laps, cannot be taken care of for such long durations. Therefore, these types of waste are socially unacceptable; nobody wants to leave a polluted planet to descendants.

  1. Electron caustic lithography

    OpenAIRE

    S. M. KENNEDY; Zheng, C. X.; J. Fu; Tang, W. X.; Paganin, D. M.; Jesson, D. E.

    2012-01-01

    A maskless method of electron beam lithography is described which uses the reflection of an electron beam from an electrostatic mirror to produce caustics in the demagnified image projected onto a resist–coated wafer. By varying the electron optics, e.g. via objective lens defocus, both the morphology and dimensions of the caustic features may be controlled, producing a range of bright and tightly focused projected features. The method is illustrated for line and fold caustics and is compleme...

  2. FULL-SCALE TESTING OF A CAUSTIC SIDE SOLVENT EXTRACTION SYSTEM TO REMOVE CESIUM FROM SAVANNAH RIVER SITE RADIOACTIVE WASTE

    International Nuclear Information System (INIS)

    Savannah River Site (SRS) personnel have completed construction and assembly of the Modular Caustic Side Solvent Extraction Unit (MCU) facility. Following assembly, they conducted testing to evaluate the ability of the process to remove non-radioactive cesium and to separate the aqueous and organic phases. They conducted tests at salt solution flow rates of 3.5, 6.0, and 8.5 gpm. During testing, the MCU Facility collected samples and submitted them to Savannah River National Laboratory (SRNL) personnel for analysis of cesium, Isopar(regsign) L, and Modifier [1-(2,2,3,3-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol]. SRNL personnel analyzed the aqueous samples for cesium by Inductively-Coupled Plasma Mass Spectroscopy (ICP-MS) and the solvent samples for cesium using a Parr Bomb Digestion followed by ICP-MS. They analyzed aqueous samples for Isopar(regsign) L and Modifier by gas chromatography (GC)

  3. Field demonstration of in situ treatment of buried low-level radioactive solid waste with caustic soda and soda ash to immobilize 90Sr

    International Nuclear Information System (INIS)

    A low-level radioactive solid waste disposal trench was injected on four occasions with solutions of caustic soda, soda ash, caustic soda, and lime/soda ash, respectively. Because investigations had indicated that 90Sr could be coprecipitated with soil calcium carbonate by treatment with soda ash, this demonstration was undertaken as a test of its technical feasibility. After concentrations of 90Sr and water hardness decreased within the intratrench monitoring wells; one well at the foot of the trench decreased from over 100 to a persistent level of less than 10 kBq of 90Sr per liter. Recharge of 90Sr from the trench to a sump immediately below was reduced by about 90%. Water hardness and 90Sr concentrations were strongly correlated through time within each monitoring well, indicating that 90Sr behaved as a tracer for soil calcium and magnesium. The disappearance of 90Sr from the trench water, therefore, was an in situ water softening. Soil samples retrieved from the trench indicated that as much as 98% of the total 90Sr was present as a coprecipitate with calcium carbonate. The hydrologic characterization of this trench indicated an average void space of 41% and an average trench-wall hydraulic conductivity of 3.4 x 10-7 m/s. Sampling of the trench's discharge contamination plume indicated that it had resulted from a combination of subsurface seepage and bathtub overflow during infrequent periods of intense precipitation. A generic assessment of soda ash treatment indicated that treatment would be most effective for soils of high cation exchange capacity with either low ( 80%) basic cation saturation of that cation exchange capacity

  4. Geopolitics of nuclear waste

    International Nuclear Information System (INIS)

    More debate has begun over questions related to the safety of high-level waste disposal at the Yucca Mountain site in the Nevada desert. An engineering geologists, Jerry Szymanski, one of the Department of Energy's (DOE) own staffers in Las Vegas, has proposed that the $15-billion repository would sit on top of an intensely active structure that, if altered by an earthquake, would send a slug of ground water up from deep within the mountain into the waste storage area. This theory has already been slammed in two formal reviews and has virtually no support among geologists. However, enough doubt has been raised that much more geological testing will be necessary to prove or disprove Szymanski's theory. Nevada state officials are also using all methods to thwart or block the project. The question of the origin of a series of calcium carbonate and opal veins exposed in an exploratory pit, trench 14, near the top of the mountain is also far from answered. The DOE and US Geological Survey may have to collect much more information on the quantity, size, and location of carbonate sites in the area at a high financial outlay to the US government before a complete case on the origin of the material in trench 14 can be made

  5. Nuclear wastes and public trust

    International Nuclear Information System (INIS)

    Citing public fear and mistrust, strong opposition to the proposed Yucca Mountain repository site, and less-than-exemplary performance by the Department of Energy (DOE), two private researchers believe present high-level radioactive waste-disposal plans may have to be scrapped. Government and the nuclear industry may have to start over. Policy makers should seek to develop new relationships with communities and states where suitable disposal sites exist. These relationships may require that citizen groups and local institutions be given unprecedented authority in locating and operating such facilities. Contrary to popular impressions, there is still time to take a new approach. The US Nuclear Regulatory Commission says present on-site storage arrangements offer a safe alternative for 100 years or more. The sense of immediate crisis and cries for immediate solutions should be calmed and a more considered strategy brought to the public debate. For starters, the researchers propose that the problems of defense waste be separated from the problems of commercial waste. They also suggest that DOE be assigned responsibility for defense waste and a new agency be created to handle high-level commercial waste

  6. Development of the Next-Generation Caustic-Side Solvent Extraction (NG-CSSX) Process for Cesium Removal from High-Level Tank Waste

    International Nuclear Information System (INIS)

    This paper describes the chemical performance of the Next-Generation Caustic-Side Solvent Extraction (NG-CSSX) process in its current state of development for removal of cesium from the alkaline high-level tank wastes at the Savannah River Site (SRS) in the US Department of Energy (USDOE) complex. Overall, motivation for seeking a major enhancement in performance for the currently deployed CSSX process stems from needs for accelerating the cleanup schedule and reducing the cost of salt-waste disposition. The primary target of the NG-CSSX development campaign in the past year has been to formulate a solvent system and to design a corresponding flowsheet that boosts the performance of the SRS Modular CSSX Unit (MCU) from a current minimum decontamination factor of 12 to 40,000. The chemical approach entails use of a more soluble calixarene-crown ether, called MaxCalix, allowing the attainment of much higher cesium distribution ratios (DCs) on extraction. Concurrently decreasing the Cs-7SB modifier concentration is anticipated to promote better hydraulics. A new stripping chemistry has been devised using a vitrification-friendly aqueous boric acid strip solution and a guanidine suppressor in the solvent, resulting in sharply decreased DCs on stripping. Results are reported herein on solvent phase behavior and batch Cs distribution for waste simulants and real waste together with a preliminary flowsheet applicable for implementation in the MCU. The new solvent will enable MCU to process a much wider range of salt feeds and thereby extend its service lifetime beyond its design life of three years. Other potential benefits of NG-CSSX include increased throughput of the SRS Salt Waste Processing Facility (SWPF), currently under construction, and an alternative modular near-tank application at Hanford.

  7. Laser induced nuclear waste transmutation

    OpenAIRE

    Hirlimann, Charles

    2007-01-01

    When producing electricity that collects the mass energy that is available at the time of the induced disintegration of radioactive elements, other unstable elements are produced with half-life span durations ranging from less than one second to hundreds of thousands of years and which are considered as waste. Managing nuclear waste with a half-life of less than 30 years is an easy task, as our societies clearly know how to keep buildings safe for more than a century, the time it takes for th...

  8. Nuclear waste and hazardous waste in the public perception

    International Nuclear Information System (INIS)

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  9. Nuclear waste and hazardous waste in the public perception

    Energy Technology Data Exchange (ETDEWEB)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael [ETH Zurich (Switzerland). Inst. for Environmental Decisions

    2015-07-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  10. Nuclear waste: A cancer cure?

    International Nuclear Information System (INIS)

    In a marriage of strange bedfellows, scientists at one of the country's most contaminated nuclear waste sites are collaborating with medical researchers to turn nuclear waste into an experimental therapy for cancer. Patients with Hodgkin's disease and brain, ovarian, and breast cancers may be able to receive the new radiatio-based treatments in the next five to ten years. Recently, scientists at the Hanford site found a way to chemically extract a pure form of the radioisotope yttrium-90 from strontium-90, a by-product of plutonium production. Yttrium-90 is being tested in clinical trials at medical centers around the country as a treatment for various types of cancers, and the initial results are encouraging. The advantage of yttrium-90 over other radioisotopes is its short half-life

  11. Nuclear waste immobilization. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    Ringwood, A.E.; Sinclair, W.; McLaughlin, G.M.

    1979-11-20

    United States defense nuclear wastes are presently in tank storage, largely as sludges comprising Fe, Mn, Ni, U and Na oxides and hydroxides, together with 0.5 to 5 percent of fission products and actinides (exclusive of uranium). The relative proportions of Al, Fe, Mn, Ni, U and Na in the sludges from different tanks vary considerably, except that (Fe + Al + Mn) are by far the major components and Fe is more abundant than Mn. Typical compositions of some calcined sludges from Savannah River are given. This paper briefly describes how the SYNROC process, utilizing straightforward technology, can be readily adapted to the problem of defense waste immobilization, yielding a dense, inert, ceramic waste-form, SYNROC-D. Two classes of processes are discussed - one designed to immobilize sludges containing normal amounts of sodium and the other designed for otherwise similar sludges which are, however, strongly depleted in sodium as a result of more efficient washing procedures.

  12. Nuclear waste immobilization. Progress report

    International Nuclear Information System (INIS)

    United States defense nuclear wastes are presently in tank storage, largely as sludges comprising Fe, Mn, Ni, U and Na oxides and hydroxides, together with 0.5 to 5 percent of fission products and actinides (exclusive of uranium). The relative proportions of Al, Fe, Mn, Ni, U and Na in the sludges from different tanks vary considerably, except that (Fe + Al + Mn) are by far the major components and Fe is more abundant than Mn. Typical compositions of some calcined sludges from Savannah River are given. This paper briefly describes how the SYNROC process, utilizing straightforward technology, can be readily adapted to the problem of defense waste immobilization, yielding a dense, inert, ceramic waste-form, SYNROC-D. Two classes of processes are discussed - one designed to immobilize sludges containing normal amounts of sodium and the other designed for otherwise similar sludges which are, however, strongly depleted in sodium as a result of more efficient washing procedures

  13. Nuclear wastes and public acceptance

    International Nuclear Information System (INIS)

    A new approach to the storage of nuclear wastes is described. Certain criteria for a nuclear waste storage system that is based on ideas of technical soundess and public acceptability are set forth. These criteria are 1.) the wastes must be reliably contained at all times, 2.) the containers must be retrievable and maintainable, 3.) the storage facility must also provide isolation from external events and must also permit careful control of human access, 4.) the storage facility and containers must have plausible or demonstratble likelihood of lasting for 100 years, and 5.) the storage system should be able to accept and retrieve both processed waste and spent fuel elements interchangeably. A specific storage system concept that is based on proved data and that meets the 5 criteria is described. The waste, either glassified high-level waste or spent fuel-fuel bundles from which the end structures have been removed, is stored in sealed stainless steel containers, which is sealed in a second sealed container made of a durable metal such as Ti. The space between the two containers is filled with a gas that can be detected at very low concentrations. These containers are stored in a tunnel excavated into the side of a convenient mountain. The tunnel is excavated above flood level, is accessible by rail and/or road, and is designed for self-draining. A free-standing inner lining is constructed within the tunnel. Offset vertical shafts provide for ventilation. Continuous monitoring leak detectors are maintained in the tunnel and in the stack

  14. Electrochemical generation of Fenton's reagent to treat spent caustic wastewater

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, H. K.; Nunez, P.; Rodriguez, N.; Guzman, J.

    2009-07-01

    An important wastewater stream from oil refineries is the spent caustic. Caustic solutions are used as scrubbing agent during the desulphurization process to eliminate sulphur an mercaptans from oil and gasses. Spent caustic is classified as DOO3 (reactive sulphide) hazardous waste under the US Resource Conservation and Recovery Act (RCRA). (Author)

  15. Nuclear wastes: fission

    International Nuclear Information System (INIS)

    Progress is reported on investigations of transuranics in soils and plants that have demonstrated the importance of valence state, complexation, competing elements, migration down the soil profile, and weathering cycles in governing transuranic, 129I and 99Tc availability to plants and, in the case of Pu, to the consuming animals. In the latter case, it was demonstrated, for the first time, that ingestion of plant tissues containing Pu may result in greater transfer across the gut compared to gavaging animals with inorganic Pu solutions, underscoring the importance of detailed studies of the soil, plant, and animal factors influencing uptake by the ingestion pathway. Further evidence of the importance of the ingestion pathway was provided in studies of foliar interception of airborne transuranic elements in which it was shown that Pu in particles in the respiratory size range were effectively intercepted and retained by plants, and significant quantities of intercepted Pu were transported to roots and seeds. Similar studies on the terrestrial ingestion pathway have been initiated with other actinides including, U, Am, Cm, and Np. Radioecological field studies were directed toward establishment of pertinent ingestion pathways and exposure levels through description of habitat types, population densities, and, in several instances, dosimetry, for major insects, reptiles, birds, and mammalian species. These studies were extended to agricultural ecosystems through definition of the uptake of long-lived nuclides and digestibility in cattle of several forage species. In studies on a pond ecosystem at the nuclear fuel reprocessing plant, Pu and Am uptake rates were studied for major biotic components including organic floc, algae, fish, and ducks. The results indicated that assimilation of transuranics by the biota and export from the pond system were low compared to the total inventory

  16. Plasma filtering techniques for nuclear waste remediation

    CERN Document Server

    Gueroult, Renaud; Fisch, Nathaniel J

    2015-01-01

    Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. This advantage may be realized over a large range of chemical waste compositions, thereby addressing the heterogeneity of legacy nuclear waste.

  17. Final disposal of nuclear waste

    International Nuclear Information System (INIS)

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

  18. Final disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1995-10-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

  19. Nuclear waste management. Semiannual progress report, October 1983-March 1984

    International Nuclear Information System (INIS)

    Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables

  20. Waste management in the nuclear engineering curriculum

    International Nuclear Information System (INIS)

    One of the most significant challenges facing the nuclear industry is to successfully close the nuclear fuel cycle and effectively demonstrate to the public that nuclear wastes do not present a health risk. This issue is currently viewed by many as the most important issue affecting public acceptance of nuclear power, and it is imperative that nuclear engineers be able to effectively address the question of nuclear waste from both a generation and disposal standpoint. To address the issue, the area of nuclear waste management has been made one of the fields of specialized study in the Department of Nuclear Engineering Sciences at the University of Florida. The study of radioactive waste management at the University of Florida is designed both for background for the general nuclear engineering student and for those wishing to specialize in it as a multidiscipline study area involving the Departments of Nuclear Engineering Sciences, Environmental Sciences, Material Science and Engineering, Geology, Civil Engineering, and Industrial Engineering

  1. Organic diagenesis in commercial nuclear wastes

    International Nuclear Information System (INIS)

    The nuclear industry currently faces numerous challenges. Large volumes of already existing wastes must be permanently disposed using environmentally acceptable technologies. Numerous criteria must be addressed before wastes can be permanently disposed. Waste characterization is certainly one of the key criteria for proper waste management. some wastes are complex melting pots of inorganics, radiochemicals, and, occasionally, organics. It is clear, for example, that organics have been used extensively in nuclear operations, such as waste reprocessing, and continue to be used widely as solvents, decontamination agents, etc. The authors have analyzed the organic content of many kinds of nuclear wastes, ranging from commercial to defense wastes. In this paper, the finale analyses are described of three commercial wastes: one waste from a pressurized water reactor (PWR) and two wastes from a boiling water reactor (BWR). The PWR waste is a boric acid concentrate waste. The two BWR wastes, BWR wastes Nos. 1 and 2, are evaporator concentrates of liquid wastes produced during the regeneration of ion-exchange resins used to purify reactor process water. In preliminary analyses, which were reported previously, a few know organics and myriad unknowns were detected. Recent reexamination of mass-spectral data, coupled with reanalysis of the wastes, has resulted in the firm identification of the unknowns. Most of the compounds, over thirty distinct organics, are derived from the degradation, or diagenesis, of source-term organics, revealing, for the first time, that organic diagenesis in commercial wastes is both vigorous and varied

  2. Electron caustic lithography

    Directory of Open Access Journals (Sweden)

    S. M. Kennedy

    2012-06-01

    Full Text Available A maskless method of electron beam lithography is described which uses the reflection of an electron beam from an electrostatic mirror to produce caustics in the demagnified image projected onto a resist–coated wafer. By varying the electron optics, e.g. via objective lens defocus, both the morphology and dimensions of the caustic features may be controlled, producing a range of bright and tightly focused projected features. The method is illustrated for line and fold caustics and is complementary to other methods of reflective electron beam lithography.

  3. Uranium immobilization and nuclear waste

    International Nuclear Information System (INIS)

    Considerable information useful in nuclear waste storage can be gained by studying the conditions of uranium ore deposit formation. Further information can be gained by comparing the chemistry of uranium to nuclear fission products and other radionuclides of concern to nuclear waste disposal. Redox state appears to be the most important variable in controlling uranium solubility, especially at near neutral pH, which is characteristic of most ground water. This is probably also true of neptunium, plutonium, and technetium. Further, redox conditions that immobilize uranium should immobilize these elements. The mechanisms that have produced uranium ore bodies in the Earth's crust are somewhat less clear. At the temperatures of hydrothermal uranium deposits, equilibrium models are probably adequate, aqueous uranium (VI) being reduced and precipitated by interaction with ferrous-iron-bearing oxides and silicates. In lower temperature roll-type uranium deposits, overall equilibrium may not have been achieved. The involvement of sulfate-reducing bacteria in ore-body formation has been postulated, but is uncertain. Reduced sulfur species do, however, appear to be involved in much of the low temperature uranium precipitation. Assessment of the possibility of uranium transport in natural ground water is complicated because the system is generally not in overall equilibrium. For this reason, Eh measurements are of limited value. If a ground water is to be capable of reducing uranium, it must contain ions capable of reducing uranium both thermodynamically and kinetically. At present, the best candidates are reduced sulfur species

  4. Southeastern Utah Nuclear Waste Transportation Study

    OpenAIRE

    Bechtel Group Inc.

    1982-01-01

    This report is published as a product of the National Waste Terminal Storage (NWTS) Program. The objective of this program is the development of terminal waste storage facilities in deep stable geologic formations for high-level nuclear waste, including spent fuel elements from commercial power reactors and transuranic nuclear waste for which the Federal Government is responsible. The initial purpose of this study was to analyze and compare possible transport modes and corridors connectin...

  5. Plasma filtering techniques for nuclear waste remediation

    OpenAIRE

    Gueroult, Renaud; Hobbs, David T.; Fisch, Nathaniel J.

    2015-01-01

    Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. This advantage may be realized over a large rang...

  6. Questions concerning nuclear waste management

    International Nuclear Information System (INIS)

    The Federal Republic of Germany has a technical concept for nuclear waste management which is convincing in the main elements of its structure. The orderly disposal of radioactive waste does not present a problem in terms of quantity in relation with comparable toxicity. The scientific-technical overall concept also corresponds to a conclusive, yet open-to-development legislative-administrative concept with a versatile and strict monitoring and control system. The German Atomic Energy Act (AtG) has proved its worth also in the main points of the 'disposal part'. When amending the Act, some changes have to be considered, one of them being: Stipulating the obligation to produce evidence of disposal provisions as an official precondition for licensing in section 7, subsection (2) AtG. (orig./HSCH)

  7. Actor notebook on the debate over nuclear waste management - Are nuclear wastes manageable?

    International Nuclear Information System (INIS)

    After a recall of some generalities on nuclear wastes (notably high-activity long life wastes like fission products and actinides), and the acceptability of sub-surface and deep disposal, this article discusses the quantities of wastes produced by the nuclear sector, and outlines that phasing out nuclear would result in higher quantities of wastes to be managed than a situation of a sustainable nuclear scenario. It compares nuclear wastes with other hazardous or toxic industrial wastes. It addresses the solution of a deep geological disposal of nuclear wastes, identifies and discusses risks of underground water contamination, risks for the population and for the environment. It outlines that the development of the separation-transmutation technology could significantly decrease the cost of nuclear waste management. It finally evokes the issue of waste management funding

  8. STRONTIUM AND ACTINIDE SEPARATIONS FROM HIGH LEVEL NUCLEAR WASTE SOLUTIONS USING MONOSODIUM TITANATE 1. SIMULANT TESTING

    Energy Technology Data Exchange (ETDEWEB)

    HOBBS, D. T.; BARNES, M. J.; PULMANO, R. L.; MARSHALL, K. M.; EDWARDS, T. B.; BRONIKOWSKI, M. G.; FINK, S. D.

    2005-04-14

    High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 137}Cs, {sup 90}Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for {sup 137}Cs removal, and ion exchange/sorption of {sup 90}Sr and alpha-emitting radionuclides with an inorganic material, monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes {sup 238}Pu, {sup 239}Pu and {sup 240}Pu. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from simulated waste solutions. These tests evaluated the influence of ionic strength, temperature, solution composition and the oxidation state of plutonium.

  9. Nuclear waste management, reactor decommisioning, nuclear liability and public attitudes

    International Nuclear Information System (INIS)

    This paper deals with several issues that are frequently raised by the public in any discussion of nuclear energy, and explores some aspects of public attitudes towards nuclear-related activities. The characteristics of the three types of waste associated with the nuclear fuel cycle, i.e. mine/mill tailings, reactor wastes and nuclear fuel wastes, are defined, and the methods currently being proposed for their safe handling and disposal are outlined. The activities associated with reactor decommissioning are also described, as well as the Canadian approach to nuclear liability. The costs associated with nuclear waste management, reactor decommissioning and nuclear liability are also discussed. Finally, the issue of public attitudes towards nuclear energy is addressed. It is concluded that a simple and comprehensive information program is needed to overcome many of the misconceptions that exist about nuclear energy and to provide the public with a more balanced information base on which to make decisions

  10. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John [Idaho National laboratory, 2525 Fremont Ave., Idaho Falls, ID 83402 (United States)

    2008-07-01

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  11. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

    2008-05-01

    The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

  12. Global Nuclear Energy Partnership Waste Treatment Baseline

    International Nuclear Information System (INIS)

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  13. Nuclear energy from radioactive waste

    International Nuclear Information System (INIS)

    The global energy demand is increasing. Sound forecasts indicate that by the year 2020 almost eight thousand million people will be living on our planet, and generating their demand for energy will require conversion of about 20 thousand million tonnes of coal equivalents a year. Against this background scenario, a new concept for energy generation elaborated by nuclear scientists at CERN attracts particular interest. The concept describing a new nuclear energy source and technology intends to meet the following principal requirements: create a new energy source that can be exploited in compliance with extremely stringent safety requirements; reduce the amount of long-lived radioactive waste; substantially reduce the size of required radwaste repositories; use easily available natural fuels that will not need isotopic separation; prevent the risk of proliferation of radioactive materials; process and reduce unwanted actinides as are generated by the operation of current breeder reactors; achieve high efficiency both in terms of technology and economics. (orig./CB)

  14. Plasma filtering techniques for nuclear waste remediation

    International Nuclear Information System (INIS)

    Highlights: • A detailed economic study on plasma mass filtering techniques is presented. • Comparison with chemical techniques shows similar costs for solid-waste pretreatment. • Significant savings potential is identified through superior waste minimization. - Abstract: Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. This advantage may be realized over a large range of chemical waste compositions, thereby addressing the heterogeneity of legacy nuclear waste

  15. Nuclear waste disposal: Gambling on Yucca Mountain

    International Nuclear Information System (INIS)

    This document describes the historical aspects of nuclear energy ,nuclear weapons usage, and development of the nuclear bureaucracy in the United States, and discusses the selection and siting of Yucca Mountain, Nevada for a federal nuclear waste repository. Litigation regarding the site selection and resulting battles in the political arena and in the Nevada State Legislature are also presented. Alternative radioactive waste disposal options, risk assessments of the Yucca Mountain site, and logistics regarding the transportation and storage of nuclear waste are also presented. This document also contains an extensive bibliography

  16. Nuclear waste hearings - a three ring circus?

    International Nuclear Information System (INIS)

    The article is a personal commentary by Dr. H. Tammemagi on the hearings held on the deep geologic concept for nuclear fuel waste disposal. He condemns the anti-nuclear proponents of voicing opinions not based on fact while they accuse the nuclear proponents of not making decisions on a nuclear waste disposal facility based on enough facts. He uses the Mars and Venus analogy of a popular book to bring forth his point

  17. Rethinking the nuclear waste program

    International Nuclear Information System (INIS)

    Based on a review of the U.S. Department of Energy's (DOE) Crystalline Repository Project, this paper recommends major changes in the federal nuclear waste program to restore state, Indian Tribe, and public confidence, in the event that a new geologic repository siting effort is needed. First, the authors recommend refinements in the site selection process, including the addition of new screening variables and a return to the original four-step screening process (national, regional, area, and location surveys leading up to site characterization). Most of the geotechnical field studies now planned for the site characterization phase should be moved forward to the location phase. This would reduce the likelihood of constructing an exploratory shaft facility, potentially costing one billion dollars or more, at a site technically unsuitable for repository development. Second, they recommend a new approach to socioeconomic impacts. The current approach fails to recognize that adverse economic impacts may begin to occur as early as the identification of candidate areas and ignores the fear of economic damages to families and individuals. Detailed economic compensation programs should be developed in consultation with states, tribes and local communities, early in the siting process, preferably prior to designation of candidate areas. Third, they recommend removal of the nuclear waste program from DOE

  18. Nuclear waste repository simulation experiments

    International Nuclear Information System (INIS)

    This document is the third joint annual report on the Cooperative German-American 'Brine Migration Tests' that are in progress at the Asse salt mine in the Federal Republic of Germany (FRG). This Government supported mine serves as an underground test facility for research and development (R and D)-work in the field of nuclear waste repository research and simulation experiments. The tests are designed to simulate a nuclear waste repository to measure the effects of heat and gamma radiation on brine migration, salt decrepitation, disassociation of brine, and gases collected. The thermal mechanical behavior of salt, such as room closure, stresses and changes of the properties of salt are measured and compared with predicted behavior. This document covers the following sections: Issues and test objectives: This section presents issues that are investigated by the Brine Migration Test, and the test objectives derived from these issues; test site: This section describes the test site location and geology in the Asse mine; test description: A description of the test configuration, procedures, equipment, and instrumentation is given in this section; actual test chronology: The actual history of the test, in terms of the dates at which major activities occured, is presented in this section. Test results: This section presents the test results observed to data and the planned future work that is needed to complete the test; conclusions and recommendations: This section summarizes the conclusions derived to date regarding the Brine Migration Test. Additional work that would be useful to resolve the issues is discussed. (orig.)

  19. Transport and nuclear waste disposal

    International Nuclear Information System (INIS)

    The author assesses both past and future of nuclear waste disposal in Germany. The failure of the disposal concept is, he believes, mainly the fault of the Federal Government. On the basis of the Nuclear Energy Act, the government is obliged to ensure that ultimate-storage sites are established and operated. Up to the present, however, the government has failed - apart from the episode in Asse and Morsleben and espite existing feasible proposals in Konrad and Gorleben - to achieve this objective. This negative development is particularly evident from the projects which have had to be prematurely abandoned. The costs of such 'investment follies' meanwhile amount to several billion DM. At least 92% of the capacity in the intermediate-storage sites are at present unused. Following the closure of the ultimate-storage site in Morsleben, action must be taken to change over to long-term intermediate-storage of operational waste. The government has extensive intermediate-storage capacity at the intermediate-storage site Nord in Greifswald. There, the wate originally planned for storage in Morsleben could be intermediately stored at ERAM-rates. Nuclear waste transportation, too, could long ago have been resumed, in the author's view. For the purpose of improving the transport organisation, a new company was founded which represents exclusively the interests of the reprocessing firms at the nuclear power stations. The author's conclusion: The EVU have done their homework properly and implemented all necessary measures in order to be able to resume transport of fuel elements as soon as possible. The generating station operators favour a solution based upon agreement with the Federal Government. The EVU have already declared their willingness - in the event of unanimous agreement - to set up intermediate-storage sites near the power stations. The ponds in the generating stations, however, are unsuitable for use as intermediate-storage areas. If intermediate-storage areas for

  20. Nuclear waste in public acceptance

    International Nuclear Information System (INIS)

    The existing problem on a faithful acceptance of nuclear information by population is connected, to a considerable extent, with a bad nuclear 'reputation' because of a great amount of misrepresented and false information from 'the greens'. In contrast to a bare style of professionals often neglecting an emotional perception, a loud voice of 'the greens' appeals both to the head, and to the heart of the audience. People pattern their behaviour weakly on problems of safe application of different irradiation sources in industry, conditions of life, medicine and everyday life. Radiation danger of some sources is often exaggerated (computers, nuclear technologies, radiation treatment) and the danger of the others is, on the contrary, underestimated (nuclear and roentgen methods of diagnostics and medical treatment). The majority of our citizens do not know which level of radiation is normal and safe, which ways radioactive substances intake into the organism of a human being and how to diminish the dose load on the organism by simple measures. Only specialists can be orientated themselves in a great number of radiation units. Low level of knowledge of the population and false conceptions are connected with the fact that they are mainly informed about nuclear technologies from mass media, where the voice of 'Greenpeace' is loudly sounded, but they often give misrepresented and false information doing it in the very emotional form. In contrast to them, scientists-professionals often ignore a sensitive part of apprehending of information and do not attach importance to it. As a rule, the style of specialists is of a serious academician character when they meet with the public. People preconception to nuclear waste and distrust to a positive information concerning nuclear technologies are explained, to a considerable extent, by a bivalent type of thinking when people operate by two opposite conceptions only, such as 'there is' or 'there is not' (there is or there is not

  1. Nuclear waste and nuclear ethics. Societal and ethical aspects of retrievable storage of nuclear waste

    International Nuclear Information System (INIS)

    The aim of the literature study on the title subject is to provide information to researchers, engineers, decision makers, administrators, and the public in the Netherlands on the subject of retrievable storage of nuclear waste, mainly from nuclear power plants. Conclusions and recommendations are formulated with respect to retrievability and ethics, sustainability, risk assessment, information transfer, environmental impacts, and discussions on radioactive waste storage. 170 refs

  2. Nuclide inventory for nuclear fuel waste management

    International Nuclear Information System (INIS)

    To assist research projects in the Canadian Nuclear Fuel Waste Management Prgram, a compilation has been made of all the nuclides that are likely to be present in a nuclear fuel waste disposal vault and that are potentially hazardous to man during the post-closure phase. The compilation includes radiologically toxic and chemically toxic nuclides

  3. Waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    The present lecture deals with energy needs and nuclear power, the importance of waste and its relative place in the fuel cycle, the games of controversies over nuclear waste in the strategies of energy and finally with missions and functions of the IAEA for privileging the rational approach and facilitating the transfer of technology. (RW)

  4. Nuclear wastes: society problem or technical question?

    International Nuclear Information System (INIS)

    During this conference day organized by the French society of nuclear energy (SFEN), several aspects of nuclear wastes were discussed and are summarized in this short paper: the dialectics of nuclear wastes; the point of view of the 'Robin des Bois' ecologist association; the safety of wastes; the French law from December 30, 1991 (separation-transmutation, deep underground disposal, packaging and storage); three examples of natural confinement analogues (uranium mines and Oklo 'reactor'); the point of view of the national commission of evaluation; the hidden aspects of communication in the domain of nuclear wastes; the other projects and studies in OECD countries; the management of wastes at the end of the fuel cycle; the main highlights of 1999 relative to the image of nuclear power in the media. (J.S.)

  5. Nuclear waste disposal educational forum

    Energy Technology Data Exchange (ETDEWEB)

    1982-10-18

    In keeping with a mandate from the US Congress to provide opportunities for consumer education and information and to seek consumer input on national issues, the Department of Energy's Office of Consumer Affairs held a three-hour educational forum on the proposed nuclear waste disposal legislation. Nearly one hundred representatives of consumer, public interest, civic and environmental organizations were invited to attend. Consumer affairs professionals of utility companies across the country were also invited to attend the forum. The following six papers were presented: historical perspectives; status of legislation (Senate); status of legislation (House of Representatives); impact on the legislation on electric utilities; impact of the legislation on consumers; implementing the legislation. All six papers have been abstracted and indexed for the Energy Data Base.

  6. Nuclear waste disposal educational forum

    International Nuclear Information System (INIS)

    In keeping with a mandate from the US Congress to provide opportunities for consumer education and information and to seek consumer input on national issues, the Department of Energy's Office of Consumer Affairs held a three-hour educational forum on the proposed nuclear waste disposal legislation. Nearly one hundred representatives of consumer, public interest, civic and environmental organizations were invited to attend. Consumer affairs professionals of utility companies across the country were also invited to attend the forum. The following six papers were presented: historical perspectives; status of legislation (Senate); status of legislation (House of Representatives); impact on the legislation on electric utilities; impact of the legislation on consumers; implementing the legislation. All six papers have been abstracted and indexed for the Energy Data Base

  7. SALTSTONE VAULT CLASSIFICATION SAMPLES MODULAR CAUSTIC SIDE SOLVENT EXTRACTION UNIT/ACTINIDE REMOVAL PROCESS WASTE STREAM APRIL 2011

    Energy Technology Data Exchange (ETDEWEB)

    Eibling, R.

    2011-09-28

    Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained by SRNL on April 5, 2011 (Tank 50H sampling occurred on April 4, 2011) during 2QCY11 to determine the non-hazardous nature of the grout and for additional vault classification analyses. The samples were cured and shipped to Babcock & Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B&W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TCLP) and subsequent extract analysis on saltstone samples for the analytes required for the quarterly analysis saltstone sample. In addition to the eight toxic metals - arsenic, barium, cadmium, chromium, mercury, lead, selenium and silver - analytes included the underlying hazardous constituents (UHC) antimony, beryllium, nickel, and thallium which could not be eliminated from analysis by process knowledge. Additional inorganic species determined by B&W TSG-RACL include aluminum, boron, chloride, cobalt, copper, fluoride, iron, lithium, manganese, molybdenum, nitrate/nitrite as Nitrogen, strontium, sulfate, uranium, and zinc and the following radionuclides: gross alpha, gross beta/gamma, 3H, 60Co, 90Sr, 99Tc, 106Ru, 106Rh, 125Sb, 137Cs, 137mBa, 154Eu, 238Pu, 239/240Pu, 241Pu, 241Am, 242Cm, and 243/244Cm. B&W TSG-RACL provided subsamples to GEL Laboratories, LLC for analysis for the VOCs benzene, toluene, and 1-butanol. GEL also determines phenol (total) and the following radionuclides: 147Pm, 226Ra and 228Ra. Preparation of the 2QCY11 saltstone samples for the quarterly analysis and for vault classification purposes and the subsequent TCLP analyses of these samples showed that: (1) The saltstone waste form disposed of in the Saltstone Disposal Facility in 2QCY11 was not characteristically hazardous for toxicity. (2) The concentrations of the eight RCRA metals and UHCs identified as possible in the saltstone waste form were present at levels below the UTS. (3) Most of the

  8. Saltstone Vault Classification Samples Modular Caustic Side Solvent Extraction Unit/Actinide Removal Process Waste Stream April 2011

    International Nuclear Information System (INIS)

    Savannah River National Laboratory (SRNL) was asked to prepare saltstone from samples of Tank 50H obtained by SRNL on April 5, 2011 (Tank 50H sampling occurred on April 4, 2011) during 2QCY11 to determine the non-hazardous nature of the grout and for additional vault classification analyses. The samples were cured and shipped to Babcock and Wilcox Technical Services Group-Radioisotope and Analytical Chemistry Laboratory (B and W TSG-RACL) to perform the Toxic Characteristic Leaching Procedure (TCLP) and subsequent extract analysis on saltstone samples for the analytes required for the quarterly analysis saltstone sample. In addition to the eight toxic metals - arsenic, barium, cadmium, chromium, mercury, lead, selenium and silver - analytes included the underlying hazardous constituents (UHC) antimony, beryllium, nickel, and thallium which could not be eliminated from analysis by process knowledge. Additional inorganic species determined by B and W TSG-RACL include aluminum, boron, chloride, cobalt, copper, fluoride, iron, lithium, manganese, molybdenum, nitrate/nitrite as Nitrogen, strontium, sulfate, uranium, and zinc and the following radionuclides: gross alpha, gross beta/gamma, 3H, 60Co, 90Sr, 99Tc, 106Ru, 106Rh, 125Sb, 137Cs, 137mBa, 154Eu, 238Pu, 239/240Pu, 241Pu, 241Am, 242Cm, and 243/244Cm. B and W TSG-RACL provided subsamples to GEL Laboratories, LLC for analysis for the VOCs benzene, toluene, and 1-butanol. GEL also determines phenol (total) and the following radionuclides: 147Pm, 226Ra and 228Ra. Preparation of the 2QCY11 saltstone samples for the quarterly analysis and for vault classification purposes and the subsequent TCLP analyses of these samples showed that: (1) The saltstone waste form disposed of in the Saltstone Disposal Facility in 2QCY11 was not characteristically hazardous for toxicity. (2) The concentrations of the eight RCRA metals and UHCs identified as possible in the saltstone waste form were present at levels below the UTS. (3) Most

  9. Nuclear Waste Management. Semiannual progress report, October 1984-March 1985

    International Nuclear Information System (INIS)

    Progress reports are presented for the following studies on radioactive waste management: defense waste technology; nuclear waste materials characterization center; and supporting studies. 19 figs., 29 tabs

  10. Nuclear Waste Management. Semiannual progress report, October 1984-March 1985

    Energy Technology Data Exchange (ETDEWEB)

    McElroy, J.L.; Powell, J.A. (comps.)

    1985-06-01

    Progress reports are presented for the following studies on radioactive waste management: defense waste technology; nuclear waste materials characterization center; and supporting studies. 19 figs., 29 tabs.

  11. Nuclear waste management: shifting the paradigm

    International Nuclear Information System (INIS)

    In planning the management of nuclear waste, the U.S. has emphasized performance assessments and compliance with regulations, and has under-utilized processes for facilitating public understanding and public acceptance. A paradigm shift is needed. Motivation for this viewpoint comes from the author's five years of service on the Nuclear Waste Technical Review Board (NWTRB) and from his experience in assessing risks associated with the Department of Energy (DOE) nuclear weapons complex

  12. International Nuclear Waste Management Fact Book

    International Nuclear Information System (INIS)

    International Nuclear Waste Management Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R ampersand D programs, and key personnel in 24 countries, including the US, four multinational agencies and 21 nuclear societies. This publication succeeds the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 13 years. While the title is different, there are no substantial changes in the content

  13. Nuclear fuel waste policy in Canada

    International Nuclear Information System (INIS)

    The 1996 Policy Framework for Radioactive Waste established the approach in Canada for dealing with all radioactive waste, and defined the respective roles of Government and waste producers and owners. The Policy Framework sets the stage for the development of institutional and financial arrangements to implement long-term waste management solutions in a safe, environmentally sound, comprehensive, cost-effective and integrated manner. For nuclear fuel waste, a 10-year environmental review of the concept to bury nuclear fuel waste bundles at a depth of 500 m to 1000 m in stable rock of the Canadian Shield was completed in March 1998. The Review Panel found that while the concept was technically safe, it did not have the required level of public acceptability to be adopted at this time as Canada's approach for managing its nuclear fuel waste. The Panel recommended that a Waste Management Organization be established at arm's length from the nuclear industry, entirely funded by the waste producers and owners, and that it be subject to oversight by the Government. In its December 1998 Response to the Review Panel, the Government of Canada provided policy direction for the next steps towards developing Canada's approach for the long-term management of nuclear fuel waste. The Government chose to maintain the responsibility for long-term management of nuclear fuel waste close with the producers and owners of the waste. This is consistent with its 1996 Policy Framework for Radioactive Waste. This approach is also consistent with experience in many countries. In addition, the federal government identified the need for credible federal oversight. Cabinet directed the Minister of NRCan to consult with stakeholders, including the public, and return to ministers within 12 months with recommendations on means to implement federal oversight. (author)

  14. Nuclear power and nuclear waste: what good are they?

    International Nuclear Information System (INIS)

    This generation is an energy-using society, and all ways of producing electricity also produce waste. Most of the industrial world and some developing nations are committed to nuclear power and have not been deterred by Chernobyl. Nuclear power generation and planning in France, Belgium, Sweden, Switzerland, Finland, West Germany, Spain, Great Britain, and Japan are noted. Beneficial uses of nuclear science other than energy production are noted. Current and potential uses of nuclear materials now or at one time considered to be waste are discussed. Garbage is not always what it seems. Today's nuclear waste contains many of tomorrow's useful materials. Nuclear waste can be mined, but only if scientists have the will and the courage to look at it as a resource first, and dispose of it only when there is no more good in it

  15. Nuclear waste handbook. Elements for a debate on nuclear wastes in France

    International Nuclear Information System (INIS)

    This handbook contains a set of sheets discussing the different aspects associated with the nuclear waste issue: materials and risks (nuclear material and waste characterization and associated risks), choice and indicators (the French reprocessing-recycling option, valuable and ultimate wastes, long life waste management, long life waste indicators), flows and stocks (flows in the present management, stored, conditioned, waiting and valuable wastes). It also describes the regulatory environment (its principles and gaps) and researches. Then, it proposes a prospective view in terms of electricity production strategies, energy scenarios and technological strategies, nuclear materials with respect to the different scenarios. The decision process and economical and international aspects are finally discussed

  16. Science, Society, and America's Nuclear Waste: Nuclear Waste, Unit 1. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 1 of the four-part series Science, Society, and America's Nuclear Waste produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to help students establish the relevance of the topic of nuclear waste to their everyday lives and activities. Particular attention is…

  17. Plasma Mass Filters For Nuclear Waste Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Abraham J. Fetterman and Nathaniel J. Fisch

    2011-05-26

    Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

  18. Plasma Mass Filters For Nuclear Waste Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Abraham J. Fetterman and Nathaniel J. Fisch

    2011-05-25

    Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

  19. Plasma Mass Filters For Nuclear Waste Reprocessing

    International Nuclear Information System (INIS)

    Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

  20. Prospects of nuclear waste management and radioactive waste management

    International Nuclear Information System (INIS)

    The policy of radioactive waste management in the Slovak Republic is based on the principles defined by law on the National Nuclear Fund (NJF) and sets basic objectives: 1 Safe and reliable nuclear decommissioning; 2 The minimization of radioactive waste; 3. Selection of a suitable fuel cycle; 4 Safe storage of radioactive waste (RAW) 5 Security chain management of radioactive waste and spent nuclear fuel (SNF); 6 Nuclear safety; 7 The application of a graduated approach; 8 Respect of the principle 'a polluter pays'; 9 Objective decision-making process; 10 Responsibility. In connection with the above objectives, it appears necessary to build required facilities that are listed in this article.

  1. Nuclear waste: the Penn State connection

    International Nuclear Information System (INIS)

    Radioactive waste management research at The Pennsyvania State University is briefly discussed. The university's research effort began in 1973 with the purpose of developing a glass or crystalline material to immobilize radioactive waste isotopes. Since that time, Penn State's contributions toward solution of the nuclear waste disposal problem have included: new ceramic-metal, neutron-adsorbing panels for fuel storage, which will make storage of spent nuclear fuel more efficient; the crystal chemistry, synthesis, compatibility, and hot pressing of the ceramic waste forms based on radiophase and encapsulated immobilization, and the concept of liquid-phase mixing; a study of the stability of waste forms with regard to dissolution and radiation; a study of thousands of compositions of different waste forms and different rock types; and a study of the role of cement, clays, and zeolites in radioactive waste science and technology

  2. Nuclear waste management: A review of issues

    International Nuclear Information System (INIS)

    The subject of radioactive waste management and burial is a subject that raises strong emotional and political issues and generates sharp technical differences of opinion. The overall problem can be subdivided into the three major categories of (1) credibility and emotionalism, (2) technology, and (3) nuclear waste isolation and containment. An area of concern desperately in need of attention is that of proper public education on all aspects of the high-level radioactive-waste (rad-waste) burial problem. A major problem related to the rad-waste issue is the apparent lack of an official, all-encompassing U.S. policy for nuclear waste management, burial, isolation, and regulation. It is clear from all past technical reports that disposal of rad wastes in an appropriate geologic horizon is the best ultimate solution to the waste problem. After 25 y of dealing with the high-level radioactive waste problem, the difficulty is that no proposed plan has to date been tested properly. It is this indecision and reaction that has contributed in no small way to the public perception of inability to solve the problem. One major change that has occurred in the last few years was the enactment of the Nuclear Waste Policy Act of 1982. This act mandates deadlines, guidelines, and state involvement. It is time that strong differences of opinions be reconciled. One must get on with the difficult job of selecting the best means of isolating and burying these wastes before the task becomes impossible

  3. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1983 are described in this report

  4. Survey on non-nuclear radioactive waste

    International Nuclear Information System (INIS)

    On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden

  5. DEVELOPMENT OF AN IMPROVED SODIUM TITANATE FOR THE PRETREATMENT OF NUCLEAR WASTE AT THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D

    2008-01-22

    High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90 and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at SRS include sorption of Sr-90 and alpha-emitting radionuclides onto monosodium titanate (MST) and caustic side solvent extraction, for Cs-137 removal. The MST and separated Cs-137 will be encapsulated into a borosilicate glass waste form for eventual entombment at the federal repository. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239 and Pu-240. This paper describes recent results to produce an improved sodium titanate material that exhibits increased removal kinetics and capacity for Sr-90 and alpha-emitting radionuclides compared to the baseline MST material.

  6. Nuclear, energy, environment, wastes, society - NEEDS

    International Nuclear Information System (INIS)

    This document presents the seven projects based on partnerships between several bodies, companies and agencies (CNRS, CEA, Areva, EDF, IRSN, ANDRA, BRGM) on research programmes on nuclear systems and scenarios, on resources (mines, processes, economy), on the processing and packaging of radioactive wastes, on the behaviour of materials for storage, on the impact of nuclear activities on the environment, on the relationship between nuclear, risks and society, and on materials for nuclear energy

  7. Risk decisions and nuclear waste

    International Nuclear Information System (INIS)

    The risk concept is multidimensional, and much of its contents is lost in the conventional reduction to a unidimensional and quantifiable term. Eight major dimensions of the risk concept are discussed, among them the time factor and the lack-of-knowledge factor. The requirements of a rational discourse are discussed, in general and in relation to risk issues. It is concluded that no single method for the comparison and assessment of risks can be seen as the only rational method. Different methods can all be rational, although based on different values. Risk evaluations cannot be performed as expert assessments, divorced from the political decision process. Instead, risk evaluation must be seen as an essentially political process. Public participation is necessary in democratic decision-making on risks as well as on other issues. Important conclusions can be drawn for the management of nuclear waste, concerning specifications for the technical solution, the need for research on risk concepts, and the decision-making process. (orig.)

  8. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    This teachers guide is unit 3, the nuclear waste policy act, in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear power plants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  9. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    This is the 3rd unit, (The Nuclear Waste Policy Act) a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  10. Public policy issues in nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Nealey, S.M.; Radford, L.M.

    1978-10-01

    This document aims to raise issues and to analyze them, not resolve them. The issues were: temporal equity, geographic and socioeconomic equity, implementation of a nuclear waste management system, and public involvement.

  11. Public policy issues in nuclear waste management

    International Nuclear Information System (INIS)

    This document aims to raise issues and to analyze them, not resolve them. The issues were: temporal equity, geographic and socioeconomic equity, implementation of a nuclear waste management system, and public involvement

  12. Tergiversating the price of nuclear waste storage

    International Nuclear Information System (INIS)

    Tergiversation, the evasion of straightforward action of clearcut statement of position, was a characteristic of high-level nuclear waste disposal until the US Congress passed the Nuclear Waste Policy Act of 1982. How the price of waste storage is administered will affect the design requirements of monitored retrievable storage (MRS) facilities as well as repositories. Those decisions, in part, are internal to the Department of Energy. From the utility's viewpoint, the options are few but clearer. Reprocessing, as performed in Europe, is not a perfect substitute for MRS. The European reprocess-repository sequence will not yield the same nuclear resource base as the American MRS-repository scheme. For the future price of the energy resource represented by nuclear waste, the author notes that tergiversation continues. 3 references

  13. Administration eyes changes to nuclear waste fund

    International Nuclear Information System (INIS)

    The Clinton administration appears close to moving forward with a proposal to change the budget status of the nuclear waste fund so additional money can flow to the Energy Department's much-criticized Yucca Mountain project

  14. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

  15. 10 CFR 1.18 - Advisory Committee on Nuclear Waste.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Advisory Committee on Nuclear Waste. 1.18 Section 1.18... Panels, Boards, and Committees § 1.18 Advisory Committee on Nuclear Waste. The Advisory Committee on Nuclear Waste (ACNW) provides advice to the Commission on all aspects of nuclear waste management,...

  16. A federalist strategy for nuclear waste management.

    Science.gov (United States)

    Lee, K N

    1980-05-16

    The federal government plans to rely on a policy of "consultation and concurrence" with state governments in developing nuclear waste repositories. The weaknesses of the concurrence approach are analyzed, and an alternative institutional framework for locating a waste repository is proposed: a siting jury that provides representation for state and local interests, while maintaining a high level of technical review. The proposal could be tested in the siting of away-from-reactor storage facilities for spent nuclear fuel. PMID:17771087

  17. Nuclear waste: A problem of perspective

    International Nuclear Information System (INIS)

    In the light of the suspicion to be felt in the public towards the problem of nuclear waste management, the author in his article attempts to correct the impression created by somewhat sensational reports in the daily press by giving a more accurate description of nuclear waste management. He points out that responsible and fruitful research work has been done and should be made known to the public. (RB)

  18. US charts plans for nuclear waste disposal

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act (NWPA) passed in 1982 defines long-term federal programs to dispose of the leftovers from nuclear power generation. A succession of interacting multiple barriers, both natural and man-made, is to protect the public. Inside a mined underground repository will go waste packages. The geological formations surrounding the repository will be the final barrier. The article discussed site selections, salt sites, and subseabed disposal. (DP)

  19. Overview assessment of nuclear-waste management

    International Nuclear Information System (INIS)

    After reviewing the environmental control technologies associated with Department of Energy nuclear waste management programs, we have identified the most urgent problems requiring further action or follow-up. They are in order of decreasing importance: (1) shallow land disposal technology development; (2) active uranium mill tailings piles; (3) uranium mine dewatering; (4) site decommissioning; (5) exhumation/treatment of transuranic waste at Idaho National Engineering Laboratory; (6) uranium mine spoils; and (7) medical/institutional wastes. 7 figures, 33 tables

  20. Status of technology for nuclear waste management

    International Nuclear Information System (INIS)

    In the area of low- and intermediate-level radioactive wastes the successful development and application of specific management technologies have been demonstrated over the years. The major area in which technology remains to be effectively implemented is in the management of high-level wastes from the nuclear fuel cycle. Research and development specifically directed at the management of high-level radioactive wastes in the USA and other countries is briefly reviewed in the article introduced

  1. Overview assessment of nuclear-waste management

    Science.gov (United States)

    Burton, B. W.; Gutschick, V. P.; Perkins, B. A.; Reynolds, C. L.; Rodgers, J. C.; Steger, J. G.; Thompson, T. K.; Trocki, L. K.; Wewerka, E. M.; Wheeler, M. L.

    1982-08-01

    The environmental control technologies associated with Department of Energy nuclear waste management programs were reviewed and the most urgent problems requiring further action or follow up were identified. In order of decreasing importance they are: (1) shallow land disposal technology development; (2) active uranium mill tailings piles; (3) uranium mine dewatering; (4) site decommissioning; (5) exhumation/treatment of transuranic waste at Idaho National Engineering Laboratory; (6) uranium mine spoils; and (7) medical/institutional wastes.

  2. Management of radioactive waste nuclear power plants

    International Nuclear Information System (INIS)

    The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR)

  3. Nuclear waste management: storage and disposal aspects

    International Nuclear Information System (INIS)

    Long-term disposal of nuclear wastes must resolve difficulties arising chiefly from the potential for contamination of the environment and the risk of misuse. Alternatives available for storage and disposal of wastes are examined in this overview paper. Guidelines and criteria which may govern in the development of methods of disposal are discussed

  4. NUCLEAR POWER PLANT WASTE HEAT HORTICULTURE

    Science.gov (United States)

    The report gives results of a study of the feasibility of using low grade (70 degrees F) waste heat from the condenser cooling water of the Vermont Yaknee nuclear plant for commercial food enhancement. The study addressed the possible impact of laws on the use of waste heat from ...

  5. Nuclear Waste Primer: A Handbook for Citizens.

    Science.gov (United States)

    Weber, Isabelle P.; Wiltshire, Susan D.

    This publication was developed with the intention of offering the nonexpert a concise, balanced introduction to nuclear waste. It outlines the dimensions of the problem, discussing the types and quantities of waste. Included are the sources, types, and hazards of radiation, and some of the history, major legislation, and current status of both…

  6. Nuclear waste management in Canada

    International Nuclear Information System (INIS)

    The classification of radioactive wastes in Canada involves two categories - waste of such a nature or in such amounts that it could be hazardous to the public, and waste which can be dealt with safely by methods available to individual institutions having at their disposal only conventional methods for getting rid of unwanted material. It is easy to provide for long-term retention of radioactive wastes if no account need be taken of expense. However, it is unreasonable (and discouraging to progress) to insist upon techniques of waste management that are applicable to multi-curie sources when the amounts to be dealt with are in the millicurie range. (author)

  7. Natural analogues of nuclear waste glass corrosion

    International Nuclear Information System (INIS)

    This report reviews and summarizes studies performed to characterize the products and processes involved in the corrosion of natural glasses. Studies are also reviewed and evaluated on how well the corrosion of natural glasses in natural environments serves as an analogue for the corrosion of high-level radioactive waste glasses in an engineered geologic disposal system. A wide range of natural and experimental corrosion studies has been performed on three major groups of natural glasses: tektite, obsidian, and basalt. Studies of the corrosion of natural glass attempt to characterize both the nature of alteration products and the reaction kinetics. Information available on natural glass was then compared to corresponding information on the corrosion of nuclear waste glasses, specifically to resolve two key questions: (1) whether one or more natural glasses behave similarly to nuclear waste glasses in laboratory tests, and (2) how these similarities can be used to support projections of the long-term corrosion of nuclear waste glasses. The corrosion behavior of basaltic glasses was most similar to that of nuclear waste glasses, but the corrosion of tektite and obsidian glasses involves certain processes that also occur during the corrosion of nuclear waste glasses. The reactions and processes that control basalt glass dissolution are similar to those that are important in nuclear waste glass dissolution. The key reaction of the overall corrosion mechanism is network hydrolysis, which eventually breaks down the glass network structure that remains after the initial ion-exchange and diffusion processes. This review also highlights some unresolved issues related to the application of an analogue approach to predicting long-term behavior of nuclear waste glass corrosion, such as discrepancies between experimental and field-based estimates of kinetic parameters for basaltic glasses

  8. Natural analogues of nuclear waste glass corrosion.

    Energy Technology Data Exchange (ETDEWEB)

    Abrajano, T.A. Jr.; Ebert, W.L.; Luo, J.S.

    1999-01-06

    This report reviews and summarizes studies performed to characterize the products and processes involved in the corrosion of natural glasses. Studies are also reviewed and evaluated on how well the corrosion of natural glasses in natural environments serves as an analogue for the corrosion of high-level radioactive waste glasses in an engineered geologic disposal system. A wide range of natural and experimental corrosion studies has been performed on three major groups of natural glasses: tektite, obsidian, and basalt. Studies of the corrosion of natural glass attempt to characterize both the nature of alteration products and the reaction kinetics. Information available on natural glass was then compared to corresponding information on the corrosion of nuclear waste glasses, specifically to resolve two key questions: (1) whether one or more natural glasses behave similarly to nuclear waste glasses in laboratory tests, and (2) how these similarities can be used to support projections of the long-term corrosion of nuclear waste glasses. The corrosion behavior of basaltic glasses was most similar to that of nuclear waste glasses, but the corrosion of tektite and obsidian glasses involves certain processes that also occur during the corrosion of nuclear waste glasses. The reactions and processes that control basalt glass dissolution are similar to those that are important in nuclear waste glass dissolution. The key reaction of the overall corrosion mechanism is network hydrolysis, which eventually breaks down the glass network structure that remains after the initial ion-exchange and diffusion processes. This review also highlights some unresolved issues related to the application of an analogue approach to predicting long-term behavior of nuclear waste glass corrosion, such as discrepancies between experimental and field-based estimates of kinetic parameters for basaltic glasses.

  9. Social dimensions of nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Grunwald, Armin [Karlsruhe Institute of Technology, Karlsruhe (Germany). Inst. for Technology Assessment and Systems Analysis

    2015-07-01

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  10. Social dimensions of nuclear waste disposal

    International Nuclear Information System (INIS)

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  11. World Nuclear Association position statement: Safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    This WNA Position Statement summarises the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the WNA will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The paper's conclusion is that the safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations. Accumulating

  12. Nuclear waste incineration technology status

    International Nuclear Information System (INIS)

    The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance

  13. Nuclear waste incineration technology status

    Energy Technology Data Exchange (ETDEWEB)

    Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

    1981-07-15

    The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

  14. Nuclear waste package fabricated from concrete

    International Nuclear Information System (INIS)

    After the United States enacted the Nuclear Waste Policy Act in 1983, the Department of Energy must design, site, build and operate permanent geologic repositories for high-level nuclear waste. The Department of Energy has recently selected three sites, one being the Hanford Site in the state of Washington. At this particular site, the repository will be located in basalt at a depth of approximately 3000 feet deep. The main concern of this site, is contamination of the groundwater by release of radionuclides from the waste package. The waste package basically has three components: the containment barrier (metal or concrete container, in this study concrete will be considered), the waste form, and other materials (such as packing material, emplacement hole liners, etc.). The containment barriers are the primary waste container structural materials and are intended to provide containment of the nuclear waste up to a thousand years after emplacement. After the containment barriers are breached by groundwater, the packing material (expanding sodium bentonite clay) is expected to provide the primary control of release of radionuclide into the immediate repository environment. The loading conditions on the concrete container (from emplacement to approximately 1000 years), will be twofold; (1) internal heat of the high-level waste which could be up to 4000C; (2) external hydrostatic pressure up to 1300 psi after the seepage of groundwater has occurred in the emplacement tunnel. A suggested container is a hollow plain concrete cylinder with both ends capped. 7 refs

  15. Nuclear data for radioactive waste management

    International Nuclear Information System (INIS)

    Highlights: • The role nuclear data plays in determining the source term of radiation from spent fuel and radioactive waste is described. • Isotopes most contributing to this source for different fuel cycles are identified. • Current international activities aiming at improving the existing data bases are addressed. - Abstract: The role nuclear data plays in determining the source term of radiation emitted by spent fuel and radioactive waste arising from nuclear activities is described. The isotopes most contributing to this source for different fuel cycles are identified. Current international activities aiming at improving the existing data bases, in particular as concerns data uncertainties are addressed

  16. Nuclear waste reform among first energy bills

    International Nuclear Information System (INIS)

    Over 300 bills were introduced in the first week of the new Congress that convened in January, among them a bill aimed at correcting the government's seriously flawed nuclear waste storage program. The bill would required the Department of Energy (DOE) to provide an interim storage site for high-level radioactive waste and spent nuclear fuel at Yucca Mountain, Nevada no later than January 31, 1998. DOE says it will no be able to complete a permanent repository until 2010, and is not obligated to take possession on nuclear waste until a permanent repository is completed. The ever worsening problem prompted 14 utilities and 20 states to file separate lawsuits against the DOE to force the agency into accepting spent fuel. Utilities and ultimately consumers have paid over $8 billion into the Nuclear Waste Fund that is supposed to be used for a permanent repository, but the money has not been put to use yet. Spokesmen for the Nuclear Energy Institute and electric utilities feel that the bill is a step in the right direction and will begin the much needed reforms in the nuclear waste program. Other energy related bills in the 104th Congress are also discussed including the phasing out of funding for the Tennessee Valley Authority

  17. Wastes: the nightmare of nuclear industry

    International Nuclear Information System (INIS)

    This polemical book proposes a worrying trip to the different nuclear dumps of the World, from Hanford, cradle of the first atomic bomb, to the French fuel facility of La Hague and to the open-air dumps of Siberia. When reading this book, the reader discovers with amazement that the nuclear industry has always confiscated to citizens the right to debate about nuclear policies and to reject the nuclear wastes. While each time the civil society was asked for its opinion, the nuclear industry was rejected. Therefore, the author questions its compatibility with democracy. (J.S.)

  18. Scientific Basis for Nuclear Waste Management

    Science.gov (United States)

    Trask, Newell J.

    As a result of the Reagan administration's commitment to nuclear energy as a significant future energy source and of attempts by the 97th Congress to grapple with legislative aspects of the problem, increased attention has focused recently on the problem of safely disposing of nuclear waste. These proceedings of the Third Symposium on Nuclear Waste Management of the Materials Research Society provide insight into the status of investigations on the subject as of late 1980. As with volumes 1 and 2 of this series, the 77 contributions are all short progress reports of ongoing research with the emphasis fittingly on materials science. Readers who wish extensive background material on the problems of nuclear-waste management and disposal, details of specific sites, or overviews of the programs of research in this country and abroad will have to look elsewhere.

  19. Nuclear waste management at DOE

    International Nuclear Information System (INIS)

    DOE is responsible for interim storage for some radioactive wastes and for the disposal for most of them. Of the wastes that have to be managed a significant part are a result of treatment systems and devices for cleaning gases. The long term waste management objectives place minimal reliance on surveillance and maintenance. Thus, the concerns about the chemical, thermal, and radiolytic degradation of wastes require technology for converting the wastes to forms acceptable for long term isolation. The strategy of the DOE airborne radioactive waste management program is to increase the service life and reliability of filters; to reduce filter wastes; and in anticipation of regulatory actions that would require further reductions in airborne radioactive releases from defense program facilities, to develop improved technology for additional collection, fixation, and long-term management of gaseous wastes. Available technology and practices are adequate to meet current health and safety standards. The program is aimed primarily at cost effective improvements, quality assurance, and the addition of new capability in areas where more restrictive standards seem likely to apply in the future

  20. Influences of microbiology on nuclear waste disposal

    International Nuclear Information System (INIS)

    This study was carried out to determine the effects of microbial activity on the disposal of nuclear waste. The areas chosen for study include nutrient availability (both organic and inorganic), the effect of increased pH and potential gas generation from the waste. Microbes from various soil habitats could grow on a variety of cellulose-based substrates including simulant waste. Increased pH did not appear to greatly effect the growth of these microbes. Gas generation by microbes growing on a simulant waste was determined over an extended period under a variety of nutritional conditions. The simulant waste was a good substrate for microbes and adding inorganic nutrients did not significantly affect the final yield of gas; extrapolated to about 14.63 gas per tonne of waste. The experiments have highlighted a number of areas for further research and they are currently being addressed. (author)

  1. Extreme scenarios for nuclear waste repositories

    International Nuclear Information System (INIS)

    Two extreme scenarios for release of radioactive waste have been constructed. In the first, a volcanic eruption releases 1 km2 of an underground nuclear waste repository, while in the second, waste enters the drinking water reservoir of a major city. With pessimistic assumptions, upper bounds on the number of cancers due to radiation are calculated. In the volcano scenario, the effects of the waste are smaller than the effects of natural radioactivity in the volcanic dust if the delay between emplacement and eruption exceeds 2000 yr. The consequences of the waste in drinking water depend on the survival time of the canisters and the rate of leaching of the nuclides from the waste matrix. For a canister life of 400 yr and a leach time of 6300 yr the cancer rate in the affected area would increase by 25%. (author)

  2. DEVELOPMENT OF AN IMPROVED SODIUM TITANATE FOR THE PRETREATMENT OF HIGH LEVEL NUCLEAR WASTE AT THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D

    2007-11-15

    High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90 and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at SRS include sorption of Sr-90 and alpha-emitting radionuclides onto monosodium titanate (MST) and caustic side solvent extraction, for {sup 137}Cs removal. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239 and Pu-240. This paper describes recent results to produce an improved sodium titanate material that exhibits increased removal kinetics and capacity for Sr-90 and alpha-emitting radionuclides compared to the baseline MST material.

  3. DEVELOPMENT OF AN IMPROVED SODIUM TITANATE FOR THE PRETREATMENT OF HIGH LEVEL NUCLEAR WASTE AT THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs D. T.; Poirier, M. R.; Barnes, M. J.; Stallings, M. E.; Nyman, M. D.

    2005-11-22

    High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 137}Cs, {sup 90}Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at SRS include caustic side solvent extraction, for {sup 137}Cs removal, and sorption of {sup 90}Sr and alpha-emitting radionuclides onto monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes {sup 238}Pu, {sup 239}Pu and {sup 240}Pu. This paper describes recent results to produce an improved sodium titanate material that exhibits increased removal kinetics and capacity for {sup 90}Sr and alpha-emitting radionuclides compared to the baseline MST material.

  4. Scientific basis for nuclear waste management XVII

    International Nuclear Information System (INIS)

    The 17th Materials Research Society Symposium on the Scientific Basis for Nuclear Waste Management included 17 sessions, during which 120 papers were presented by scientists from 16 countries. The nuclear waste glass overview surveyed achievements to date and identified issues requiring further research. The objectives and limitations session noted the progress that has been made in developing a scientific basis for nuclear waste management, but questioned whether regulations calling for detailed predictions over a period of 10,000 years are either necessary or capable of being satisfied. The other papers presented at the Symposium described the progress of studies in a broad array of areas of nuclear waste science and technology. These areas included radiation effects and gas generation, ceramic materials, cementitious materials, actinides spent fuel, glass processing and properties, glass leaching, dissolution and alteration, natural and ancient analogues, transuranic wastes and special topics, sorption mechanisms, repository studies, geochemistry and hydrology, containers, and backfill materials. Several novel experimental techniques were described, as well as advances in modeling. An encouraging feature of the progress in modeling is that the agreement between calculated results based on models developed, refined and tested in the US and in other countries on one hand, and experimental data on the other, shows considerable improvement. This reflects greater understanding of the mechanisms involved in the release of radionuclides from the various components of the waste repository system, including the wasteforms themselves. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  5. Preconceptual Design Description for Caustic Recycle Facility

    Energy Technology Data Exchange (ETDEWEB)

    Sevigny, Gary J.; Poloski, Adam P.; Fountain, Matthew S.; Kurath, Dean E.

    2008-04-12

    The U.S. Department of Energy plans to vitrify both high-level and low-activity waste at the Hanford Site in southeastern Washington State. One aspect of the planning includes a need for a caustic recycle process to separate sodium hydroxide for recycle. Sodium is already a major limitation to the waste-oxide loading in the low-activity waste glass to be vitrified at the Waste Treatment Plant, and additional sodium hydroxide will be added to remove aluminum and to control precipitation in the process equipment. Aluminum is being removed from the high level sludge to reduce the number of high level waste canisters produced. A sodium recycle process would reduce the volume of low-activity waste glass produced and minimize the need to purchase new sodium hydroxide, so there is a renewed interest in investigating sodium recycle. This document describes an electrochemical facility for recycling sodium for the WTP.

  6. Mechanical properties of nuclear waste glasses

    International Nuclear Information System (INIS)

    The mechanical properties of nuclear waste glasses are important as they will determine the degree of cracking that may occur either on cooling or following a handling accident. Recent interest in the vitrification of intermediate level radioactive waste (ILW) as well as high level radioactive waste (HLW) has led to the development of new waste glass compositions that have not previously been characterised. Therefore the mechanical properties, including Young's modulus, Poisson's ratio, hardness, indentation fracture toughness and brittleness of a series of glasses designed to safely incorporate wet ILW have been investigated. The results are presented and compared with the equivalent properties of an inactive simulant of the current UK HLW glass and other nuclear waste glasses from the literature. The higher density glasses tend to have slightly lower hardness and indentation fracture toughness values and slightly higher brittleness values, however, it is shown that the variations in mechanical properties between these different glasses are limited, are well within the range of published values for nuclear waste glasses, and that the surveyed data for all radioactive waste glasses fall within relatively narrow range.

  7. Changing the paradigm of disposing nuclear wastes

    International Nuclear Information System (INIS)

    The Fukushima accident occurred in Japan in March 2011 could potentially change the courses of future nuclear energy development in many countries, including Japan. While this game-changing event re-focused the issues on nuclear safety, it also exposed the problem of 'What to do with the growing stocks of used fuel? ' especially toward their final disposal in geologic media. This problem is obviously not confined to Fukushima but is common to all nuclear power programs in the world. The answer to the challenge may lie in the possibility of changing the paradigm in managing the nuclear technologies and wastes in the back-end of the nuclear fuel cycle, including the final disposal of long-lived and problematic radioactive wastes in deep geologic media. (author)

  8. Nuclear waste isolation activities report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    Included are: a report from the Deputy Assistant Secretary, a summary of recent events, new literature, a list of upcoming waste management meetings, and background information on DOE`s radwaste management programs. (DLC)

  9. Nuclear waste isolation activities report

    International Nuclear Information System (INIS)

    Included are: a report from the Deputy Assistant Secretary, a summary of recent events, new literature, a list of upcoming waste management meetings, and background information on DOE's radwaste management programs

  10. Management of radioactive waste from nuclear applications

    International Nuclear Information System (INIS)

    Radioactive waste arises from the generation of nuclear energy and from the production of radioactive materials and their applications in industry, agriculture, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. Technical expertise is a prerequisite for safe and cost-effective management of radioactive waste. A training course is considered an effective tool for providing technical expertise in various aspects of waste management. The IAEA, in co-operation with national authorities concerned with radioactive waste management, has organized and conducted a number of radioactive waste management training courses. The results of the courses conducted by the IAEA in 1991-1995 have been evaluated at consultants meetings held in December 1995 and May 1996. This guidance document for use by Member States in arranging national training courses on the management of low and intermediate level radioactive waste from nuclear applications has been prepared as the result of that effort. The report outlines the various requirements for the organization, conduct and evaluation of training courses in radioactive waste management and proposes an annotated outline of a reference training course

  11. Analysis of nuclear waste management

    International Nuclear Information System (INIS)

    An event tree is developed, outlining ways which radioactivity can be accidentally released from high level solidified wastes. Probabilities are assigned to appropriate events in the tree and the major contributors to dose to the general population are identified. All doses are computed on a per megawatt electric-year basis. Sensitivity relations between the expected dose and key characteristics of the solidified wasted are developed

  12. Science, Society, and America's Nuclear Waste: The Nuclear Waste Policy Act, Unit 3. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 3 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to identify the key elements of the United States' nuclear waste dilemma and introduce the Nuclear Waste Policy Act and the role of the…

  13. DOE states reheat nuclear waste debate

    International Nuclear Information System (INIS)

    After decades of struggling with the issue, Congress in late 1982 established a firm plan for burying growing volumes of nuclear reactor wastes. But 2 l/2 years later the waste disposal debate is as hot as ever. Utility companies, environmentalists, federal officials, and state governments are again clashing - this time over the way the program is proceeding. The Nuclear Waste Policy Act calls for the Department of Energy to start accepting wastes in 1998 at the first of two planned repositories. Selection of this first repository site was mandated for early 1987, but program delays at DOE have pushed the decision back to March 1991. Despite this postponement and other schedule slips, the Department still aims to meet Congress's 1998 deadline. But states, Indian tribes, and environmentalists fear the site selection process will be compromised and want the start up date rolled back

  14. Trilingual vocabulary of nuclear waste management

    International Nuclear Information System (INIS)

    This reference document is produced in cooperation with partners in the Union Latine, an international organization dedicated to promoting the Romance languages. In 1992 acting on a request submitted by the Montreal Environment Section of the Translation Bureau, the Terminology and Standardization Directorate published an in-house glossary containing 2500 entries on nuclear waste management. The glossary was produced by scanning bilingual terms in the reports submitted to Atomic Energy of Canada Limited by the Siting Process Task Force on Low-Level Radioactive Waste Disposal. Because the scale of the nuclear waste management problem has grown considerably since then, the glossary needed to be expanded and revised. The Vocabulary contains some 1000 concepts for a total of approximately 3000 terms in each of the three languages, english, french and spanish. Special attention has been given to defining basic physical concepts, waste classifications and disposal methods

  15. Project safety studies - nuclear waste management (PSE)

    International Nuclear Information System (INIS)

    The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW)

  16. The local community and the nuclear waste

    International Nuclear Information System (INIS)

    In this book social and political scientists discuss different aspects of the selection of a site for disposal of the Swedish nuclear waste. Special attention is given to the preliminary studies that have been performed at a few localities. The authors study the chain of events after a community is proposed for a site study. What powers are set in motion? How do different groups act in order to support or stop the study? Which is the role played by political parties, local environmentalist movements, media and experts? Why is there a forceful opposition in one community and not in another? Why does one local government invite the nuclear waste company to perform the study, while another refuses? The role of the local government has become crucial, since the nuclear waste company have chosen to perform studies only in municipalities that show a positive interest

  17. Conceptual Design of a Simplified Skid-Mounted Caustic-Side Solvent Extraction Process for Removal of Cesium from Savannah Rive Site High-Level Waste

    International Nuclear Information System (INIS)

    This report presents the results of a conceptual design of a solvent extraction process for the selective removal of 137Cs from high-level radioactive waste currently stored in underground tanks at the U.S. Department of Energy's Savannah River Site (SRS). This study establishes the need for and feasibility of deploying a simplified version of the Caustic-Side Solvent Extraction (CSSX) process; cost/benefit ratios ranging from 33 to 55 strongly support the considered deployment. Based on projected compositions, 18 million gallons of dissolved salt cake waste has been identified as having 137Cs concentrations that are substantially lower than the worst-case design basis for the CSSX system that is to be deployed as part of the Salt Waste Processing Facility (SWPF) but that does not meet the waste acceptance criteria for immobilization as grout in the Saltstone Manufacturing and Disposal Facility at SRS. Absent deployment of an alternative cesium removal process, this material will require treatment in the SWPF CSSX system, even though the cesium decontamination factor required is far less than that provided by that system. A conceptual design of a CSSX processing system designed for rapid deployment and having reduced cesium decontamination factor capability has been performed. The proposed accelerated-deployment CSSX system (CSSX-A) has been designed to have a processing rate of 3 million gallons per year, assuming 90% availability. At a more conservative availability of 75% (reflecting the novelty of the process), the annual processing capacity is 2.5 million gallons. The primary component of the process is a 20-stage cascade of centrifugal solvent extraction contactors. The decontamination and concentration factors are 40 and 15, respectively. The solvent, scrub, strip, and wash solutions are to have the same compositions as those planned for the SWPF CSSX system. As in the SWPF CSSX system, the solvent and scrub flow rates are equal. The system is designed to

  18. Conceptual Design of a Simplified Skid-Mounted Caustic-Side Solvent Extraction Process for Removal of Cesium from Savannah Rive Site High-Level Waste

    Energy Technology Data Exchange (ETDEWEB)

    Birdwell, JR.J.F.

    2004-05-12

    This report presents the results of a conceptual design of a solvent extraction process for the selective removal of {sup 137}Cs from high-level radioactive waste currently stored in underground tanks at the U.S. Department of Energy's Savannah River Site (SRS). This study establishes the need for and feasibility of deploying a simplified version of the Caustic-Side Solvent Extraction (CSSX) process; cost/benefit ratios ranging from 33 to 55 strongly support the considered deployment. Based on projected compositions, 18 million gallons of dissolved salt cake waste has been identified as having {sup 137}Cs concentrations that are substantially lower than the worst-case design basis for the CSSX system that is to be deployed as part of the Salt Waste Processing Facility (SWPF) but that does not meet the waste acceptance criteria for immobilization as grout in the Saltstone Manufacturing and Disposal Facility at SRS. Absent deployment of an alternative cesium removal process, this material will require treatment in the SWPF CSSX system, even though the cesium decontamination factor required is far less than that provided by that system. A conceptual design of a CSSX processing system designed for rapid deployment and having reduced cesium decontamination factor capability has been performed. The proposed accelerated-deployment CSSX system (CSSX-A) has been designed to have a processing rate of 3 million gallons per year, assuming 90% availability. At a more conservative availability of 75% (reflecting the novelty of the process), the annual processing capacity is 2.5 million gallons. The primary component of the process is a 20-stage cascade of centrifugal solvent extraction contactors. The decontamination and concentration factors are 40 and 15, respectively. The solvent, scrub, strip, and wash solutions are to have the same compositions as those planned for the SWPF CSSX system. As in the SWPF CSSX system, the solvent and scrub flow rates are equal. The system

  19. Characterising highly active nuclear waste simulants

    OpenAIRE

    Paul, N; Biggs, S.; Edmondson, M; Hunter, TN; Hammond, RB

    2013-01-01

    Reprocessing of spent nuclear fuel produces a highly active liquor (HAL) waste stream, which is typically stored over extended periods of many years in waste tanks equipped with extensive heat exchange capability. Over time, particulates are known to precipitate from the HAL within these tanks. Particle simulants provide a route for understanding the physical behaviour of these HAL solids under different agitation and transfer conditions. Particle and dispersion characterisation techniques ar...

  20. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    This report, the fifth of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes activities over the past year in the following areas: public interaction; used fuel storage and transportation; immobilization of used fuel and fuel recycle waste; geoscience research related to deep underground disposal; environmental research; and environmental and safety assessment

  1. Promethean ethics and nuclear waste management

    International Nuclear Information System (INIS)

    The proposed safety standards for commercial nuclear waste management are examined and shown to be Promethean; that is, they are shown to be dominated by time and care for future generations. Some of the long-term environmental impact assessment methodologies being developed in commmercial waste management are examined. They are aimed at demonstrating repository isolation integrity over a 10,000-year period or 300 human generations, a truly Promethean period of examination unknown in other 20th Century technical analyses

  2. Southeastern Utah nuclear-waste-transportation study

    International Nuclear Information System (INIS)

    This report is published as a product of the National Waste Terminal Storage (NWTS) Program. The objective of this program is the development of terminal waste storage facilities in deep stable geologic formations for high-level nuclear waste, including spent fuel elements from commercial power reactors and transuranic nuclear waste for which the Federal Government is responsible. The initial purpose of this study was to analyze and compare possible transport modes and corridors connecting each of four candidate sites in Utah with existing rail lines of the Denver and Rio Grande Western Railroad (D and RG) or the Atchison, Topeka, and Santa Fe Railway (ATSF). The primary use of these routes would be for shipping spent nuclear fuel and other nuclear wastes. During the study, the Gibson Dome area was recommended as the preferred location by the screening process evaluating the four Utah areas. Therefore, this report presents transportation routes to Gibson Dome examining order-of-magnitude capital costs of railroad and heavy haul routes, railroad and heavy haul truck operating costs and environmental factors. The scope of work did not include consideration of using public highways. Information on the other candidate sites and possible routes to them is also presented. 15 figures, 10 tables

  3. Environment. How to store nuclear wastes?

    International Nuclear Information System (INIS)

    As a trial is about to take place between the ANDRA (the French National Agency for the Management of Nuclear Wastes) and associations opposed to the Cigeo project of geological deposit of nuclear wastes in Bures, this article briefly recalls the objectives of Cigeo in terms of volumes of storage of high and intermediate activity-long life wastes, and the failure of the public debate process in 2013. It briefly discusses the assessment of the geothermal potential of the area which has been the motivation of the associations to obtain this trial. While providing a sketch of the Cigeo project, and briefly recalling that geological deposit is a rather spread technique in the world, the article briefly recalls the main steps of this industrial project, and outlines that its cost and financing are still a matter of discussion, notably because some costs cannot be precisely known for a site which is planned to be exploited during 125 years. It outlines that Cigeo still lacks a legal framework (it has been removed from the law on energy transition, and from a more recent bill project), and that there is for now no alternative for nuclear waste storage. The issue of wastes produced by the dismantling of nuclear installations is briefly evoked

  4. The international politics of nuclear waste

    International Nuclear Information System (INIS)

    This book depicts the wide diversity and the striking similarities in the international politics of nuclear waste management, using good organization and well defined terminology. The authors provide a background of geography, geology and demographics, and provide informed and common-sensical observations and conclusions. They question the ethics of leaving nuclear wastes where they are and waiting for better solutions, and they put forward a rational set of siting options, including coupling repository plans with environmental enhancement programs such as protection of coastal access, landscape improvements, and erosion control

  5. Citizen participation in nuclear waste repository siting

    International Nuclear Information System (INIS)

    The following study presents a proposed strategy for citizen participation during the planning stages of nuclear waste repository siting. It discusses the issue from the general perspective of citizen participation in controversial issues and in community development. Second, rural institutions and attitudes toward energy development as the context for developing a citizen participation program are examined. Third, major citizen participation techniques and the advantages and disadvantages of each approach for resolving public policy issues are evaluated. Fourth, principles of successful citizen participation are presented. Finally, a proposal for stimulating and sustaining effective responsible citizen participation in nuclear waste repository siting and management is developed

  6. Citizen participation in nuclear waste repository siting

    Energy Technology Data Exchange (ETDEWEB)

    Howell, R.E.; Olsen, D.

    1982-12-01

    The following study presents a proposed strategy for citizen participation during the planning stages of nuclear waste repository siting. It discusses the issue from the general perspective of citizen participation in controversial issues and in community development. Second, rural institutions and attitudes toward energy development as the context for developing a citizen participation program are examined. Third, major citizen participation techniques and the advantages and disadvantages of each approach for resolving public policy issues are evaluated. Fourth, principles of successful citizen participation are presented. Finally, a proposal for stimulating and sustaining effective responsible citizen participation in nuclear waste repository siting and management is developed.

  7. Grouting of nuclear waste vault shafts

    International Nuclear Information System (INIS)

    A nuclear waste vault must be designed and built to ensure adequate isolation of the nuclear wastes from human contact. Consequently, after a vault has been fully loaded it must be adequately sealed off to prevent radionuclide migration which may be provided by circulating ground water. Of particular concern in vault sealing are the physical and chemical properties of the sealing materials its long-term durability and stability and the techniques used for its emplacement. Present grouting technology and grout material are reviewed in terms of the particular needs of shaft grouting. Areas requiring research and development are indicated

  8. Nuclear fuel waste disposal in Canada

    International Nuclear Information System (INIS)

    Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under the Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

  9. NRC nuclear waste geochemistry 1983

    International Nuclear Information System (INIS)

    The purpose of the meeting was to present results from NRC-sponsored research and to identify regulatory research issues which need to be addressed prior to licensing a high-level waste repository. Important summaries of technical issues and recommendations are included with each paper. The issue reflect areas of technical uncertainty addressed by the NRC Research program in geochemistry. The objectives of the NRC Research Program in geochemistry are to provide a technical basis for waste management rulemaking, to provide the NRC Waste Management Licensing Office with information that can be used to support sound licensing decisions, and to identify investigations that need to be conducted by DOE to support a license application. Individual papers were processed for inclusion in the Energy Data Base

  10. Legal problems in international nuclear waste transport

    International Nuclear Information System (INIS)

    The question of international transboundary movements of radioactive wastes have been discussed within several organizations, leading to the adoption of different texts from among which we can mention the LOME IV Convention, the International Atomic Energy Agency (IAEA) Code of Practice for International Transactions involving Radioactive Wastes and the draft of the European Directive about transboundary transfers of radioactive wastes. Each of these texts has a different source and emphasis, and much duplication occurs, leading to unnecessarily complex regulations on the nuclear industry. (author)

  11. Nuclear waste management program. Summary document

    International Nuclear Information System (INIS)

    This document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (ETW) under the Assistant Secretary for Energy Technology, DOE. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to ETW programs is summarized, including field and regional activities, commercialization plans, the environmental and socioeconomic implications of waste management activities, and international programs

  12. Next nuclear gamble: transportation and storage of nuclear waste

    International Nuclear Information System (INIS)

    Accidents during transport of nuclear waste are more threatening - though less likely - than a reactor meltdown because transportation accidents could occur in the middle of a populous city, affecting more people and property than a plant accident, according to the Council on Economic Priorities, a non-profit public service research organization. Transportation, as presently practiced, is unsafe. Shipping containers, called casks, are poorly designed and constructed, CEP says. The problem needs attention because the number of casks filled with nuclear waste on the nation's highways could increase a hundred times during the next 15 years under the Nuclear Waste Policy Act of 1982, which calls for storage areas. Recommendations, both technical and regulatory, for reducing the risks are presented

  13. Nuclear wastes: disposal, storage or reprocessing?

    International Nuclear Information System (INIS)

    In the domains of medium-, low- and very low-level radioactive wastes, existing techniques are already implemented and belong to a well-mastered know-how. For high level wastes, according to the December 30, 1991 law, researches are carried out in three ways: separation-transmutation of long living radioactive elements, reversible or irreversible disposal inside deep geologic formations, and long lasting conditioning and surface storage. Each of these ways is useful, not contradictory but complementary to each other. This meeting has contributed to fulfill the approach requested by the French Parliament who considers that information spreading and transparency are key elements of the radioactive waste management debate, like technicality is. This small book is the proceedings of the 2 parliamentary meeting on nuclear energy which were specifically devoted to the problem of radioactive wastes management in the framework of the 1991 law. The meeting was organized around three round-tables dealing with: 1 - the management of low and medium-level radioactive wastes: a problem on the way of disappearing? 2 - What reprocessing mean for nuclear wastes? 3 - Disposal and storage of high-level radioactive wastes and spent fuels: where and for how long? The opinions expressed by the participants during the round-tables are compiled in this document. (J.S.)

  14. Chemical aspects of nuclear waste treatment

    International Nuclear Information System (INIS)

    The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized

  15. Time Motion Study for Modular Caustic Solvent Extraction Unit

    International Nuclear Information System (INIS)

    The Defense Waste Processing Facilities (DWPF) at the Savannah River Site (SRS) is used to process high-level radioactive waste from the Tank Farm into borosilicate glass to reduce the mobility of the radionuclides and has processed and vitrified nuclear wastes into canisters for long-term disposal since FY96. All wastes vitrified to date in DWPF are ''sludge only'' wastes. The old salt waste processing technology, ITP, was suspended in FY98 due to benzene build-up inside the tank. The new selected technologies for treating the salt waste are Actinide Removal Process (ARP) and Caustic Side Solvent Extraction process (CSSX). The Modular CSSX Unit (MCU) is a cesium removal process that will be operated downstream of the ARP. The MCU is a short-term method for cesium removal, which uses the same technology as the Salt Waste Processing Facility (SWPF). Once the SWPF becomes operational, the MCU will be shut down. The modeling request is from the MCU project to verify the validity of its Concept Design Package. The modeling task is not typical because there are five different facilities/projects/processes involved, i.e., Tank Farm, ARP, MCU, Saltstone, and DWPF. Each facility, project, and process has their own management team and organization, with its own fiscal responsibility and performance accountability. In addition, from a task cost perspective, MCU desires to minimize modeling not directly associated with their facility. The balancing of comprehensive analysis with limited granularity is challenging. The customer expectation is the model should be small and delivered within weeks. Modeling a stand-alone MCU will not yield overall meaningful results because it can be expected that most problems will occur at interfaces with other facilities. This paper discusses how we set out our modeling strategy, overcame obstacles, avoided touchy issues, and delivered the modeling result on time and on budget

  16. Global nuclear waste repository proposal highlights Australia's nuclear energy vacuum

    International Nuclear Information System (INIS)

    The Pangea proposal is disscused and considered relevant to Australia. A five-year research program by the company has identified Australia and Argentina as having the appropriate geological, economic and democratic credentials for such a deep repository, with Australia being favoured. A deep repository would be located where the geology has been stable for several hundred million years, so that there need not be total reliance on a robust engineered barrier system to keep the waste securely isolated for thousands of years. It would be a commercial undertaking and would have dedicated port and rail infrastructure. It would take spent fuel and other wastes from commercial reactors, and possibly also waste from weapons disposal programs. Clearly, while the primary ethical and legal principle is that each country is entirely responsible for its own waste, including nuclear waste (polluter pays etc), the big question is whether the concept of an international waste repository is acceptable ethically. Political and economic questions are secondary to this. By taking a fresh look at the reasons for the difficulties which have faced most national repository programs, and discarding the preconception that each country must develop its own disposal facilities, it is possible to define a class of simple, superior high isolation sites which may provide a multi-national basis for solving the nuclear waste disposal problem. The relatively small volumes of high-level wastes or spent fuel which arise from nuclear power production make shared repositories a feasible proposition. For small countries, the economies of scale which can be achieved make the concept attractive. For all countries, objective consideration of the relative merits of national and multi-national solutions is a prudent part of planning the management of long-lived radioactive wastes

  17. The Next Nuclear Gamble. Transportation and storage of nuclear waste

    International Nuclear Information System (INIS)

    The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

  18. Salvaging of nuclear waste by nuclear-optical converters

    Science.gov (United States)

    Karelin, A. V.; Shirokov, R. V.

    2007-06-01

    In modern conditions of power consumption growing in Russia, apparently, it is difficult to find alternative to further development of nuclear power engineering. The negative party of nuclear power engineering is the spent fuel of nuclear reactors (radioactive waste). The gaseous and fluid radioactive waste furbished of highly active impurity, dumps in atmosphere or pools. The highly active fluid radioactive waste stores by the way of saline concentrates in special tanks in surface layers of ground, above the level of groundwaters. A firm radioactive waste bury in pods from a stainless steel in underground workings, salt deposits, at the bottom of oceans. However this problem can be esteemed in a positive direction, as irradiation is a hard radiation, which one can be used as a power source in nuclear - optical converters with further conversion of optical radiation into the electric power with the help of photoelectric converters. Thus waste at all do not demand special processing and exposure in temporary storehouses. And the electricity can be worked out in a constant mode within many years practically without gang of a stimulus source, if a level of a residual radioactivity and the half-lives of component are high enough.

  19. Biological treatment of sulfidic spent caustics under haloalkaline conditions using soda lake bacteria

    NARCIS (Netherlands)

    Graaff, de C.M.

    2012-01-01

    In this thesis, the development of a newbiotechnological process for the treatment of undiluted sulfidic spent caustics (SSC’s) using soda lake bacteria is described. SSC’s are waste solutions that are formed in the oil and gas industry due to the caustic (NaOH) scrubbing of hydrocarbon

  20. Cost estimates of nuclear waste management

    International Nuclear Information System (INIS)

    The costs caused by the management of the spent fuel produced by nuclear power plant units TVO I and TVO II during their 30 years' operational life are estimated in the report. The cost estimate is based, in regard to the spent fuel management, on TVO's plan according to which spent fuel is stored intermediately and finally disposed as such in Finland. As far as decommissioning is concerned, the estimate is based on deferred dismantlement, and for reactor waste's part, on final disposal at site at Olkiluoto. The report deals also with the development of nuclear waste management reserve during the years 1979...1982 and the effect of the reserve on electricity prices. The Ministry of Trade and Industry has approved the calculation basis 1.36 p/kWh for the year 1982. The effect of significant changes in nuclear waste management plans on the cost estimate has also been discussed. This kind of changes comprise reprocessing, significant increase in waste amounts when a new power plant unit is added into the waste management plan, untimely termination of plant operation and accident at the plant. The cost estimate at October 1982 price level is as follows: spent nuclear fuel transfer to interim storage and intermediate storing 873 million marks, transfer to final disposal site 127 million marks, and encapsulation and final disposal 1450 million marks; decommissioning of the power plant 520 million marks; final disposal of reactor waste 80 million marks. The sales estimate for TVO I and TVO II during the corresponding period of time is 240 TWh. Thus the price effect with 0% discount rate is 1.27 p/kWh. Decrease, when compared to the cost estimate on which the previous provision calculations were based, is due to the new, more precise cost estimates concerning intermediate storing and transportation of spent nuclear fuel

  1. Productivity studies of the nuclear waste programme

    International Nuclear Information System (INIS)

    The Swedish Nuclear Inspectorate reviews and supplements the SKB proposal for cost estimations for the nuclear waste programme. These estimations are of great importance for the determination of annual fees to the Nuclear Waste Fund and guarantee amounts in accordance with the Financing Act. The majority of the Nuclear Waste Fund's assets are invested in real interest bonds, issued by the Swedish state. The average duration for the Nuclear Waste Fund investments was 12.8 years at the end of December 2001. From July 1, 2002 on the Nuclear waste Fund investments will consist of nominal and real bonds on the official market. The Fund is increased in line with the Consumer Price Index (KPI). If real costs within the nuclear waste programme increase at a faster rate than the KPI, there is a risk that the Nuclear Waste Fund will be 'under balanced'. SKI has developed a weighted index, the KBS-3-index, to compare the SKB cost re-estimate with. Productivity changes have however no impact on these indices. The KBS-3-index indicates that there might be a risk that the de facto, cost increases will exceed KPI. An improved productivity might however balance the cost escalations. Productivity is normally defined as production divided by the input of production factors. The production can be a quantity measurement or the value added. A common approach is calculation of the labour productivity. The productivity development within different industries in Sweden and in EU varies, and is not only positive. The so called DEA method is used for productivity and efficiency measurements in public and private operations. Efficiency evaluations based on known norms are not made with the DEA models. Instead the evaluation is performed in relation to an empirically based reference technology, a relative efficiency. A selection or an optimisation of output is difficult for the nuclear waste programme. It is not possible to change parts of the nuclear waste programme to something else

  2. On the need for nuclear waste management

    International Nuclear Information System (INIS)

    One may find reasons justifying one's hopes in the sun or wind or other sources of energy to replace nuclear energy, or even reasons justifying the selfish attitude of those who believe that, for our lifetime, money will buy us enough fossil fuels to continue, but all this may not and must not let us close our eyes to the main problem that must be solved in the next few decades: disposal of the nuclear wastes. Shutting down all nuclear power plants would not free us from the problem at all. In 1986, medical and research establishments and industry have produced more than twice the amount of medium level and low level radioactive waste than have the nuclear power plants. However, even if we would place our hopes in the solar power plant and decide to abandon nuclear power, and even if society would also be prepared to close down the nuclear medical departments of the hospitals, to prohibit the use of radioactive substances by research and industry, we still would have to cope for a certain transitional period with the spent fuel accumulated so far, so that safe reprocessing and disposal of radioactive wastes is a problem remaining in any case. (orig./DG)

  3. Nuclear risk: the juridical control of nuclear waste

    International Nuclear Information System (INIS)

    Nuclear waste is nowadays one of the major problems of this century and particularly for future generations. In front of this devious danger, the law appears to be deficient at two levels: first, juridical norms of prevention are contradictory for they are based on multiple interests. Moreover the decision making process is highly governed by the executive power whereas the legislative power is deliberately neglected. The result of all that is an ambiguous juridical situation: the content of the juridical norms has no specificity and so, its effectiveness is doubtful. Faced with these obvious facts, the present juridical system must be, a priori reconsidered in two fields: first, in that of the responsibility of nuclear waste because the present system is based on that of nuclear civil responsibility, and so is not adapted because it does not take into account the specificity of nuclear waste then, a system of dissuasion must be created which should be based on the right of international interference in order to prevent any attempt to transgress le law concerning nuclear waste. (author)

  4. Inhibition of nuclear waste solutions containing multiple aggressive anions

    International Nuclear Information System (INIS)

    The inhibition of localized corrosion of carbon steel in caustic, high-level radioactive waste solutions was studied using cyclic potentiodynamic polarization scans supplemented by partially immersed coupon tests. The electrochemical tests provided a rapid and accurate means of determining the relationship between the minimum inhibitor requirements and the concentration of the aggressive anions in this system. Nitrate, sulfate, chloride, and fluoride were identified as aggressive anions; however, no synergistic effects were observed between these anions. This observation may have important theoretical implications because it tends to contradict the behavior of aggressive anions as predicted by existing theories for localized corrosion

  5. Corrosion Engineers and Nuclear Waste Disposition

    International Nuclear Information System (INIS)

    More and more articles appear in the press daily about the renaissance of nuclear energy. Even many former opponents of nuclear energy are now convinced that nuclear energy is more environmentally friendly than burning fossil fuels. Nuclear energy does not release carbon dioxide to the atmosphere and therefore does not contribute to the global warming problem. But nuclear energy produces spent fuel or nuclear waste. Spent fuel is radioactive and requires thousands of years of isolation from plants, animals and humans. Every country currently studying the option for disposing of high-level nuclear waste has selected deep geologic formations to be the primary barrier for accomplishing this isolation. It is postulated that by the very nature of these geological sites, they will contain the waste for long time, limiting the spread of radionuclides, for example, through water flow. The release of radionuclides to the environment can also be delayed by the construction of engineered barrier systems between the waste and the geologic formation. Corrosion engineers are participating in the design and the performance prediction of the engineered barriers. The principal engineered component in this multibarrier approach is the container for the waste. Beyond the metallic containers, other engineered barriers could be added to attenuate the impact of the emplacement environment on the containers. The containers will probably be concentric double walled vessels of dissimilar metals. Each vessel would have a specific function. For example, the inner container may be designed to shield radiation and provide structural support to facilitate the safe handling and emplacement operations. This inner container may be over-packed with a corrosion-resistant outer layer. The design of the different containers for nuclear waste would vary according to the nature of the geologic formation at the site of the repository. The most common host rocks for nuclear waste repositories in the world

  6. Nuclear waste management. Quarterly progress report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-06-01

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  7. Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates

  8. Radioactive waste treatment technology at Czech nuclear power plants

    International Nuclear Information System (INIS)

    This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

  9. Nuclear fuel cycle and waste management in France

    International Nuclear Information System (INIS)

    After a short description of the nuclear fuel cycle mining, milling, enrichment and reprocessing, radioactive waste management in France is exposed. The different types of radioactive wastes are examined. Storage, solidification and safe disposal of these wastes are described

  10. Systems approach to nuclear waste glass development

    International Nuclear Information System (INIS)

    Development of a host solid for the immobilization of nuclear waste has focused on various vitreous wasteforms. The systems approach requires that parameters affecting product performance and processing be considered simultaneously. Application of the systems approach indicates that borosilicate glasses are, overall, the most suitable glasses for the immobilization of nuclear waste. Phosphate glasses are highly durable; but the glass melts are highly corrosive and the glasses have poor thermal stability and low solubility for many waste components. High-silica glasses have good chemical durability, thermal stability, and mechanical stability, but the associated high melting temperatures increase volatilization of hazardous species in the waste. Borosilicate glasses are chemically durable and are stable both thermally and mechanically. The borosilicate melts are generally less corrosive than commercial glasses, and the melt temperature miimizes excessive volatility of hazardous species. Optimization of borosilicate waste glass formulations has led to their acceptance as the reference nuclear wasteform in the United States, United Kingdom, Belgium, Germany, France, Sweden, Switzerland, and Japan

  11. What can be done with nuclear wastes?

    International Nuclear Information System (INIS)

    In this book, a technical adviser of the French atomic energy commission (CEA) answers the questions of the author about nuclear wastes: how are they produced? Where are they stored? Are they dangerous? How do we protect against their harmful effects? (J.S.)

  12. Impact of nuclear waste traffic on highways

    International Nuclear Information System (INIS)

    A system was developed to evaluate the impact of nuclear waste traffic on the structural performance of highway pavements throughout the state of Nevada. The associated needs of maintenance and rehabilitations can also be evaluated along with their costs. This paper summarizes the system and provides two sample analyses

  13. Nuclear Waste Management under Approaching Disaster

    NARCIS (Netherlands)

    Ilg, Patrick; Gabbert, Silke; Weikard, Hans Peter

    2016-01-01

    This article compares different strategies for handling low- and medium-level nuclear waste buried in a retired potassium mine in Germany (Asse II) that faces significant risk of uncontrollable brine intrusion and, hence, long-term groundwater contamination. We survey the policy process that has

  14. THERMOCHEMICAL MODELING OF NUCLEAR WASTE GLASS

    Science.gov (United States)

    The development of assessed and consistent phase equilibria and thermodynamic data for major glass constituents used to incorporate high-level nuclear waste is discussed in this paper. The initial research has included the binary Na{sub 2}O-SiO{sub 2}, Na{sub 2}O-Al{sub 2}O{sub ...

  15. Classification and management of nuclear wastes

    International Nuclear Information System (INIS)

    The nuclear wastes resulting from nuclear explosives and reactors are classified in various physical states ( solid , fluid and gaseous ) . In order to get rid of the activity of these radioactive wastes , they are stored in the submerged pools of water as first step and under tight control for many years until they lose a part of their high radiation activity . Also by using of physical and chemical methods to reduce them to the lowest possible size through casting them in the form of small molds placed inside other molds of concrete surrounded by a thick wall of steel, where they are transported carefully to the concrete deep wells that may range of several kilometers deep in the ground. As for nuclear waste storage in sea beds and oceans , the concrete containers are buried under depths up to 500 meters from the ground , and this depth is sufficient to reduce their risks to an acceptable limit , once taking into account the stability that covers these beds/bottoms , depth of which may reach several kilometers . Scientists are now studying the possibility of sending thousands of tons of nuclear wastes in parcels using missiles heading toward the sun or deployment in space far from the earth. (author)

  16. Nuclear wastes and the evaluation of hazards

    International Nuclear Information System (INIS)

    A review is given of the volume and contents of wastes from the operation and the decommissioning of a 1000 MWe reactor and of wastes generated by spent fuel management. Official Dutch reports appear to remarkably underestimate nuclear waste problems. A comparison between the 'throw away' option and the 'full recycling' for spent fuel shows that recycling increases the waste volume with a factor of 15 to 40, spreads half of the longlive radionuclides over instable packing materials, enhances the accessibility of plutonium for abuse, increases the radiation exposure to workers and the public as a whole, and reduces in the long term the plutonium content of the waste only with a factor 5 to 7. In the analysis of long term risks of nuclear waste, the environmental dose commitment i.e. the total integrated population dose should be calculated. Individual risk estimates such as made in a Dutch risk analysis are highly insufficient. Referring to the same analysis uncertainties in human knowledge, the influence of human failure or intervention and assumptions about future social development, are discussed. (Auth.)

  17. Role of utility nuclear waste management group

    International Nuclear Information System (INIS)

    The Utility Nuclear Waste Management Group (UNWMG) is a group of 39 nuclear utilities which support a general program which is under the administration of Edison Electric Institute (EEI), but which actually operates quite separately. The function of the group is primarily to interact with Congress in the development of desired legislation, interact with NRC and EPA in the development of regulations, and interact with DOE in the carrying out of programs in which they are interested. The group is organized into four working groups. One devotes its efforts to high-level waste activities, one to low-level waste interests, one to spent fuel storage and reprocessing, and a fourth to public information. Each of these working groups has a number of task forces that are organized to respond to a particular need at the time. The activities of each group are discussed briefly

  18. Public values associated with nuclear waste disposal

    International Nuclear Information System (INIS)

    This report presents the major findings from a study designed to assess public attitudes and values associated with nuclear waste disposal. The first objective was to obtain from selected individuals and organizations value and attitude information which would be useful to decision-makers charged with deciding the ultimate disposal of radioactive waste materials. A second research objective was to obtain information that could be structured and quantified for integration with technical data in a computer-assisted decision model. The third general objective of this research was to test several attitude-value measurement procedures for their relevance and applicability to nuclear waste disposal. The results presented in this report are based on questionnaire responses from 465 study participants

  19. Nuclear waste issues: a perspectives document

    International Nuclear Information System (INIS)

    This report contains the results of systematic survey of perspectives on the question of radioactive waste management. Sources of information for this review include the scientific literature, regulatory and government documents, pro-nuclear and anti-nuclear publications, and news media articles. In examining the sources of information, it has become evident that a major distinction can be made between the optimistic or positive viewpoints, and the pessimistic or negative ones. Consequently, these form the principal categories for presentation of the perspectives on the radioactive waste management problem have been further classified as relating to the following issue areas: the physical aspects of radiation, longevity, radiotoxicity, the quantity of radioactive wastes, and perceptual factors

  20. Nuclear waste issues: a perspectives document

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, J.J.; Smith, C.F.; Ciminese, F.J.

    1983-02-01

    This report contains the results of systematic survey of perspectives on the question of radioactive waste management. Sources of information for this review include the scientific literature, regulatory and government documents, pro-nuclear and anti-nuclear publications, and news media articles. In examining the sources of information, it has become evident that a major distinction can be made between the optimistic or positive viewpoints, and the pessimistic or negative ones. Consequently, these form the principal categories for presentation of the perspectives on the radioactive waste management problem have been further classified as relating to the following issue areas: the physical aspects of radiation, longevity, radiotoxicity, the quantity of radioactive wastes, and perceptual factors.

  1. The need for public education: Nuclear waste disposal programs

    International Nuclear Information System (INIS)

    The nuclear industry has made great technical strides in the quest for safe and efficient management and disposal of nuclear wastes. Public acceptance and cooperation, however, lag far behind. An extensive in-depth public information campaign must be instituted if the public is to deal with nuclear waste issues intelligently and reasonably rather than emotionally. Westinghouse has developed the Nuclear Waste Management Outreach Program, an objective seminar series, to make the necessary information both available and accessible. The program was initially designed as a broad-scoped nuclear waste management overview to give participants comprehensive information on all aspects of nuclear waste

  2. The so-called nuclear waste affair

    International Nuclear Information System (INIS)

    The so-called nuclear waste affair has placed the Hanau nuclear fuel company NUKEM and its daughter Transnuklear in the centre of public discussions about nuclear safety. The disclosed and alleged irregularities have led to preliminary investigation by the public prosecutor, a parliamentary inquiry commission has been set in, and the Hanau companies have been re-organised by order of the state: Transnuklear has been dissolved, and NUKEM will discontinue fuel element fabrication. The article in hand explains the foundation and the history of the NUKEM company and its daughter companies in order to reveal the significance of the current events. (orig./DG)

  3. Radioactive waste management and the nuclear renaissance

    International Nuclear Information System (INIS)

    Full text: Full text: For many years, nuclear supporters have been talking of a possible nuclear power renaissance. Today there are definite signs that this is finally beginning to happen. New plants are being built or planned in China, Japan, Korea, Finland, France and even the USA. Phase-out policies are being rethought in countries like Sweden, Belgium and Germany. Countries like Vietnam, Indonesia, the Baltic States and even Australia are choosing or debating initiating a nuclear programme. Support for these nuclear power developments may be strongly influenced by the progress of waste management programmes, especially final disposal. Conversely, the growing realisation of the potential global benefits of nuclear power may well lead to increased support, effort and funding for initiatives to ensure that all nations have access to safe and secure waste management facilities. This implies that large nuclear programmes must make progress with implementation of treatment, storage and disposal facilities for all of their radioactive wastes. For small nuclear programmes (and for countries with nuclear applications other than power generation) such facilities are also necessary. For economic and other reasons, these small programmes may not be able to implement all of the required national facilities. Multinational cooperation is needed. This can be realised by large countries providing back-end services such as reprocessing and disposal, or by small countries forming regional or international partnerships to implement shared facilities for storage and/or disposal. This paper will trace through the past decades the mutual interactions between programmes in nuclear power and in waste management. The relevant issues of concern for both include radiological safety, environmental impacts and, most topically, non-proliferation and security. Debates on these issues have strongly affected national efforts to implement power plants and repositories, and also influenced the

  4. Ethical Issues in Nuclear Waste Management

    International Nuclear Information System (INIS)

    Nuclear experts claim that the health risks from radioactive waste disposal are low compared to other environmental hazards, yet the general public is sceptical of the industry's ability to guarantee acceptable safety standards. Many allude to what might be deemed morally relevant factors, such as potential harms to future generations, possibly catastrophic consequences and environmental effects. Industry has often tended to respond with a claim that the public has an irrational perception of radiation risks, particularly those from man-made rather than natural sources. From a philosophical point of view it is interesting to consider exactly how nuclear risks might differ from other hazards, not least to evaluate which ethically relevant factors could be used to defend the stringent demands made by society for nuclear waste disposal

  5. Ethical Issues in Nuclear Waste Management

    Energy Technology Data Exchange (ETDEWEB)

    Oughton, Deborah [Agricultural Univ. of Norway, Aas (Norway). Dept. of Chemistry and Biotechnology

    2001-07-01

    Nuclear experts claim that the health risks from radioactive waste disposal are low compared to other environmental hazards, yet the general public is sceptical of the industry's ability to guarantee acceptable safety standards. Many allude to what might be deemed morally relevant factors, such as potential harms to future generations, possibly catastrophic consequences and environmental effects. Industry has often tended to respond with a claim that the public has an irrational perception of radiation risks, particularly those from man-made rather than natural sources. From a philosophical point of view it is interesting to consider exactly how nuclear risks might differ from other hazards, not least to evaluate which ethically relevant factors could be used to defend the stringent demands made by society for nuclear waste disposal.

  6. Can shale safely host US nuclear waste?

    Science.gov (United States)

    Neuzil, C.E.

    2013-01-01

    "Even as cleanup efforts after Japan’s Fukushima disaster offer a stark reminder of the spent nuclear fuel (SNF) stored at nuclear plants worldwide, the decision in 2009 to scrap Yucca Mountain as a permanent disposal site has dimmed hope for a repository for SNF and other high-level nuclear waste (HLW) in the United States anytime soon. About 70,000 metric tons of SNF are now in pool or dry cask storage at 75 sites across the United States [Government Accountability Office, 2012], and uncertainty about its fate is hobbling future development of nuclear power, increasing costs for utilities, and creating a liability for American taxpayers [Blue Ribbon Commission on America’s Nuclear Future, 2012].However, abandoning Yucca Mountain could also result in broadening geologic options for hosting America’s nuclear waste. Shales and other argillaceous formations (mudrocks, clays, and similar clay-rich media) have been absent from the U.S. repository program. In contrast, France, Switzerland, and Belgium are now planning repositories in argillaceous formations after extensive research in underground laboratories on the safety and feasibility of such an approach [Blue Ribbon Commission on America’s Nuclear Future, 2012; Nationale Genossenschaft für die Lagerung radioaktiver Abfälle (NAGRA), 2010; Organisme national des déchets radioactifs et des matières fissiles enrichies, 2011]. Other nations, notably Japan, Canada, and the United Kingdom, are studying argillaceous formations or may consider them in their siting programs [Japan Atomic Energy Agency, 2012; Nuclear Waste Management Organization (NWMO), (2011a); Powell et al., 2010]."

  7. Nuclear Waste under Mode 2 - Knowledge Production

    International Nuclear Information System (INIS)

    The Swedish National Council for Nuclear Waste, established in 1989, consists of academic scholars from the natural and technical sciences as well as the social and humanistic sciences. The council has attended to the contribution of knowledge and theoretical perspectives from social science and the humanities at several occasions and most recently in a special report from 2007: Straalande forskningsutsikter? En oeversikt om kaernavfallsfraagor inom samhaellsvetenskaplig forskning (Radiating Prospects for Research? An Overview of Nuclear Waste Issues in Social Scientific Research) (Bergquist). The report concludes that most of the research in Sweden has been made with the support of SKB (Swedish Nuclear Fuel and Waste Management Company), i.e. the company which has the main responsibility of finding a technical solution for a safe deposition of HLW in Sweden. Since 2004 SKB has conducted a special social scientific programme with a focus on local processes of decision making, local social economic factors and attitudes towards nuclear waste (even as international perspectives have also been highlighted in other projects).1 The programme has contributed to our knowledge about the history of nuclear power and nuclear waste. The significance of this programme notwithstanding, research that analyses the nuclear waste issue in a larger democratic and economic perspective is lacking. Furthermore, there is need for more theoretical perspectives on nuclear waste from both humanities and social science. What are the more general social and cultural conditions for the activities of the main actors on the national and international scene? One important example is the so-called 'Mode 2' theory on science and society. This idea was introduced in book published in 1994 (Gibbons), wherein a number social scientific scholars argue that contemporary research is moving from academic, investigator-initiated and discipline-based knowledge production (Mode 1 knowledge) to a 'context

  8. The nuclear waste disaster. A view behind the curtain of the presumably clean nuclear power

    International Nuclear Information System (INIS)

    The brochure on the nuclear waste disaster - a view behind the curtain of the presumably clean nuclear power discusses the following topics: Thuringia and Saxony - radiating landscapes, Gronau - 100.000 tons for eternity, Gundremmingen - nuclear waste records and castor shortage, Brunsbuettel - castor storage facility without licensing, Juelich the pebble bed drama, Karlsruhe - the hall is filled, Obrigheim - radioactive waste for cooking pots, Asse - the ticking bomb, final repositories - an illusion without solution, stop the waste production, Germany - endless nuclear waste.

  9. Management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

  10. Disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    In 1978, the governments of Canada and Ontario established the Nuclear Fuel Waste Management program. As of the time of the conference, the research performed by AECL was jointly funded by AECL and Ontario Hydro through the CANDU owners' group. Ontario Hydro have also done some of the research on disposal containers and vault seals. From 1978 to 1992, AECL's research and development on disposal cost about C$413 million, of which C$305 was from funds provided to AECL by the federal government, and C$77 million was from Ontario Hydro. The concept involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield. Used fuel (or possibly solidified reprocessing waste) would be sealed into containers (of copper, titanium or special steel) and emplaced (probably in boreholes) in the vault floor, surrounded by sealing material (buffer). Disposal rooms might be excavated on more than one level. Eventually all excavated openings in the rock would be backfilled and sealed. Research is organized under the following headings: disposal container, waste form, vault seals, geosphere, surface environment, total system, assessment of environmental effects. A federal Environmental Assessment Panel is assessing the concept (holding public hearings for the purpose) and will eventually make recommendations to assist the governments of Canada and Ontario in deciding whether to accept the concept, and how to manage nuclear fuel waste. 16 refs., 1 tab., 3 figs

  11. Nuclear waste management. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-04-01

    Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

  12. The management of nuclear fuel waste

    International Nuclear Information System (INIS)

    A Select Committee of the Legislature of Ontario was established to examine the affairs of Ontario Hydro, the provincial electrical utility. The Committee's terms of reference included examination of the waste management program being carried out jointly by the Ontario provincial government and the Canadian federal government. Public hearings were held which included private citizens as well as officials of organizations in the nuclear field and independent experts. Recommendations were made concerning the future direction of the Canadian fuel waste management program. (O.T.)

  13. Titanium alloy corrosion in nuclear waste environments

    International Nuclear Information System (INIS)

    A corrosion study has been conducted on the titanium alloys Ti-50A, TiCode 12, and Ti-Pd to evaluate their suitability as a long lifetime (300 to 600 year) canister material for the isolation of nuclear wastes. TiCode 12, selected as the primary candidate material, is shown to be very resistant to environmental attack. Results of electrochemical, general corrosion, and stress corrosion cracking experiments are presented. These data, including those from severe overtests, have shown that TiCode 12 is a viable candidate material for long-term waste isolation. 17 figures

  14. The nuclear fuel waste act: context, public confidence, social considerations

    International Nuclear Information System (INIS)

    Like any energy source, nuclear energy generates some waste, in this case mostly low-level radioactive waste and nuclear fuel waste. In Canada, nuclear fuel waste refers to the irradiated fuel bundles that come out of domestic nuclear reactors and includes those bundles discharged from twenty-two Canadian CANDU reactors. Twenty of these reactors are owned by Ontario Power Generation Inc (OPG), and the other two are owned by Hydro-Quebec and New Brunswick Power. Atomic Energy of Canada Limited (AECL), a federal Crown corporation, produces a small amount of such waste from its prototype and research reactors. OPG produces about 90% of the total amount of waste, the other two nuclear utilities about 8%, and AECL 2%. Other waste owners, e.g., universities, produce a much smaller quantity of nuclear fuel waste. About 1 million bundles of nuclear fuel waste are currently stored at nuclear reactor sites in Canada; 60 000 bundles are expected to be produced annually. A cornerstone of Canada approach to addressing radioactive waste management issues is the Government of Canada 1996 Policy Framework for Radioactive Waste, which has set general policy for dealing with all radioactive waste from the nuclear fuel cycle (nuclear fuel waste, low-level radioactive waste, and uranium mine and mill waste). The Policy Framework defines the respective roles of the Government and waste owners. It also sets the stage for developing institutional and financial arrangements to implement long-term waste management solutions in a safe, environmentally sound, comprehensive, cost-effective, and integrated manner. The challenge is to ensure that the public is confident that the Policy Framework is being carried out in the best interest of Canadians. Part of the answer to this challenge was the development of the Nuclear Fuel Waste Act which entered into force on November 15, 2002. (author)

  15. Velocity peaks and caustic rings

    International Nuclear Information System (INIS)

    The late infall of cold dark matter onto an isolated galaxy produces flows with definite velocity vectors at any physical point in the galactic halo. It also produces caustic rings, which are places in space where the dark matter density is very large. The self-similar model of galactic halo formation predicts that the caustic ring radii an follow the approximate law an ≅ 1/n. Bumps in the rotation curves of NGC 3198 and of our own galaxy are interpreted as due to caustic rings of dark matter

  16. Nuclear waste: Quarterly report on DOE's Nuclear Waste Program as of March 31, 1987

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act established a national program and policy for safely storing, transporting, and disposing of nuclear waste. This fact sheet provides the status of the Department of Energy's program activities. They include (1) the release of a draft amendment to the mission plan in which DOE extends by 5 years its target date for beginning first repository operations and information on DOE's decision to postpone site-specific activities for the second repository; (2) a monitored retrievable storage proposal and related documents; (3) receipts of comments from utilities, state regulators, and others on its Notice of Inquiry on proposals for the calculation of fees for defense waste disposal; and (4) information on the Nuclear Waste Fund collection of over /135.4 million in fees and investment income and obligations of $139 million for program activities. The fund balance as of March 31, 1987, was about $1.5 billion

  17. Review of radiation effects in solid-nuclear-waste forms

    International Nuclear Information System (INIS)

    Radiation effects on the stability of high-level nuclear waste (HLW) forms are an important consideration in the development of technology to immobilize high-level radioactive waste because such effects may significantly affect the containment of the radioactive waste. Since the required containment times are long (103 to 106 years), an understanding of the long-term cumulative effects of radiation damage on the waste forms is essential. Radiation damage of nuclear waste forms can result in changes in volume, leach rate, stored energy, structure/microstructure, and mechanical properties. Any one or combination of these changes might significantly affect the long-term stability of the nuclear waste forms. This report defines the general radiation damage problem in nuclear waste forms, describes the simulation techniques currently available for accelerated testing of nuclear waste forms, and reviews the available data on radiation effects in both glass and ceramic (primarily crystalline) waste forms. 76 references

  18. Review of radiation effects in solid-nuclear-waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Weber, W.J.

    1981-09-01

    Radiation effects on the stability of high-level nuclear waste (HLW) forms are an important consideration in the development of technology to immobilize high-level radioactive waste because such effects may significantly affect the containment of the radioactive waste. Since the required containment times are long (10/sup 3/ to 10/sup 6/ years), an understanding of the long-term cumulative effects of radiation damage on the waste forms is essential. Radiation damage of nuclear waste forms can result in changes in volume, leach rate, stored energy, structure/microstructure, and mechanical properties. Any one or combination of these changes might significantly affect the long-term stability of the nuclear waste forms. This report defines the general radiation damage problem in nuclear waste forms, describes the simulation techniques currently available for accelerated testing of nuclear waste forms, and reviews the available data on radiation effects in both glass and ceramic (primarily crystalline) waste forms. 76 references.

  19. Theoretical modelling of nuclear waste flows - 16377

    International Nuclear Information System (INIS)

    A large amount of nuclear waste is stored in tailings ponds as a solid-liquid slurry, and liquid flows containing suspensions of solid particles are encountered in the treatment and disposal of this waste. In processing this waste, it is important to understand the behaviour of particles within the flow in terms of their settling characteristics, their propensity to form solid beds, and the re-suspension characteristics of particles from a bed. A clearer understanding of such behaviour would allow the refinement of current approaches to waste management, potentially leading to reduced uncertainties in radiological impact assessments, smaller waste volumes and lower costs, accelerated clean-up, reduced worker doses, enhanced public confidence and diminished grounds for objection to waste disposal. Mathematical models are of significant value in nuclear waste processing since the extent of characterisation of wastes is in general low. Additionally, waste processing involves a diverse range of flows, within vessels, ponds and pipes. To investigate experimentally all waste form characteristics and potential flows of interest would be prohibitively expensive, whereas the use of mathematical models can help to focus experimental studies through the more efficient use of existing data, the identification of data requirements, and a reduction in the need for process optimisation in full-scale experimental trials. Validated models can also be used to predict waste transport behaviour to enable cost effective process design and continued operation, to provide input to process selection, and to allow the prediction of operational boundaries that account for the different types and compositions of particulate wastes. In this paper two mathematical modelling techniques, namely Reynolds-averaged Navier-Stokes (RANS) and large eddy simulation (LES), have been used to investigate particle-laden flows in a straight square duct and a duct with a bend. The flow solutions provided by

  20. International nuclear waste management fact book

    Energy Technology Data Exchange (ETDEWEB)

    Abrahms, C W; Patridge, M D; Widrig, J E

    1995-11-01

    The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US.

  1. International nuclear waste management fact book

    International Nuclear Information System (INIS)

    The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US

  2. Nuclear waste management programme 1997 for the Olkiluoto and Loviisa nuclear power plants

    International Nuclear Information System (INIS)

    A joint company Posiva Oy founded by nuclear energy producing Teollisuuden Voima Oy (TVO) and Imatran Voima Oy (IVO) coordinates the research work of the companies on nuclear waste management in Finland. In Posiva's Nuclear Waste Management Programme 1997, an account of the nuclear waste management measures of TVO and IVO is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, nuclear waste management situation and the programme of activities are reported. The nuclear waste management research for the year 1997 and more generally for the years 1997-2001 is presented

  3. Nuclear waste management programme 2000 for the Loviisa and Olkiluoto nuclear power plants

    International Nuclear Information System (INIS)

    A joint company Posiva Oy founded by nuclear energy producing Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy coordinates the research work of the companies on nuclear waste management in Finland. In Posiva's Nuclear Waste Management Programme 2000, an account of the nuclear waste management measures of TVO and Fortum is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, nuclear waste management situation and the programme of activities are reported. The nuclear waste management research for the year 2000 and more generally for the years 2000-2004 is presented

  4. Nuclear waste management programme 1999 for the Loviisa and Olkiluoto nuclear power plants

    International Nuclear Information System (INIS)

    A joint company Posiva Oy founded by nuclear energy producing Teollisuuden Voima Oy (TVO) and Imatran Voima Oy (IVO) coordinates the research work of the companies on nuclear waste management in Finland. in Posiva's Nuclear Waste Management Programme 1999, an account of the nuclear waste management measures of TVO and IVO is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, nuclear waste management situation and the programme of activities are reported. The nuclear waste management research for the year 1999 and more generally for the years 1999-2003 is presented

  5. Nuclear waste management programme 1998 for the Olkiluoto and Loviisa nuclear power plants

    International Nuclear Information System (INIS)

    A joint company Posiva founded by nuclear energy producing Teollisuuden Voima Oy (TVO) and Imatran Voima Oy (IVO) coordinates the research work of the companies on nuclear waste management in Finland. In Posiva's Nuclear Waste Management Programme 1998, an account of the nuclear waste management measures of TVO and IVO's is given as required by the sections 74 and 75 of the Nuclear Energy Degree. At first, nuclear waste management situation and the programme of activities are reported. The nuclear waste management research for the year 1997 and more generally for the years 1998-2002 is presented

  6. Dissolution of tailored ceramic nuclear waste forms

    International Nuclear Information System (INIS)

    Dissolution experiments on polyphase, high alumina tailored ceramic nuclear waste forms developed for the chemical immobilization of Savannah River Plant nuclear waste are described. Three forms of leach tests have been adopted; bulk samples conforming to the Materials Characterization Center Static Leach Test (MCC-1), a powdered sample leach test, and a leach test performed on transmission electron microscope thin foil samples. From analysis of these tests the crystalline phases that preferentially dissolve on leaching and the product phases formed are identified and related to the tailoring and processing schemes used in forming the ceramics. The thin foil sample leaching enables the role of intergranular amorphous phases as short-circuit leaching paths in polyphase ceramics to be investigated

  7. Office of the US Nuclear Waste Negotiator

    International Nuclear Information System (INIS)

    The Office of the US Nuclear Waste Negotiator was created as an independent federal agency by the US Congress pursuant to the 1987 amendments to the Nuclear Waste Policy Act of 1982. The office, which was authorized by Congress for 5 years following the enactment of the 1987 amendments, is headquartered in Boise, Idaho, and maintains a liaison office in Washington DC. The negotiator is charged with the responsibility of attempting to find a state or Indian tribe willing to host a repository or monitored retrievable storage (MRS) facility at a technically qualified site on reasonable terms. The negotiator is instructed to negotiate with any state or Indian tribe that expresses an interest in hosting a repository or MRS facility. The negotiator will formally submit the negotiated agreement and environmental assessment to Congress, and the agreement will become effective when acted on by Congress and signed by the President into law

  8. Nuclear Materials: Reconsidering Wastes and Assets - 13193

    International Nuclear Information System (INIS)

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

  9. Can clays ensure nuclear waste repositories?

    OpenAIRE

    Zaoui, A.; Sekkal, W.

    2015-01-01

    Research on argillite as a possible host rock for nuclear waste disposal is still an open subject since many issues need to be clarified. In the Underground Research Laboratories constructed for this purpose, a damaged zone around the excavation has been systematically observed and characterized by the appearance of micro-fissures. We analyse here -at nanoscale level- the calcite/clay assembly, the main constituents of argillite, under storage conditions and show the fragility of the montmori...

  10. Radiation damage in nuclear waste materials

    International Nuclear Information System (INIS)

    Final disposal of high-level radioactive nuclear waste is usually envisioned in some sort of ceramic material. The physical and chemical properties of host materials for nuclear waste can be altered by internal radiation and consequently their structural integrity can be jeopardized. Assessment of long-term performance of these ceramic materials is therefore vital for a safe and successful disposal. This paper presents an overview of studies on several possible candidate materials for immobilization of fission products and actinides, such as spinel (MgAl2O4), perovskite (CaTiO3), zircon (ZrSiO4), and pyrochlore (Gd2Ti2O7 and Gd2Zr2O7). The basic microscopic picture of radiation damage in ceramics consists of atomic displacements and ionization. In many cases these processes result in amorphization (metaminctization) of irradiated material. The evolution of microscopic structure during irradiation leads to various macroscopic radiation effects. The connection between microscopic and macroscopic picture is in most cases at least qualitatively known and studies of radiation induced microscopic changes are therefore an essential step in the design of a reliable nuclear waste host material. The relevance of these technologically important results on our general understanding of radiation damage processes and on current research efforts in Slovenia is also addressed. (author)

  11. Causticizing for Black Liquor Gasifiers

    Energy Technology Data Exchange (ETDEWEB)

    Scott Sinquefeld; James Cantrell; Xiaoyan Zeng; Alan Ball; Jeff Empie

    2009-01-07

    The cost-benefit outlook of black liquor gasification (BLG) could be greatly improved if the smelt causticization step could be achieved in situ during the gasification step. Or, at a minimum, the increase in causticizing load associated with BLG could be mitigated. A number of chemistries have been proven successful during black liquor combustion. In this project, three in situ causticizing processes (titanate, manganate, and borate) were evaluated under conditions suitable for high temperature entrained flow BLG, and low temperature steam reforming of black liquor. The evaluation included both thermodynamic modeling and lab experimentation. Titanate and manganate were tested for complete direct causticizing (to thus eliminate the lime cycle), and borates were evaluated for partial causticizing (to mitigate the load increase associated with BLG). Criteria included high carbonate conversion, corresponding hydroxide recovery upon hydrolysis, non process element (NPE) removal, and economics. Of the six cases (three chemistries at two BLG conditions), only two were found to be industrially viable: titanates for complete causticizing during high temperature BLG, and borates for partial causticizing during high temperature BLG. These two cases were evaluated for integration into a gasification-based recovery island. The Larsen [28] BLG cost-benefit study was used as a reference case for economic forecasting (i.e. a 1500 tpd pulp mill using BLG and upgrading the lime cycle). By comparison, using the titanate direct causticizing process yielded a net present value (NPV) of $25M over the NPV of BLG with conventional lime cycle. Using the existing lime cycle plus borate autocausticizing for extra capacity yielded a NPV of $16M.

  12. Clearance of nuclear waste and decommissioned nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

    The guide is applied to waste, including recyclable materials, arising from the operation and decommissioning of a nuclear facility, as well as to non-dismantled buildings and surrounding sites being subject to regulatory control. The guide gives the radiation protection principles to be followed in the planning and implementation of clearances. The guide also covers the clearance procedures and the activity monitoring and record-keeping of materials to be cleared. The guide does not address radioactive waste or contaminated sites arising as a consequence of the utilization of natural resources. The guidance for such activities is given in Section 13 of the Finnish Radiation Act, Section 6 of the Radiation Decree and in STUK's (Finnish Radiation and Nuclear Safety Authority) guides ST 6.2, ST 12.1 and ST 12.2

  13. General and regulatory aspects of nuclear waste disposal in Finland

    International Nuclear Information System (INIS)

    A policy decision concerning nuclear waste management was made by the government of Finland in April 1978. The decision defines the principal functional and financial responsibilities for waste management. Preparations for specific nuclear waste management legislation were only recently initiated. Research and development activities are under way in a limited scale, geological storage and disposal are included. Licensing of nuclear facilities is the responsibility of the Ministry of Trade and Industry. Practical evaluation and control measures are performed by the Institute of Radiation Protection. General legal framework for nuclear waste disposal is included in atomic energy and radiation protection legislations. So far there are no technical criteria or regulations for waste disposal. Licensing process for waste repositories, although not yet formulated, will evidently contain elements similar to the existing procedure for nuclear power plants. Particular emphasis should be put on site selection and approval. Disposal into deep crystalline rock formations is regarded as the realistic nuclear waste disposal alternative in Finland. (author)

  14. Stakeholder involvement in Swedish nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Elam, Mark; Sundqvist, Goeran [Goeteborg Univ. (Sweden). Section for Science and Technology Studies

    2006-09-15

    This report concerning Swedish nuclear waste management has been produced as part of a cross national research project: CARL - A Social Science Research Project into the Effects of Stakeholder involvement on Decision-Making in Radioactive Waste Management. Besides Sweden, the participating countries are Belgium, Canada, Finland, Slovenia and United Kingdom. A social science research team, working for three years, is in the first phase conducting research in their own countries in order to produce 6 country reports. During the next years the focus will shift to comparisons of stakeholder involvement practices in the participating countries. The report addresses current practices of Swedish nuclear waste management and their historical development. The main focus is on past, current and emerging patterns of stakeholder involvement in the siting of a deep repository for the final disposal of Sweden's spent nuclear fuel. The general questions attended to in the report are: Who are the main stakeholders, and how have they emerged and gained recognition as such? What are the issues currently subject to stakeholder involvement and how have these been decided upon? How is stakeholder involvement organized locally and nationally and how has this changed over time? How has stakeholder involvement gained acceptance as an activity of value in the siting of major waste facilities? The report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden's spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, into something more like a patchwork of different shapes and forms. Some of the forces that may well contribute to the further elaboration of the patchwork of stakeholder involvement have been pointed out, contingently modifying once more its overall colour and orientation. Questions

  15. Stakeholder involvement in Swedish nuclear waste management

    International Nuclear Information System (INIS)

    This report concerning Swedish nuclear waste management has been produced as part of a cross national research project: CARL - A Social Science Research Project into the Effects of Stakeholder involvement on Decision-Making in Radioactive Waste Management. Besides Sweden, the participating countries are Belgium, Canada, Finland, Slovenia and United Kingdom. A social science research team, working for three years, is in the first phase conducting research in their own countries in order to produce 6 country reports. During the next years the focus will shift to comparisons of stakeholder involvement practices in the participating countries. The report addresses current practices of Swedish nuclear waste management and their historical development. The main focus is on past, current and emerging patterns of stakeholder involvement in the siting of a deep repository for the final disposal of Sweden's spent nuclear fuel. The general questions attended to in the report are: Who are the main stakeholders, and how have they emerged and gained recognition as such? What are the issues currently subject to stakeholder involvement and how have these been decided upon? How is stakeholder involvement organized locally and nationally and how has this changed over time? How has stakeholder involvement gained acceptance as an activity of value in the siting of major waste facilities? The report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden's spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, into something more like a patchwork of different shapes and forms. Some of the forces that may well contribute to the further elaboration of the patchwork of stakeholder involvement have been pointed out, contingently modifying once more its overall colour and orientation. Questions have been

  16. Nuclear waste: Quarterly report on DOE's nuclear waste program as of June 30, 1987

    International Nuclear Information System (INIS)

    Department of Energy nuclear waste activities during the quarter ending June 30, 1987 include extension of the operational data planned for the first repository from January 1998 to 2003; a proposal to construct and operate a monitored retrievable storage facility in Roane County, Tennessee; and a decision to delay site-specific work for a second repository and begin in 1995 a national survey of potential second repository sites. The Nuclear Waste Fund collected over $170 million in fees and investment income during the quarter and obligated about $31 million for program activities. The fund balance as of June 1987 was about $1.5 billion. During this quarter, several legislative proposals were introduced in the Congress that would redirect or significantly change the nuclear waste management program

  17. Nuclear Waste, Risks and Sustainable Development

    International Nuclear Information System (INIS)

    The proposed Swedish nuclear waste project is not in line with the three principles of sustainable development. In some aspects, it is not even compatible with Swedish law and ought therefore not to be given a permit under present circumstances. In our view, a number of measures need to be taken to improve the likelihood that the waste repository will promote and not further jeopardise sustainable development. One obvious measure would be to follow the recommendations concerning polluter pays principle put forward by the 2004 governmental committee. Further, it can be credible argued that the focus of the present disposal process has not been to find the best site and method from environmental point of view. If the precautionary principle is to be applied (and Swedish law is to be followed), alternative methods and sites have to be examined to see if they could provide better long-term safety. Concerning method, there are options that deserve much more attention such as so called 'deep boreholes'. In this approach the nuclear waste is placed in deep boreholes at depths of 2-4 km. Studies show that the long-term environmental safety and the possibility of hindering intentional intrusion may improve using the deep borehole method. Regarding localisation, one option would be to avoid siting the repository on the coast, but in what is called a 'recharge area'. In such an area groundwater on a regional scale travels downwards into the bedrock and it may take 50 000 years for a release of radioactivity to reach the surface, compared to less than 100 years with a coastal siting. Evidently, there may be better methods and sites than those now proposed by the Swedish nuclear industry. These options must be examined in detail before a decision is taken to implement the KBS method at a coastal site. If such methods or sites are found better they have to be used in the first place. Improvements are also necessary when it comes to public participation. We believe it is possible

  18. The future of the civil nuclear industry: the challenge of nuclear wastes

    International Nuclear Information System (INIS)

    This research thesis first gives an overview of the nuclear waste processing and storage in France (reasons and future of this political choice, legal framework, storage means and sites, weaknesses of waste storage). Then it comments various aspects of the processing of foreign nuclear wastes in France: economy and media impact, law and contracts, waste transport, temporary storage in France

  19. Caustic stress corrosion cracking

    International Nuclear Information System (INIS)

    Liquid Metal Fast Breeder Reactors (LMFBRs) use sodium as a coolant for transfer of heat from the core to the steam generators. Maintenance and examination of the system require removal of sodium from components of the system. One process for removal reacts the sodium with water vapor and removes the residual sodium hydroxide from the components by rinsing with liquid water. This process exposes components such as pumps, heat exchangers, valves, and fuel-handling machines to contact with aqueous NaOH solutions in various concentrations over a range of temperatures and times. Since stress can be present in these components, as generated by fabrication, structural loads, deformation in service, and possible wedging action by corrosion products, conditions are potentially available for the mechanism of caustic stress corrosion cracking (CSCC). Since LMFBR components are fabricated from Types 304 and 316 stainless steels which have been found to be susceptible to CSCC, it was therefore considered necessary to establish the threshold of CSCC so that the components could be processed under conditions avoiding CSCC. The materials used in the testing program included heats of Types 304 and 316 stainless steel, Inconel 600 and 718, hardfacing deposits of Stellite 6 and 156, and three special wear-resistant, carbide-type materials. The analysis of these materials is tabulated

  20. Nuclear waste: Quarterly report on DOE's nuclear waste program as of September 30, 1986

    International Nuclear Information System (INIS)

    This fact sheet provides the status of the Department of Energy's nuclear waste program activities for the quarter ending September 1986. The activities include (1) the President's approval of potential first repository sites in Nevada, Texas, and Washington for detailed studies; (2) a DOE announcement of an indefinite postponement of any site-specific work on a second repository; (3) unresolved pending court cases concerning nuclear waste and nine new actions initiated against DOE; and (4) the collection of over $84.6 million in fees and investment income and obligations of about $144 million for program activities. The fund balance as of September 1986 was about $1.4 billion

  1. Internal Mainland Nuclear Power Liquid Waste Treatment Technology

    Institute of Scientific and Technical Information of China (English)

    YOU; Xin-feng; ZHANG; Zhen-tao; ZHENG; Wen-jun; WANG; Lei; YANG; Lin-yue; HUA; Xiao-hui; ZHENG; Yu; YANG; Yong-gang; WU; Yan

    2013-01-01

    Taohuajiang power station is the first internal mainland nuclear power station,and it adopts AP1000nuclear technology belongs to the Westinghouse Electric Corporation.To ensure the safety of the environment around the station and satisfy the radio liquid waste discharge standards,our team has researched the liquid waste treatment technology for the internal mainland nuclear power plant.According

  2. Nuclear waste treatment using Iranian natural zeolites

    International Nuclear Information System (INIS)

    Full text: The zeolite researches in Iran is a relatively new subject which has started about 10 years ago. The motivation for this scientific and interesting field was provided after discovery of significant deposits of natural zeolites in different regions of Iran as well as further developments of research institutions and the national concern to environmental protection especially the wastewater clean-up in point of view of recycling of such waste water to compensate some needs to water in other utilizations. This paper intends to review and describes scientific researches which have done on using zeolites in the field of nuclear waste treatment in Iran to introduce the potential resources to the world in more details. Zeolite tuffs are widely distributed in huge deposits in different regions of Iran. So far, the clinoptilolite tuffs are the most abundant natural zeolite which exist with zeolite content of 65%- 95%. Nowadays several different types of Iranian natural zeolites are characterized in point of view of chemical composition, type of structure, chemical, thermal, and radiation resistance using different instrumental and classical methods such as; X-ray diffraction (XRD), X-ray fluoresce (XRF), thermal methods of analysis (TA), scanning electron microscopy (SEM), analytical chemistry and radioanalytical methods as well as different ion-exchange techniques (e.g.3-7). The ability of Iranian natural clinoptilolite for removal of some fission products from nuclear wastewaters have been investigated. The selectivity of all investigated zeolites toward radiocesium and radiostrontium have been promising (e.g. 8-10). The successful synthesize of P zeolite from Iranian clinoptilolite-reach tuffs under different conditions were performed. The compatibility of zeolites with glass and cement matrices, for final disposal of radwaste, as well as their selectivity toward most dangerous heat generating radionuclides (e.g. 137Cs and 90Sr) is very important in using them

  3. Nuclear waste: Monitored retrievable storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    The primary purpose of a monitored retrievable storage facility would be to receive and prepare spent nuclear fuel from commercial reactors for disposal in a geologic repository. The Department of Energy has concluded that an MRS facility located in Tennessee would significantly improve the performance of the nuclear waste management system and has identified three sites that it considered the most favorable-the cancelled Clinch River Breeder Reactor Project site, a site on Oak Ridge Reservation, and the site of the Tennessee Valley Authority's cancelled nuclear power plant. This fact sheet described Tennessee's role in the development of the MRS, potential advantages and disadvantages of MRS, and state and local impacts of siting an MRS facility in Tennessee

  4. Public participation in nuclear waste management

    International Nuclear Information System (INIS)

    The recent report of the Interagency Review Group (IRG) on Nuclear Waste Management formalized what has become increasingly clear in recent years: public participation in nuclear waste management decisions is a fact of life and will be more emphasized in the future than in the past. The purpose of this paper is to discuss, and stimulate discussion, of major issues which must be considered before attempting to design and implement a program to encourage public participation in this complex and sensitive area. Public participation is a term with many possible meanings. The term is used here to stand for a very wide range of activities including: providing information about programs and intended actions, seeking advice or permission from state or local officials, conducting public meetings to announce plans and receive reactions, conducting hearings, establishing consultative panels of outside experts or special interest group members, and even conducting surveys of public opinion and concern. This paper is not a proposal or a set of specific recommendations, but a stimulus to thought and discussion. It was prepared with DOE's role in waste management in mind, and benefits from the authors' opportunity to observe the public participation process in this topic area to data. The paper is organized into four sections that take account of (1) past participation efforts, (2) why public participation is necessary and what might be gained by it, (3) considerations in designing a participation program, and (4) major principles involved in conducting a public participation program, including a brief review of participation procedures

  5. Bored tunnel storage of nuclear waste

    International Nuclear Information System (INIS)

    Contrary to the current emphasis on deep geologic disposal of high-level nuclear waste, simple bored tunnels offer many advantages. Much lower cost is important in this period of severe budget crisis. Recoverability is feasible from a tunnel in a mountain, but dubious from a flooded mine 3000-ft (914.4-m) deep. It is quite possible that the world will need the breeder energy cycle urgently 200 years from now. In the writer's opinion, it would be a profound mistake for our generation to make so much fertile and fissile uranium fuel unavailable for future generations. Storage conditions in a near-surface repository are much better than in a deep repository, because the temperature can be kept down, pressure will be atmospheric instead of potentially 1200 psi (8.2738 MPa), and flooding will not occur. The ''hydrothermal'' conditions are thus completely avoided. Accordingly, endless studies of hydrogeology, water pathway times, waste-host rock interactions, and the like are unnecessary, and the time for action is much shorter. In addition, spent (partly used) fuel also contains palladium and rhodium in quantities that may be important in the future. ''Spent'' fuel is renamed ''reusable uranium fuel'' (RUF). Use of this simple bored tunnel storage system should be demonstrated as soon as possible to persuade Congress to change direction on nuclear waste disposal away from deep-mined repositories

  6. Transient thermal response in nuclear waste repositories

    International Nuclear Information System (INIS)

    In this paper, it is shown that a previously reported non-linear, one-dimensional, theoretical approximation simplifies - from a computational point of view - the calculation of the time-decay temperature field in nuclear waste repositories (NWR). This conclusion has been reached after solving, by using the control volume numerical method, the full three dimensional, transient, non-linear heat diffusion equation. The transient thermal field in a rock salt repository, is analytically solved and numerically predicted, along 100 years, after the disposal of a high-level waste (HLW). The nuclear waste, with a half-life of 32.9 years, releases an exponentially time dependent heat flux with 12 W m-2 as the initial thermal load. Two cases are studied, in the first one it is assumed that the conductivity (k) and the volumetric heat capacity ρcp of the host rock (diffusion domain) remain constant (linear case), whereas in the second one, a more realistic situation is analysed. In this last case, the conductivity of the rock salt varies as a function of the temperature field and the product ρ x cp remains constant (non-linear case). In order to observe the effect of the salt conductivity (constant or variable) on the repository temperature distribution, a comparison of both cases is performed. It is concluded, that the theoretical model, which provides an analytical solution of the thermal fields may be a powerful low cost method for design purposes. (orig.)

  7. Waste Stream Analyses for Nuclear Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    N. R. Soelberg

    2010-08-01

    A high-level study was performed in Fiscal Year 2009 for the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) Advanced Fuel Cycle Initiative (AFCI) to provide information for a range of nuclear fuel cycle options (Wigeland 2009). At that time, some fuel cycle options could not be adequately evaluated since they were not well defined and lacked sufficient information. As a result, five families of these fuel cycle options are being studied during Fiscal Year 2010 by the Systems Analysis Campaign for the DOE NE Fuel Cycle Research and Development (FCRD) program. The quality and completeness of data available to date for the fuel cycle options is insufficient to perform quantitative radioactive waste analyses using recommended metrics. This study has been limited thus far to qualitative analyses of waste streams from the candidate fuel cycle options, because quantitative data for wastes from the front end, fuel fabrication, reactor core structure, and used fuel for these options is generally not yet available.

  8. Microorganisms in nuclear waste disposal. Part I

    International Nuclear Information System (INIS)

    This article gives information about the structure of the multi-author review. Block I contains a general introduction on the possible effects of microorganisms in nuclear waste disposal, a summary of basic information on how a repository is planned and constructed, and on the type and composition of waste deposited. In Block II some important basic topics of microbial ecology relevant to repository conditions are presented; subsoil microbiology, adhesion to surfaces, starvation and survival in oligotrophic environments, and bioenergetics. Block III reviews some examples of general metabolic behaviour relevant to microrganisms in nuclear waste disposal such as tolerance to heavy metals, transformation of elements or gas formation. In block IV experimental data are presented which have been obtained in applied research directed to specific questions emerging from safety assessments, such as examination of microbial population in future repository sites, degradation of bitumen or sorption of nuclides. In the final block V, an attempt is made via modelling and computer simulation to foresee the behaviour of a complex system 'repository' in the future, on the basis of our present knowledge. (author) 1 fig

  9. Scientific Solutions to Nuclear Waste Environmental Challenges

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Bradley R.

    2014-01-30

    The Hidden Cost of Nuclear Weapons The Cold War arms race drove an intense plutonium production program in the U.S. This campaign produced approximately 100 tons of plutonium over 40 years. The epicenter of plutonium production in the United States was the Hanford site, a 586 square mile reservation owned by the Department of Energy and located on the Colombia River in Southeastern Washington. Plutonium synthesis relied on nuclear reactors to convert uranium to plutonium within the reactor fuel rods. After a sufficient amount of conversion occurred, the rods were removed from the reactor and allowed to cool. They were then dissolved in an acid bath and chemically processed to separate and purify plutonium from the rest of the constituents in the used reactor fuel. The acidic waste was then neutralized using sodium hydroxide and the resulting mixture of liquids and precipitates (small insoluble particles) was stored in huge underground waste tanks. The byproducts of the U.S. plutonium production campaign include over 53 million gallons of high-level radioactive waste stored in 177 large underground tanks at Hanford and another 34 million gallons stored at the Savannah River Site in South Carolina. This legacy nuclear waste represents one of the largest environmental clean-up challenges facing the world today. The nuclear waste in the Hanford tanks is a mixture of liquids and precipitates that have settled into sludge. Some of these tanks are now over 60 years old and a small number of them are leaking radioactive waste into the ground and contaminating the environment. The solution to this nuclear waste challenge is to convert the mixture of solids and liquids into a durable material that won't disperse into the environment and create hazards to the biosphere. What makes this difficult is the fact that the radioactive half-lives of some of the radionuclides in the waste are thousands to millions of years long. (The half-life of a radioactive substance is the

  10. Photofission tomography of nuclear waste packages

    International Nuclear Information System (INIS)

    Quantifying the mass of actinides in large concrete waste packages using non-destructive methods is a major challenge for the management and the storage of packages in appropriate facilities. Since the beginning of 1990s, our team in CEA has been working on the development of a method based on interrogation with high-energy photons to assay actinides in large concrete waste package. The method consists in using photons of high energy (bremsstrahlung radiation) in order to induce photofission reactions on the fissile nuclei present in the wastes. The measurement of the delayed neutrons emitted by fission products allows us to quantify the actinides present in the wastes. The accuracy of the method can be deeply improved by carrying out a tomography, i.e. computing the three-dimensional spatial distribution of the actinide mass inside the nuclear waste package. This paper presents the first experimental results of a tomography carried out on a 1.2 t real concrete waste package. Measurements associated with reconstruction algorithms and Monte Carlo simulations have allowed to locate an equivalent mass of 690 mg of uranium 238 centered in a disc of 20-25 cm of diameter at 75 cm height. These measurements have been performed in the SAPHIR irradiation facility at CEA/Saclay. This facility houses a pulsed linear electron accelerator (energy range from 15 to 30 MeV, pulse duration of 2.5 μs, peak current of 130 mA). The located mass has been subsequently confirmed by a destructive analysis of the package

  11. Public reactions to nuclear waste: Citizens' views of repository siting

    International Nuclear Information System (INIS)

    This book presents revised and updated papers from a panel of social scientists, at the 1989 AAAS meetings, that examined the public's reactions to nuclear waste disposal and the repository siting process. The papers report the results of original empirical research on citizens' views of nuclear waste repository siting. Topics covered include the following: content analysis of public testimony; sources of public concern about nuclear waste disposal in Texas agricultural communities; local attitudes toward high-level waste repository at Hanford; perceived risk and attitudes toward nuclear wastes; attitudes of Nevada urban residents toward a nuclear waste repository; attitudes of rural community residents toward a nuclear waste respository. An introductory chapter provides background and context, and a concluding chapter summarizes the implications of the reports. Two additional chapters cover important features of high-level waste disposal: long term trends in public attitudes toward nuclear energy and nuclear waste policy and assessment of the effects on the Los Vegas convention business if a high-level nuclear waste depository were sited in Nevada

  12. A systems view of the nuclear waste dilemma

    OpenAIRE

    Bonnett, Timothy Charles

    1991-01-01

    The nuclear waste problem is defined and analyzed from a systems engineering viewpoint. Problem magnitude and systems context are discussed. Requirements for a waste repository are presented and the current progress of the repository is noted. The Department of Energy's waste disposal system including repository site selection, monitored retrievable storage facility, and waste transportation system is analyzed. A description of nuclear fuel reprocessing is given. The potential benefits ...

  13. Nuclear Waste Treatment Program: Annual report for FY 1986

    International Nuclear Information System (INIS)

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

  14. Predicting the Lifetimes of Nuclear Waste Containers

    Science.gov (United States)

    King, Fraser

    2014-03-01

    As for many aspects of the disposal of nuclear waste, the greatest challenge we have in the study of container materials is the prediction of the long-term performance over periods of tens to hundreds of thousands of years. Various methods have been used for predicting the lifetime of containers for the disposal of high-level waste or spent fuel in deep geological repositories. Both mechanical and corrosion-related failure mechanisms need to be considered, although until recently the interactions of mechanical and corrosion degradation modes have not been considered in detail. Failure from mechanical degradation modes has tended to be treated through suitable container design. In comparison, the inevitable loss of container integrity due to corrosion has been treated by developing specific corrosion models. The most important aspect, however, is to be able to justify the long-term predictions by demonstrating a mechanistic understanding of the various degradation modes.

  15. Geochemical immobilisation of nuclear waste; the SYNROC proposal

    International Nuclear Information System (INIS)

    Glass is not the best solid to which nuclear waste should be converted. Geochemical criteria, drawing on the experience with natural minerals in natural environments can be used to indicate which stable cristalline compounds should be selected for the immobilisation of nuclear waste. Disposal of nuclear waste should use several independent barriers to prevent its return to the biosphere. This multi-barrier concept, and the optimalization of the individual steps are discussed. (Auth.)

  16. nuclear fuel strategies and environmental geophysics in waste management

    International Nuclear Information System (INIS)

    Geophysicists contribute their knowledge to the solution of many societal problems-seismic and volcanic risk, exploration and mapping to name a few. A field of special demand which has recently grown important is nuclear waste disposal. This article summarizes the background of nuclear waste disposal problem and how geophysicists are contributing to its solution and what kind of geophysical techniques are used to solve the nuclear waste disposal problem

  17. JYT - Publicly financed nuclear waste management research programme

    International Nuclear Information System (INIS)

    The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

  18. Science, society, and America's nuclear waste: Unit 2, Ionizing radiation

    International Nuclear Information System (INIS)

    ''Science, Society and America's Nuclear Waste'' is a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  19. FURTHER DEVELOPMENT OF MODIFIED MONOSODIUM TITANATE, AN IMPROVED SORBENT FOR PRETREATMENT OF HIGH LEVEL NUCLEAR WASTE AT THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, K.; Hobbs, D.; Fondeur, F.; Fink, S.

    2011-01-12

    High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove Cs-137, Sr-90, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at SRS include caustic side solvent extraction, for Cs-137 removal, and sorption of Sr-90 and alpha-emitting radionuclides onto monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes Pu-238, Pu-239, and Pu-240. This paper describes recent results from the development of an improved titanate material that exhibits increased removal kinetics and effective capacity for Sr-90 and alpha-emitting radionuclides compared to the baseline MST material.

  20. Nuclear waste dump no threat, says NAS

    International Nuclear Information System (INIS)

    This article is a review of the National Academy of Sciences report on the efforts to site a low-level waste repository in the Mohave Desert. This report states that there would be little threat to ground water or the Colorado River, but critics charge that the advisory group, with close ties to the nuclear industry, set forth some findings that support arguments against the project. Leakage pathways from the containers to the Colorado River are reviewed, and it is concluded that even if all the leakage of plutonium reached the river, the impact would be minimal

  1. Citizen participation in nuclear waste repository siting

    International Nuclear Information System (INIS)

    Citizen participation, which is both legally and morally mandated, must be an essential part of the nuclear waste repository siting process. The experience from siting other large-scale development projects suggests that a repository is unlikely to be sited without an effective citizen participation program to illustrate how the program can be based upon past lessons and principles derived from appropriate social science theory. To be effective, it must be based on open and mutally respectful communication between repository developers and local citizens and be guided by a trained and experienced community development professional

  2. Nuclear wastes management; Gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is the proceedings of the debate that took place at the French Senate on April 13, 2005 about the long-term French policy of radioactive wastes management. The different points tackled during the debate concern: the 3 axes of research of the 1991 law, the public acceptance about the implementation of repositories, the regional economic impact, the cost and financing, the lack of experience feedback, the reversibility or irreversibility of the storage, the share of nuclear energy in the sustainable development policy, the European Pressurized Reactor (EPR) project, the privatization of Electricite de France (EdF) etc. (J.S.)

  3. Curriculum and instruction in nuclear waste disposal

    International Nuclear Information System (INIS)

    Curriculum and instruction in nuclear waste disposal is part of the larger problem of curriculum and instruction in science. At a time when science and technological literacy is crucial to the nation's economic future fewer students are electing to take needed courses in science that might promote such literacy. The problem is directly related to what science teachers teach and how they teach it. Science content that is more relevant and interesting to students must be a part of the curriculum. Science instruction must allow students to be actively involved in investigating or playing the game of science

  4. Thermodynamic tables for nuclear waste isolation

    International Nuclear Information System (INIS)

    Tables of consistent thermodynamic property values for nuclear waste isolation are given. The tables include critically assessed values for Gibbs energy of formation, enthalpy of formation, entropy and heat capacity for minerals; solids; aqueous ions; ion pairs and complex ions of selected actinide and fission decay products at 25 degree C and zero ionic strength. These intrinsic data are used to calculate equilibrium constants and standard potentials which are compared with typical experimental measurements and other work. Recommendations for additional research are given. 13 figs., 23 tabs

  5. Radioactive Waste as an Argument against Nuclear Energy

    International Nuclear Information System (INIS)

    The issue of safe radioactive waste is commonly regarded as the Achilles Heel of nuclear energy production. To add strength to the 'unsolved' waste problem as an argument in favour of abandoning nuclear energy production, anti-nuclear groups systematically seek to discredit waste management projects and stand in the way of progress in this field. The paradox in this situation is that it is exactly in the field of waste management that nuclear energy production allows ecologically sound procedures to be followed. (author)

  6. See for yourself! : Enrolling the public in nuclear waste management

    OpenAIRE

    Soneryd, Linda; Johansson, Hanna Sofia

    2010-01-01

    This paper explores exhibitions of nuclear waste facilities and their use as a tool for enrolling the public in the Swedish nuclear waste programme. We argue that the planning process for the final disposal of nuclear waste has dual purposes. On one hand, the consultation meetings provide opportunities for dialogue among a broader set of actors – at least to some extent. The goal of the exhibitions, on the other hand, is to highlight the state of nuclear waste management today and the future ...

  7. Nuclear waste: Quarterly report on DOE's nuclear waste program as of June 30, 1986

    International Nuclear Information System (INIS)

    The Department of Energy's status of nuclear waste program activities for the quarter ending June 30, 1986 included (1) final environmental assessments for first repository sites and recommendations for sites in Nevada, Texas, and Washington for site characterization; (2) postponement of any site-specific work on a second repository; and (3) collection of over $166 million in fees and investment income

  8. Informing future societies about nuclear waste repositories

    International Nuclear Information System (INIS)

    In 1990 a working group of the NKS (the Nordic nuclear safety program) was formed and give the task of established a basis for a common Nordic view of the need for information conservation for nuclear waste repositories. The Group investigated what tipy of information should be conserved; in what form the information should be kept; the quality of the information; and the problems of future retrieval of information, including retrieval after very long periods of time. Topics covered include the following: scientific aspects including social context of scientific solutions; information management; systems for conservation and retrieval of information including the problems of prediction; archives, markers, archives vs. markers, and continuing processes in society; Archive media including paper documents, microfilm, digital media, media lifetimes; and finally conclusions and recommendations

  9. Quantum caustics in the Gaussian slit experiment

    OpenAIRE

    Horie, K.; Miyazaki, H.; Tsutsui, I.; Tanimura, S.

    1998-01-01

    We study classical and quantum caustics for system with quadratic Lagrangian. Gaussian slit experiment is examined and it is pointed out that the focusing around caustics is stabilized against initial momentum fluctuations by quantum effect.

  10. Radioactive waste management and advanced nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    In 2007 ENEA's Department of Nuclear Fusion and Fission, and Related Technologies acted according to national policy and the role assigned to ENEA FPN by Law 257/2003 regarding radioactive waste management and advanced nuclear fuel cycle technologies

  11. Nuclear waste in the Pacific: perceptions of the risks

    International Nuclear Information System (INIS)

    This dissertation examines the problem of the disposal of high-level nuclear waste in the Pacific region. There is a consensus of scientific opinion that the technical difficulties in waste disposal can be overcome. The most acceptable solution seems to be the multi-barrier approach for deep land-based geologic disposal. A questionnaire survey on the perception of nuclear and other hazards, conducted with student populations in Japan and Australia, and a survey of reporting of nuclear events in Pacific newspapers over the period 1946 to the 1980s, reveal that the image of nuclear weapons dominates public views on the risks associated with waste disposal in Australia, Japan, and the Pacific Islands. The problem of finding a suitable site for a nuclear waste disposal facility is to a large extent political. The capacity of anti-nuclear groups to influence waste disposal policies in Australia, Japan, and the Pacific Islands is examined. Current public attitudes toward nuclear waste disposal will delay the further development of activities connected with the nuclear fuel cycle, but this may change over time if the connection between commercial nuclear power and nuclear weapons can be severed more effectively. The most urgent problem in the region is the waste from the ambitious nuclear power programs of Japan, South Korea, and Taiwan

  12. Nuclear waste repository in basalt: a design description

    International Nuclear Information System (INIS)

    The conceptual design of a nuclear waste repository in basalt is described. Nuclear waste packages are placed in holes drilled into the floor of tunnels at a depth of 3700 ft. About 100 miles of tunnels are required to receive 35,000 packages. Five shafts bring waste packages, ventilation air, excavated rock, personnel, material, and services to and from the subsurface. The most important surface facility is the waste handling building, located over the waste handling shaft, where waste is received and packaged for storage. Two independent ventilation systems are provided to avoid potential contamination of spaces that do not contain nuclear waste. Because of the high temperatures at depth, an elaborate air chilling system is provided. Because the waste packages deliver a considerable amount of heat energy to the rock mass, particular attention is paid to heat transfer and thermal stress studies. 3 references, 31 figures, 3 tables

  13. Nuclear waste: beyond Faust and fate

    International Nuclear Information System (INIS)

    Regarding development of the nuclear industry and the resulting turmoil over generation of nuclear wastes, Dr. Maxey presents as a fundamental bioethical principle for organizing evidence and dealing with conflicting opinions the following formulation: social justice requires an equitable mangement of potential hazards that might have harmful health effects and unjustifiable social consequences. By equitable management she means: (1) comprehensively informing policymakers about the broad spectrum of hazards; (2) make comparisons of actual costs to reduce the effects; and (3) only then make policies and set standards that will get the most public protection out of a finite amount of money. Translating this principle into public policy is no easy task, since opponents have developed several arguments that appeal to nonscientific moral and ethical premises. Briefly, these statements can be summarized as: (a) indefinite delay of high-level waste disposal facilities is regarded as morally preferable to a policy of implementing one of several currently available options, and (b) it is claimed that involuntary risks of radiation exposure imposed on present and unconsulted future generations violate ethical principles of social justice and equity. Dr. Maxey uses most of the article in countering these premises and finally suggests the following bioethical principle for guidance: any involuntary risks imposed by social policies for radiation protection must be congruent with, must not be in excess of, and may be reasonably less than, those involuntary risks imposed by the naturally occurring toxic elements and harmful effects from our natural environment

  14. Nuclear waste - where to go?; Atommuell - wohin?

    Energy Technology Data Exchange (ETDEWEB)

    Dornsiepen, Ulrich

    2015-07-01

    The question of the final di9sposal of nuclear waste is a problem of international importance. The solution of the problem is of increasing urgency; the discussion is controversial and implies a lot of emotions. In Germany there is consensus that the nuclear wastes have to be disposed within the country in deep geological formations. This kind of final disposal is predominantly a geological problem and has to be solved from the geological point of view. The geologist Ulrich Dornsiepen presents the problems of the final disposal in an objective way without ideology and generally understandable. Such a presentation is necessary since the public information and participation is demanded but the open geological questions and their scientific solutions are never explained for the public. [German] Die Frage der endgueltigen Lagerung von Atommuell ist ein Problem von nationaler Tragweite, dessen Loesung immer dringender wird, bisher aber sehr kontrovers diskutiert wird und mit vielen Emotionen verknuepft ist. Es besteht in Deutschland ein Konsens, diese Abfaelle innerhalb der Landesgrenzen dauerhaft in tief liegenden Gesteinsschichten abzulagern. Diese Art der Endlagerung ist aber in erster Linie ein geologisches Problem und so auch nur von geologischer Seite her zu loesen. Daher stellt der Geologe Ulrich Dornsiepen die Problematik der Endlagerung objektiv, ideologiefrei und allgemein verstaendlich dar. Ein solches Hoerbuch ist dringend noetig, da zwar die Information und Beteiligung breiter, betroffener Bevoelkerungsteile eingefordert, aber niemals versucht wird, die offenen geologischen Fragen und ihre wissenschaftliche Loesung verstaendlich zu machen.

  15. Spectral Caustics in Attosecond Science

    Directory of Open Access Journals (Sweden)

    Dudovich N.

    2013-03-01

    Full Text Available A unique type of singularity common in wave phenomena, known as caustics, links processes observed in many different branches of physics [1]. We investigate the role of caustics in attosecond science and in particular the physical process behind high harmonic generation. By exploiting singularities of the three-step model that describes HHG, we can manipulate and enhance specific features in the emitted harmonic spectrum. This new level of control holds promises in both scientific and technological aspects of attosecond science, and provides a deeper insight into the basic mechanism underlying the high harmonic generation process.

  16. Nuclear Waste Incineration- The Case for ADS

    International Nuclear Information System (INIS)

    In this paper we consider some key issues associated with nuclear waste incineration and how these issues can be addressed with the euse of accelerator driven systems (ADS). The first issue is related to the safety and control of reactor systems. The control of critical reactor systems is determined mainly by delayed neutrons (which do not appear immediately in the fission process) and their associated reactivity. When critical reactor systems are used to burn nuclear waste, this delayed neutron fraction decreases making the control of the system significantly more difficult. For sub-critical accelerator driven systems, it is shown that the spallation neutrons (which are independent of the sub-critical assembly), can be considered as a very much enhanced delayed neutron fraction. As a result, accelerator driven sub-critical systems will react more benignly and can cope with greater reactivity excursions than critical reactor systems. This is especially true for fast neutron systems. The second issue we address is how much waste we may have to deal with and whether ADSs can cope. At the present level of global nuclear power production, about 10''4 tons of spent fuel are being produced each year containing approximately 90 tons Pu, 6 tons Np, 2 tons Am, and 0.5 tons Cm. Since fissioning 1 to Pu will result in an energy release of approximately 1 GWey (i. e. the energy produced by one large reactor in one year), a large number of ADSs will be required to burn all the plutonium and minor actinides. The scale of this problem can be significantly reduced by recycling the Pu back into MOX or TMOX fueled PWRs. A detailed analysis of this problem is presented. Finally, we consider some conceptual designs for an accelerator driven waste incinerator with a view to starting relatively small scale experiments. In principle, one should be able to design a system in which at any time less than one critical mass (e. g. of Pu) is present thereby avoiding the possibility of

  17. Liquid centrifugation for nuclear waste partitioning

    Energy Technology Data Exchange (ETDEWEB)

    Bowman, C.D.

    1992-03-11

    The performance of liquid centrifugation for nuclear waste partitioning is examined for the Accelerator Transmutation of Waste Program currently under study at the Los Alamos National Laboratory. Centrifugation might have application for the separation of the LiF-BeF{sub 2} salt from heavier radioactive materials fission product and actinides in the separation of fission product from actinides, in the isotope separation of fission-product cesium before transmutation of the {sup 137}Cs and {sup 135}Cs, and in the removal of spallation product from the liquid lead target. It is found that useful chemical separations should be possible using existing materials for the centrifuge construction for all four cases with the actinide fraction in fission product perhaps as low as 1 part in 10{sup 7} and the fraction of {sup 137}CS in {sup 133}Cs being as low as a few parts in 10{sup 5}. A centrifuge cascade has the advantage that it can be assembled and operated as a completely closed system without a waste stream except that associated with maintenance or replacement of centrifuge components.

  18. Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

  19. Management of abnormal radioactive wastes at nuclear power plants

    International Nuclear Information System (INIS)

    As with any other industrial activity, a certain level of risk is associated with the operation of nuclear power plants and other nuclear facilities. That is, on occasions nuclear power plants or nuclear facilities may operate under conditions which were not specifically anticipated during the design and construction of the plant. These abnormal conditions and situations may cause the production of abnormal waste, which can differ in character or quantity from waste produced during normal routine operation of nuclear facilities. Abnormal waste can also occur during decontamination programmes, replacement of a reactor component, de-sludging of storage ponds, etc. The management of such kinds of waste involves the need to evaluate existing waste management systems in order to determine how abnormal wastes should best be handled and processed. There are no known publications on this subject, and the IAEA believes that the development and exchange of such information among its Member States would be useful for specialists working in the waste management area. The main objective of this report is to review existing waste management practices which can be applied to abnormal waste and provide assistance in the selection of appropriate technologies and processes that can be used when abnormal situations occur. Naturally, the subject of abnormal waste is complex and this report can only be considered as a guide for the management of abnormal waste. Refs, figs and tabs.

  20. For Sale: Nuclear Waste Sites--Anyone Buying?

    Science.gov (United States)

    Hancock, Don

    1992-01-01

    Explores why the United States Nuclear Waste Program has been unable to find a volunteer state to host either a nuclear waste repository or monitored retrieval storage facility. Discusses the Department of Energy's plans for Nevada's Yucca Mountain as a repository and state and tribal responses to the plan. (21 references) (MCO)

  1. Policy conflicts in the process for siting nuclear waste repositories

    International Nuclear Information System (INIS)

    This article reviews the sources of nuclear waste policy conflicts over the past five years and the reasons for congressional action. It also attempts to assess the prospects for future controversies and to extract lessons for public policy. This paper focuses mainly on attempts in the United States to manage and dispose of the intensely radioactive spent fuel from civilian reactors and reprocessed high-level waste from nuclear weapons production. Both types of waste are referred to as high-level waste, or HLW. Transuranic waste, which is not HLW but is radioactive waste contaminated with radionuclides heavier than uranium, is also discussed. The safe management of these wastes is an imperative regardless of the future of nuclear power

  2. How do social systems treat and dispose nuclear waste? : -A comparison of general and radioactive wastes -

    OpenAIRE

    YUASA, Yoichi||ユアサ, ヨウイチ

    2013-01-01

    All countries that have nuclear reactors are confronted with the problem of treating or disposing radioactive waste. What factors decide which countries are successful at radioactive waste management? We propose an assumption that the method a country selects for treating or disposing radioactive waste depends on the way social systems function. From the perspective of social systems, we will compare the disposal of general waste to the disposal of radioactive waste. The social system for gen...

  3. Caustic saving potentile in textile processing mills

    International Nuclear Information System (INIS)

    The textile processing industry of pakistan has great potential of improvement in resource consumption in various production processes. One major concern is the heavy usage of caustic soda (sodium hydroxide) especially during the mercerization process which incurs a significant cost to a textile processing mill. To reduce the unit fabric production cost and stay competitive, the industry need to minimize the caustic wastage and explore the caustic saving potential. This paper describe the detailed caustic consumption practices and saving potentials in woven textile sector based on the data base of 100 industries. Region wise caustic saving potential is also investigated . Three caustic conservation option including process improvement, reuse and recycling, and caustic recovery plants are discussed. Detailed technical and and financial requirements. saving potentials and paybacks of these options are provided. (author)

  4. Can alchemy solve the nuclear waste problem?

    International Nuclear Information System (INIS)

    One new technology being explored to deal with highly radioactive elements that remain dangerous for thousands of years is transmutation-a modern twist on the ancient idea of transforming one element into another. This modern version of transmutation is not a new concept: transmutation is the essence of nuclear reactions. The latest idea is to harness the process not to create an explosive chain reaction, as in a nuclear weapon, or even primarily to generate power, as in a nuclear power reactor, but to transform dangerous radionuclides into less harmful elements. Last year a Los Alamos team began looking into using a particle accelerator instead of a conventional nuclear reactor to drive the transmutation process. Accelerator transmutation is being pursued elsewhere as well. The Los Alamos project envisions using a linear accelerator to generate extremely high intensities of neutrons for transmutation. The most powerful medium-energy accelerator in the world is located at Los Alamos-the Meson Physics Facility. All major components have been demonstrated individually but have yet to be tested in an integrated unit; when built, these accelerators will produce very intense beams of fast-moving protons. The beams will be directed into heavy-metal targets of lead and bismuth, where each proton will knock-out more than 50 neutrons from the target atoms. The scheme calls for the target to be surrounded by a moderator of heavy water, which would slow the neutrons so they could more easily be captured by the waste products to be transmuted-the lightweight fission products and the heavy actinides. These substances would be carried in a molten salt solution in a separate loop through the moderator. Circulation of both the moderator and the salt loop would dissipate the heat generated by the fission process in what is essentially a subcritical reactor. The paper discusses the advantages of this process and summarizes related research

  5. Nuclear waste management. Quarterly progress report, April-June 1981

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A.

    1981-09-01

    Reports and summaries are presented for the following: high-level waste process development; alternative waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; and analysis of spent fuel policy implementation.

  6. Radioactive waste management perspectives in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Waste Technology Development Centre (WasTeC) has been mandated to carry out radioactive waste management activities since 1984. The main objective of WasTeC is to deal with radioactive waste in a manner that protects health and the environment now and in the future, without imposing undue burdens on the future generations. This centre provides services for waste generators within Nuclear Malaysia and also for external waste generators. Services provided include transportation of radioactive waste, decontamination, treatment and storage. This paper will discuss on procedure for applying for services, responsibility of waste generator, responsibility of waste operator, need to comply with waste acceptance criteria and regulations related to management of radioactive waste. (Author)

  7. Helium behaviour in nuclear waste materials

    Energy Technology Data Exchange (ETDEWEB)

    Wiss, T.; Hiernaut, J.P.; Colle, J.Y.; Maugeri, E.; Raison, P.; Konings, R.; Rondinella, V.V. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, 76125 Karlsruhe (Germany); Roudil, D.; Deschanel, X.; Peuget, S. [Commissariat a l' Energie Atomique, Centre de VALRHO, B.P. 30207 Bagnols-sur-Ceze (France)

    2008-07-01

    Waste conditioning matrices like synthetic zirconolite (CaZrTi{sub 2}O{sub 7}) were fabricated and doped with either the short-lived alpha-emitters {sup 238}Pu or {sup 244}Cm, or with {sup 239}Pu to generate various amounts of helium and of alpha-damage. The samples were annealed in a Knudsen cell, and the helium desorption profiles interpreted in conjunction with parallel radiation damage and previous annealing behaviour studies. To understand the long term behaviour of spent nuclear fuel, UO{sub 2} samples doped with the alpha-emitters {sup 233}U, {sup 238}Pu have been investigated by transmission electron microscopy (TEM), by XRD and by thermal desorption spectroscopy. The release of helium has been explained by the recrystallization of amorphized zirconolite on one hand and partially during alpha-damage recovery in the case of the spent fuel. This study mostly highlights the correlation between restructuring of damaged materials and gas release.

  8. Radiation effects in ceramic nuclear waste forms

    International Nuclear Information System (INIS)

    This paper reports on alpha-decay event damage (a particle and recoil-nucleus) that results in atomic-scale disorder which causes changes in the molar volume, corrosion rate, stored energy, mechanical properties, and macrostructure of ceramics. These changes particularly of volume and corrosion rate, have critical implications for the long-term durability of nuclear waste forms, such as the polyphase. Ti-based ceramic Synroc. This paper reviews data on actinide-bearing (U and Th) phases of great age (>100 m.y.) found in nature and compares these results to observation on actinide-doped phases (Pu and Cm) of nearly equivalent α-decay doses. Of particular interest is evidence for annealing of radiation damage effects over geologic periods of time under ambient conditions

  9. Quality assurance considerations in nuclear waste management

    International Nuclear Information System (INIS)

    Proper use of quality assurance will provide the basis for an effective management control system for nuclear waste management programs. Control is essential for achieving successful programs free from costly losses and failures and for assuring the public and regulators that the environment and health and safety are being protected. The essence of quality assurance is the conscientious use of planned and systematic actions, based on selecting and applying appropriate requirements from an established quality assurance standard. Developing a quality assurance program consists of using knowledge of the technical and managerial aspects of a project to identify and evaluate risks of loss and failure and then to select appropriate quality assurance requirements that will minimize the risks. Those requirements are integrated into the project planning documents and are carried out as specific actions during the life of the project

  10. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    International Nuclear Information System (INIS)

    One critical aspect of any denuclearization of the Democratic People's Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for 'complete, verifiable and irreversible dismantlement,' or 'CVID.' It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times

  11. Environmental and waste disposal options in nuclear engineering curricula

    International Nuclear Information System (INIS)

    The strong national emphasis on waste and environmental issues has prompted increasing interest among nuclear engineering students in study options that will prepare them for careers in these areas. Student interest appears to focus principally on health physics, radioactive waste disposal, and environmental interactions with radionuclides. One motivation for this interest appears to be the growing national programs in environmental restoration and waste remediation that have produced fellowship support for nuclear engineering students as well as employment opportunities. Also, the recent National Academy of sciences study on nuclear engineering education specifically emphasized the importance of expanding nuclear engineering curricula and research programs to include a greater emphasis on radioactive waste and environmental issues. The North Carolina State University (NCSU) Department of Nuclear Engineering is attempting to respond to these needs through the development of course options that will allow students to acquire background in environmental subjects as a complement to the traditional nuclear engineering education

  12. Ice ages and nuclear waste disposal

    International Nuclear Information System (INIS)

    This report is an overview of Quaternary Ice Age and its potential consequences for nuclear waste disposal. Geological information on past climatic changes is shortly reviewed, based on the following records: geomorphological information, loessic deposits, deep-sea carbonate sediments, ice-core records, and continental calcite precipitates. Even though the present 'Great Ice Age' has lasted more that two million years, the present variation in cycles of about 100 000 years seems to have commenced only about 600 - 700 thousands years ago. According to the present understanding, southern Finland was during a major span of Weichsel free of continental ice sheet. However, the conditions may have been very cold, periglacial, when the continental ice sheet covered the Caledonian mountains and large areas of central Fennoscandia. The last glacial maximum of Weichsel glaciation was shorter than estimated earlier. Periglacial conditions are characterized by deep permafrost, reaching even the depth of nuclear waste disposal. Calculations of the advancement of permafrost indicate that the permafrost-front may reach the depth of about 500 meters in less than 10 000 years. The crust beneath the continental ice cover depresses, and rebounds when the ice sheet retreats. During the most intensive vertical movement of the crust, some crush zones may be activated and bedrock movements may take place along them. Due to the growth of ice sheets, ocean water table also depresses during glacial maximum, thus changing hydrogeological conditions in non-glaciated terrains. Increase in global ice volume is manifested in the stable oxygen and hydrogen isotope ratios. Based on isotope signals, as well other hydrogeochemical interpretation methods, indications of the earlier glaciations have been recognized in present groundwaters. (orig.)

  13. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    An overview is presented of the status of the research and development program, under rsponsibility of the Atomic Energy of Canada Limited (AECL), for assessing the concept of nuclear fuel waste disposal deep in plutonic rock of the Canadian Shield. A passive multi-barrier concept has been adopted for disposal that combines the containment provided by the structural, hydraulic and geochemical characteristics of the rock mass with a series of engineered barriers. The conceptual disposal vault consists of an array of disposal rooms excavated in plutonic rock at a depth between 500 and 1000 m. Prior to disposal, the waste would be placed in cylindrical containers surrounded by a buffer, which is a mixture of bentonite cla and sand. The rooms would be backfilled with mixture of clay, and crushed granite or san. Bulkheads would seal the entrances. Closure would be achieved by backfilling the access tunnels in the same manner as the rooms and than backfilling the shafts with compacted clay and crushed granite separated by a series of supporting bulkheads. Very preliminary results from the case study indicate that the good rock provides the most effective barrier to movement of radionuclides to the surface. The most significant pathways through the geosphere involve diffusion through the good rock to the major fracture intersecting the vault, convection upward along the fracture, and discharge either at topographic lows or through a domestic water supply well used by the critical group. Long-lived non-sorbing radionuclides, available in the gaps between the fuel pellets and the fuel cladding or at the grain boundaries, contribute most to the radiological dose. With appropriate constraints on the location of the waste packages relative to the major fracture zones, radiological risk is expected to satisfy the regulatory criteria. (H.W.) 5 figs

  14. Science, society, and America's nuclear waste: Unit 4, The waste management system

    International Nuclear Information System (INIS)

    This is unit 4 (The Waste Management System) in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  15. Science, society, and America's nuclear waste: Unit 4, The waste management system

    International Nuclear Information System (INIS)

    This is the teachers guide to unit 4, (The Waste Management System), of a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  16. Overview of the NRC nuclear waste management program

    International Nuclear Information System (INIS)

    The NRC has firmly established waste management as a high-priority effort and has made the commitment to act rapidly and methodically to establish a sound regulatory base for licensing waste management activities. We believe the priorities for NRC work in waste management are consistent with the needs of the overall national waste management program. Present licensing procedures and criteria are adequate for the short term, and priority attention is being given to the longer term, when the quantities of waste to be managed will be greater and licensing demands will increase. Recognizing that its decision will affect industry, other governmental jurisdictions, private interest groups, and the public at large, NRC has encouraged and will continue to encourage their participation in planning our program. We also recognize that the problems of nuclear waste management are international in scope. Many waste management problems (e.g., potential for contamination of oceans and atmosphere, need for isolation of some wastes for longer periods than governments and political boundaries have remained stable in the past), require a set of internationally acceptable and accepted solutions. The wastes from the U.S. nuclear industry will account for only about one third of the nuclear waste generated in the world. Therefore, we propose to cooperate and where appropriate take the lead in establishing acceptable worldwide policies, standards and procedures for handling nuclear wastes

  17. Annual Report 2014 / Institute for Nuclear Waste Disposal. (KIT Scientific Reports ; 7709)

    OpenAIRE

    Geckeis, Horst; ALTMAIER, Marcus; Fanghänel, Susanne

    2015-01-01

    Institut für Nukleare Entsorgung, Nukleare Sicherheitsforschung, Radiochemie, Geochemie, Endlagerung Institute for Nuclear Waste Disposal, Nuclear Safety Research, Radiochemistry, Geochemistry, Waste Disposal

  18. Canister design for deep borehole disposal of nuclear waste

    OpenAIRE

    Hoag, Christopher Ian.

    2006-01-01

    The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories using currently available and proven oil, gas, and geothermal drilling technology. The canister is suitable for disposal of various waste forms, such as fuel assemblies and vitrified waste. The design addresses real and perceived hazards of transporting and placing high-level waste, in the form of spent reactor fuel, into a deep igneous rock env...

  19. Hydration process of nuclear-waste glass: an interim report

    International Nuclear Information System (INIS)

    Aging of simulated nuclear waste glass by contact with a controlled-temperature, humid atmosphere results in the formation of a double hydration layer penetrating the glass, as well as the formation of minerals on the glass surface. The hydration process can be described by Arrhenius behavior between 120 and 2400C. Results suggest that simulated aging reactions are necessary for demonstrating that nuclear waste forms can meet projected Nuclear Regulatory Commission regulations. 16 figures, 4 tables

  20. Micro-organisms and nuclear waste: a neglected problem

    International Nuclear Information System (INIS)

    The paper addresses the problem of bacteria in nuclear waste disposal. A description is given of how bacteria colonised the Three Mile Island Nuclear Reactor soon after meltdown, demonstrating the ability of some bacteria to operate under extreme conditions. Work is also described indicating that microbial corrosion of metal canisters can occur. Thus the author recommends that studies of nuclear waste disposal should take into account the interrelations between geology, geochemistry and microbiology. (U.K.)

  1. Nuclear-waste-package materials degradation modes and accelerated testing

    International Nuclear Information System (INIS)

    This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

  2. Effects on the environment of the dumping of nuclear wastes

    International Nuclear Information System (INIS)

    Nationally and internationally accepted procedures and technologies are available for the safe handling and disposal of radioactive wastes. Authorized waste disposal practices are designed to ensure that there will be no significant impacts on man and his environment. 'Dumping' of nuclear wastes may result in the elimination of one or more of the multibarriers of protection inherent in an effective radioactive waste management system, thereby increasing the risk of radiological exposure to man and his environment. Quantitative assessments of the degree of environmental contamination and of the resulting hazards to man depend on the specific conditions surrounding the 'uncontrolled disposal' of radioactive waste. These include the nature and activity level of the waste, the physical form of the waste, the package that the waste is contained in and the characteristics of the dumping site. Depending on the scenario envisaged, the consequences of 'uncontrolled disposal' could vary from being insignificant to a situation where there is a significant hazard to an exposed population group. International transactions involving nuclear wastes are taking place between countries on the basis of bilateral agreements and under strict regulatory supervision so that radioactive wastes are transferred safely from one controlled area to another. Such transactions may increase in the future with increased international co-operation in sharing common waste repositories. No evidence exists that confirms that transboundary dumping of radioactive waste has occurred. Investigation of alleged dumping of radioactive wastes by the International Atomic Energy Agency has revealed that the 'suspect wastes' did not contain radioactive material. 2 tabs

  3. Reference waste forms and packing material for the Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    The Lawrence Livermore National Laboratory (LLNL), Livermore, Calif., has been given the task of designing and verifying the performance of waste packages for the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. NNWSI is studying the suitability of the tuffaceous rocks at Yucca Mountain, Nevada Test Site, for the potential construction of a high-level nuclear waste repository. This report gives a summary description of the three waste forms for which LLNL is designing waste packages: spent fuel, either as intact assemblies or as consolidated fuel pins, reprocessed commercial high-level waste in the form of borosilicate glass, and reprocessed defense high-level waste from the Defense Waste Processing Facility in Aiken, S.C. Reference packing material for use with the alternative waste package design for spent fuel is also described. 14 references, 8 figures, 20 tables

  4. PIME '98, proposal for opening contribution: Nuclear waste

    International Nuclear Information System (INIS)

    Full text: Would a debate about an international nuclear waste repository help us win greater public acceptance for our disposal plans? My opening points will be: - International nuclear waste repositories can be accepted by the public only after the acceptance of national repositories. If there are no accepted national plans or existing national repositories, nobody is accepting any international repository in his or her own country; - The focus of gaining public acceptance should therefore be on the national programmes and on the technology itself, i.e. 'Deep disposal is a safe solution independent on the type of rock formations, crystalline, salt, clay etc.'; - The Finnish situation is quite clear. Our people are rather confident on the stability of our old crystalline granite bedrock. Finnish politicians and ordinary people are very much against accepting high-level waste or spent nuclear fuel of foreign origin to be disposed of in Finland. This was one of the reasons why the Finnish Nuclear Act was amended before Finland joined to EU, so that the import and export of nuclear waste are forbidden; - Our site selection programme in Finland is in a very sensitive phase. The Government has just confirmed the target, site selection at the end of year 2000, and the statutory Environmental Impact Assesment process has just been initiated in four candidate sites. Certain opponents try to frighten people by claiming that accepting the site and the deep disposal of our domestic waste means also definitely accepting the same for foreign waste, in any case for any nuclear waste from other EU countries; - So, all news on discussion about international nuclear waste repositories will create more suspicions against the Finnish nuclear authorities, waste company and utilities. Summary: The answer is no, the debate about international nuclear waste repository does not help us to win greater public acceptance for our disposal plans. (author)

  5. Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination

    Energy Technology Data Exchange (ETDEWEB)

    Jacobson, Victor Levon

    2002-08-01

    U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodiumbearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements.

  6. Radioactive waste: the poisoned legacy of the nuclear industry

    International Nuclear Information System (INIS)

    The nuclear industry produces a huge amount of radioactive waste from one end to the other of the nuclear cycle: i.e. from mining uranium to uranium enrichment through reactor operating, waste reprocessing and dismantling nuclear power plants. Nuclear power is now being 'sold' to political leaders and citizens as an effective way to deal with climate change and ensure security of energy supplies. Nonetheless, nuclear energy is not a viable solution and is thus a major obstacle to the development of clean energy for the future. In addition to safety and security issues, the nuclear industry is, above all, faced with the huge problem of how to deal with the waste it produces and for which it has no solution. This ought to put a brake on the nuclear industry, but instead, against all expectations, its development continues to gather pace. (author)

  7. Effects of beta/gamma radiation on nuclear waste glasses

    International Nuclear Information System (INIS)

    A key challenge in the disposal of high-level nuclear waste (HLW) in glass waste forms is the development of models of long-term performance based on sound scientific understanding of relevant phenomena. Beta decay of fission products is one source of radiation that can impact the performance of HLW glasses through the interactions of the emitted β-particles and g-rays with the atoms in the glass by ionization processes. Fused silica, alkali silicate glasses, alkali borosilicate glasses, and nuclear waste glasses are all susceptible to radiation effects from ionization. In simple glasses, defects (e.g., non-bridging oxygen and interstitial molecular oxygen) are observed experimentally. In more complex glasses, including nuclear waste glasses, similar defects are expected, and changes in microstructure, such as the formation of bubbles, have been reported. The current state of knowledge regarding the effects of β/γ radiation on the properties and microstructure of nuclear waste glasses are reviewed. (author)

  8. Treatment of radioactive waste in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    The report explains the various methods and steps of radioactive waste treatment in the nuclear fuel cycle for interested readers who are not familiar with the subject. The term 'waste management' is illustrated with special regard to the situation in the FRG, and concepts such as reprocessing, direct ultimate disposal of spent fuel elements are explained. Nuclear spent fuel reprocessing is dealt with only as far as it is of significance to the waste management. The report concentrates on the discussion of the various nuclear waste types, and their handling, of reprocessing methods and waste conditioning methods, and of ultimate disposal (in underground geological spaces, on the seafloor, or in trenches). Interim storage, transport, safety and nuclear safeguards are also dealt with in this context. A concise glossary of terms and hints for further reading are attached. (RB)

  9. Effects of beta/gamma radiation on nuclear waste glasses

    Energy Technology Data Exchange (ETDEWEB)

    Weber, W.J. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-07-01

    A key challenge in the disposal of high-level nuclear waste (HLW) in glass waste forms is the development of models of long-term performance based on sound scientific understanding of relevant phenomena. Beta decay of fission products is one source of radiation that can impact the performance of HLW glasses through the interactions of the emitted {beta}-particles and g-rays with the atoms in the glass by ionization processes. Fused silica, alkali silicate glasses, alkali borosilicate glasses, and nuclear waste glasses are all susceptible to radiation effects from ionization. In simple glasses, defects (e.g., non-bridging oxygen and interstitial molecular oxygen) are observed experimentally. In more complex glasses, including nuclear waste glasses, similar defects are expected, and changes in microstructure, such as the formation of bubbles, have been reported. The current state of knowledge regarding the effects of {beta}/{gamma} radiation on the properties and microstructure of nuclear waste glasses are reviewed. (author)

  10. Nuclear waste treatment program. Annual report for FY 1985

    International Nuclear Information System (INIS)

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and the closure of the nuclear fuel cycle and (2) to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide (1) documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required, to treat existing wastes. This annual report describes progress during FY 1985 toward meeting these two objectives. The detailed presentation is organized according to the task structure of the program

  11. Defence nuclear waste disposal in Russia. International perspective

    International Nuclear Information System (INIS)

    Significant amounts of liquid and solid radioactive waste have been generated in Russia during the production of nuclear weapons, and there is an urgent need to find suitable ways to manage these wastes in a way that protects both the current population and future generations. This book contains contributions from pure and applied scientists and other representatives from Europe, North America, and Russia, who are, or have been, actively involved in the field of radioactive waste management and disposal. First-hand experience of specific problems associated with defence-related wastes in the USA and the Russian Federation is presented, and current plans are described for the disposal of solid wastes arising from civilian nuclear power production programmes in other countries, including Belgium, Bulgaria, Canada, Germany and the UK. The book provides a good insight into ongoing research at local and national level within Russia, devoted to the safe disposal of defence-related radioactive waste. It also demonstrates how existing expertise and technology from civilian nuclear waste management programmes can be applied to solving the problems created by nuclear defence programmes. Contributions address methods of immobilisation, site selection methodology, site characterisation techniques and data interpretation, the key elements of safety/performance assessments of planned deep (geological) repositories for radioactive waste, and radionuclide transport modelling. Concerns associated with certain specific nuclear waste disposal concepts and repository sites are also presented. refs

  12. Nuclear waste treatment program: Annual report for FY 1987

    International Nuclear Information System (INIS)

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs

  13. Nuclear Waste Treatment Program. Annual report for FY 1984

    International Nuclear Information System (INIS)

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are: (1) to ensure that waste management is not an obstacle to the further deployment of light-water reactors (LWR) and nuclear fuel cycle closure and (2) to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving those goals, the Office of Terminal Waste Disposal and Remedial Action of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory (PNL) during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP has two objectives: (1) to provide documented technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and (2) to provide problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required, to treat existing wastes. This annual report describes progress during FY 1984 toward meeting the two objectives. 31 figs., 4 tabs

  14. Nuclear Waste Management Program summary document, FY 1981

    International Nuclear Information System (INIS)

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel

  15. Nuclear waste management. Quarterly progress report, October through December 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A. (comps.)

    1981-03-01

    Progress reports and summaries are presented under the following headings: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of radionuclides in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; high level waste form preparation; development of backfill material; development of structural engineered barriers; ONWI disposal charge analysis; spent fuel and fuel component integrity program; analysis of spent fuel policy implementation; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; revegetation of inactive uranium tailing sites; verification instrument development.

  16. Nuclear waste management. Quarterly progress report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-09-01

    The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

  17. Supply, operation and radioactive waste disposal of nuclear power plants

    International Nuclear Information System (INIS)

    The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP)

  18. Financing responsibility for nuclear waste disposal

    International Nuclear Information System (INIS)

    The basic premise for financing arrangements for the disposal of nuclear waste is that the nuclear industry - not the taxpayer - must bear the costs. Present regulations, however, are imperfect in this regard. The Inquiry therefore proposes extending the financial liability of the nuclear industry and introducing new fee-setting arrangements. It is proposed that a new law be enacted to regulate these changes. The present financing system is regulated in the 'Financing Act' 1. Under this Act, the licensed owner and operator of a nuclear reactor is required to pay an annual fee and provide guarantees to the State. Four companies are reactor owners. These companies are wholly or partly owned by other companies according to various arrangements. Each reactor owner is responsible for its own dismantling costs and for its share of allocated common costs of disposal and related measures. If there is insufficient money in the funds, the nuclear industry will still be liable. The basic premise of the Inquiry is that the financing system should be designed so as to minimise the risk that the State (and taxpayers) will need to step in and pay. Although the nuclear industry is intended to have full liability for payment, in practice it does not. This is because the formal full liability for payment in the nuclear industry rests with the reactor companies and not where the industry's long-term ability to pay is to be found. Essentially, the present arrangements mean that: - Companies that cannot be expected to have any long-term ability to pay have unlimited liability, and - Companies that can be expected to have an ability to pay have very limited liability. The Inquiry therefore proposes that ability to pay and liability are brought into line by a formal assumption by owning companies of the sort of liability for payment that now rests solely with the reactor companies. This means that the owning company in each group that is best suited to bear the liability for payment

  19. Cement-Based Materials for Nuclear Waste Storage

    CERN Document Server

    Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

    2013-01-01

    As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

  20. Chromatographic separation of actinides and fission products from nuclear wastes

    International Nuclear Information System (INIS)

    Although a number of partitioning processes have been proposed and studied to separate the minor actinides (MA: Am, Cm, Np) and some fission product elements (FPs) from nuclear wastes, most of these processes essentially utilize liquid-liquid extraction technology by using a mixture of organic extractants hydrocarbon diluents. A large amount of the secondary waste, which is difficult for treatment and disposal will be generated by the extraction process. Compared to U and Pu, the MA and FPs are significantly abundant in the spent fuel, so that the scale of an efficient partitioning process for nuclear wastes reasonably small and result in less waste amount

  1. GAO and the Nuclear Waste Policy Act of 1982

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act of 1982 (Section 304(d)) requires the General Accounting Office to perform an annual audit of DOE's Office of Civilian Radioactive Waste Management. The first annual audit report (to be issued in spring 1984) will focus on DOE's organization and management structure, progress in siting decisions for a geologic repository, and establishment of a Nuclear Waste Fund to finance the program. As th DOE program progresses, GAO will be addressing a variety of other issues surrounding development of a waste repository, interim spent fuel storage, and DOE research and development

  2. Nuclear waste disposal: technology and environmental hazards

    International Nuclear Information System (INIS)

    The subject is discussed under the headings: introduction; the nature and origin of wastes (fuel cycles; character of wastes; mining and milling operations; middle stages; irradiated fuel; reprocessing (waste generation); reactor wastes); disposal techniques and disposal of reprocessing wastes; siting of repositories; potential environmental impacts (impacts after emplacement in a rock repository; catastrophic effects; dispersion processes (by migrating ground water); thermal effects; future security; environmental survey, monitoring and modelling); conclusion. (U.K.)

  3. WNA position statement on safe management of nuclear waste and used nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Saint-Pierre, S. [World Nuclear Association - WNA, London (United Kingdom)

    2006-07-01

    This World nuclear association (W.N.A.) Position Statement summarizes the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the W.N.A. will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry

  4. WNA position statement on safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    This World nuclear association (W.N.A.) Position Statement summarizes the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the W.N.A. will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations

  5. More reliable financing of future nuclear waste costs

    International Nuclear Information System (INIS)

    This appendix contains seven reports written by consultants to the Commission. The report titles are: Basic document regarding the inquiry on fund management; Scenarios for growth and real interest rates in a long perspective; Stability of the Swedish financing system; Report concerning the financing of nuclear waste management in Sweden and Finland and the cost control system in Sweden; Evaluation of the cost estimates and calculation methods of SKB; A study of the costs for nuclear waste - The basis for cost estimation; A review of scope and costs for the Swedish system for management of nuclear waste. The four last reports are separately indexed

  6. Risk perception as it applies to nuclear power and nuclear waste disposal

    International Nuclear Information System (INIS)

    Disparate perceptions of risk have emerged as one of the critical issues confronting the future of commercial nuclear power. This paper explores the origins and possible ramifications of the public's perception of risks associated with commercial nuclear power and related high-level nuclear waste disposal programs. This paper summarizes the results of numerous psychometric studies and public opinion polls that analyze the relationship of risk to nuclear power and waste management

  7. Nuclear Waste Fund fee adequacy: An assessment: Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    The estimated long-term impact of the costs and fees associated with disposal of defense high-level wastes (DHLW) in the Office of Civilian Radioactive Waste Management (OCRWM) repository system is assessed. It is assumed that the DHLW disposal fees paid will provide funds equivalent to the OCRWM costs for disposing of this waste, including interest on costs incurred before the payment of the fee(s) to cover these costs, and the appropriate share of the common costs of the OCRWM waste disposal system. The DHLW disposal fee payments into the Nuclear Waste Fund will be subject to Congressional appropriations. This report is based on the assumptions that the first repository will open in 2003 and the second repository in 2023. In addition, this analysis features an Improved Performance System (IPS), a major component of which is a proposed (but currently unauthorized) Monitored Retrievable Storage (MRS) facility that is assumed to open in 1998. The possibility of adverse developments in inflation and real interest rates should be considered in assessing the findings of this analysis which are based on a cash flow analysis that utilized methods very similar to those employed in previous fee adequacy studies. Revisions were made in the areas of system logistics, repository schedules, real interest rates, inflation rates, and the estimation of costs for design and evaluation work, transportation, and repositories in differing host rocks. The principal recommendation is that the ongoing disposal fee should remain at 1.0 mill per (net) kilowatt-hour (kWh) for 1987 based on the assumption that defense waste fees will be adequate to cover the defense share of the program costs

  8. Understanding nuclear waste management within a global framework

    International Nuclear Information System (INIS)

    Within the past two decades important questions have emerged relative to the increased use of nuclear power worldwide and to the need to store high level radioactive waste from nuclear power plants. Because students in today's classrooms will become future decision-makers and caretakers of both nuclear power plants and radioactive waste repositories, they will be faced with these questions. This paper considers the value of nuclear power and radioactive waste management (RWM) as topics for science classrooms. First, nuclear power as a global educational topic is discussed. Second, the results of the first international workshop on education in the field of RWM are presented. Finally, questions for developing school classroom curriculum materials on nuclear power and RWM are considered

  9. Stakeholder Involvement in Swedish Nuclear Waste Management

    International Nuclear Information System (INIS)

    The focus in this paper is on past, current and emerging patterns of stakeholder involvement in the siting of a deep repository for final disposal of Sweden's spent nuclear fuel. In particular, we concentrate on how the two municipalities of Oskarshamn and Oesthammar have acted as engaged stakeholders, and have gained recognition as such, in the siting process. In general: How has stakeholder involvement gained acceptance as an activity of value in the siting of major waste facilities? What are the issues currently subject to stakeholder involvement and how have these been decided upon? An effect of the history of nuclear activity in Oskarshamn and Oesthammar is that stakeholder involvement over a final repository can be divided into social and technical issues. Both municipalities have out of tradition, as part of their social acceptance of a new repository, been prepared to surrender extended involvement in key safety issues. They have been prepared to do this because they also see themselves being able to delegate these safety issues to the government authorities SSI and SKI. These two authorities have been acceptable to the two municipalities as their legitimate 'technological guardians'. As physical geology re-enters the siting process for a deep repository, Oskarshamn appear more prepared to break with tradition than Oesthammar. Oskarshamn are currently demanding transparency from SKB in relation to the exact technical and geological criteria they will use to choose between them and Oesthammar as a repository site. In contrast to Oesthammar, Oskarshamn are preparing with the expected help of SKI and SSI to dispute their geology and its relation to nuclear safety with SKB if they consider it necessary. If Oskarshamn act to draw safety issues in relation to alternative methods and sitings into the EIA process where might this lead? As environmental groups now enter the process (three groups were granted funding in the first round - 2005) the character of site

  10. Radioactive waste management methodology development for waste generated by nuclear facilities decommissioning applicable to CANDU-600 Nuclear Power Plant

    International Nuclear Information System (INIS)

    The objective of this paper is to provide information for nuclear field specialists and decision makers on opportunities for development of management methodology for radioactive wastes arising from the decontamination and decommissioning of a CANDU 600 nuclear facility. In this paper we report the waste management strategies: on-site management of the waste, centralized management, and a mixture of these two. Also we present the waste management plan in which a range of technological options shall be identified and evaluated in order to select and justify the most appropriate solution by taking into account the basic waste management principles. Because of the variety of processes, techniques and equipment available for different steps of a waste management scheme, a proper technology has to be selected for each step. A number of trends in radioactive waste management in many countries have been observed. These trends are summarized in this paper. (authors)

  11. High level nuclear waste treatment in the Defense Waste Processing Facility: Overview and integrated flowsheet model

    International Nuclear Information System (INIS)

    Design and construction of the world's largest vitrification facility for high level nuclear waste has been nearly completed at the US Department of Energy's Savannah River Site. Equipment testing and calibration are currently being performed in preparation for the nonradioactive Chemical Runs in the late 1991. In 1993, the Defense Waste Processing Facility (DWPF) will begin producing 100 kg/hr of radioactive waste glass at 28 wt% waste oxide loading. This paper describes all phases of waste processing operations in DWPF and waste tank farms using the integrated flowsheet modeling approach. Particular emphases are given to recent developments in the DWPF processes and design

  12. Will America's nuclear waste be laid to rest?

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) in New Mexico, was designed to store waste from the United States (U.S.) nuclear weapons production in deep repositories under the naturally occurring salt beds. However no waste can be put into the repository until safety checks, designed as nuclear reactor safety standards, have been satisfactorily completed to the U.S. congress's satisfaction. While political controversy reigns the WIPP structure stands empty and steel drums of radioactive waste remain at the U.S. nuclear weapons factories. Proponents say costly capital investment is being wasted, opponents that people and the environment would be at risk of contamination if safety standards were not understood and adhered to. (UK)

  13. Nuclear waste management; La gestion des dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Nifenecker, H.

    2008-07-01

    The author gives an overview of the main issues related to the use of nuclear energy: the management and the environmental impact of wastes. After having outlined the different radiological consequences of different radionuclides, he proposes an approximate assessment of waste production which may depend on reactor technology, and which needs a distinction between low level, intermediate level, and high level wastes. He discusses the differences between primary energies and final energies, and how to consider nuclear energy and its wastes within this classification. Then, considering the deep geological storage, he describes how contamination may occur and the risks for the population as well as for the environment. After having evoked the use of breeder reactors and its separation-transmutation issues, the author briefly comments the nuclear waste financing issue

  14. Waste management at the Nuclear Technology Development Centre (CDTN)

    International Nuclear Information System (INIS)

    In several laboratories and pilot plants at the Nuclear Technology Development Centre (Centro de Desenvolvimento da Tecnologia Nuclear - CDTN), low level solid and liquid radioactive wastes are generated from nuclear fuel cycle activities, radioisotopes application, R and D and routine works. The CDTN also receives spent sources from radioisotopes users. These wastes are to be managed to avoid contamination risks and minimize the costs of treatment and further storage. To systematize the waste control, a Waste Management Programme has been implemented since 1983, which strategy is based on the national regulations and the available infrastructure at the Centre. This paper presents an overview of the waste management at the CDTN, some results of research and development and the technical support given to the community, as well as dealing with the emergency caused by the radiological accident that occurred in Goiania. (author). 5 refs, 1 fig., 1 tab

  15. Can clays ensure nuclear waste repositories?

    Science.gov (United States)

    Zaoui, A.; Sekkal, W.

    2015-03-01

    Research on argillite as a possible host rock for nuclear waste disposal is still an open subject since many issues need to be clarified. In the Underground Research Laboratories constructed for this purpose, a damaged zone around the excavation has been systematically observed and characterized by the appearance of micro-fissures. We analyse here -at nanoscale level- the calcite/clay assembly, the main constituents of argillite, under storage conditions and show the fragility of the montmorillonite with respect to calcite. Under anisotropic stress, we have observed a shear deformation of the assembly with the presence of broken bonds in the clay mineral, localised in the octahedral rather than the tetrahedral layers. The stress/strain curve leads to a failure strength point at 18.5 MPa. The obtained in-plane response of the assembly to perpendicular deformation is characterized by smaller perpendicular moduli Ez = 48.28 GPa compared to larger in-plane moduli Ex = 141.39 GPa and Ey = 134.02 GPa. Our calculations indicate the instability of the assembly without water molecules at the interface in addition to an important shear deformation.

  16. Seismic safety in nuclear-waste disposal

    International Nuclear Information System (INIS)

    Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures

  17. Importance measures for nuclear waste repositories

    International Nuclear Information System (INIS)

    Several importance measures are identified for possible use in the performance assessment of a high-level nuclear waste repository. These importance measures are based on concepts of importance used in system reliability analysis, but the concepts are modified and adapted to the special characteristics of the repository and similar passive systems. In particular, the importance measures proposed here are based on risk (in comparison to traditional importance measures which are based on frequency of failure) and are intended to be more suitable to systems comprised of components whose behavior is most easily and naturally represented as continuous, rather than binary. These importance measures appear to be able to evaluate systems comprised of both continuous-behavior and binary-behavior components. Three separate examples are provided to illustrate the concepts and behavior of these importance measures. The first example demonstrates various formulations for the importance measures and their implementation for a simple radiation safety system comprised of a radiation source and three shields. The second example demonstrates use of these importance measures for a system comprised of components modeled with binary behavior and components modeled with continuous behavior. The third example investigates the use of these importance measures for a proposed repository system, using a total system model and code currently under development. Currently, these concepts and formulations of importance are undergoing further evaluation for a repository system to determine to what degree they provide useful insights and to determine which formulations are most useful

  18. Can clays ensure nuclear waste repositories?

    Science.gov (United States)

    Zaoui, A; Sekkal, W

    2015-01-01

    Research on argillite as a possible host rock for nuclear waste disposal is still an open subject since many issues need to be clarified. In the Underground Research Laboratories constructed for this purpose, a damaged zone around the excavation has been systematically observed and characterized by the appearance of micro-fissures. We analyse here -at nanoscale level- the calcite/clay assembly, the main constituents of argillite, under storage conditions and show the fragility of the montmorillonite with respect to calcite. Under anisotropic stress, we have observed a shear deformation of the assembly with the presence of broken bonds in the clay mineral, localised in the octahedral rather than the tetrahedral layers. The stress/strain curve leads to a failure strength point at 18.5 MPa. The obtained in-plane response of the assembly to perpendicular deformation is characterized by smaller perpendicular moduli Ez = 48.28 GPa compared to larger in-plane moduli Ex = 141.39 GPa and Ey = 134.02 GPa. Our calculations indicate the instability of the assembly without water molecules at the interface in addition to an important shear deformation. PMID:25742950

  19. Chemistry of nuclear resources, technology, and waste

    Energy Technology Data Exchange (ETDEWEB)

    Keller, O.L. Jr.

    1978-01-01

    Chemistry is being called on today to obtain useful results in areas that have been found very difficult for it in the past, but new instrumentation and new theories are allowing much progress. The area of hydrolytic phenomena and colloid chemistry, as exemplified by the plutonium polymer problem, is clearly entering a new phase in which it can be studied in a much more controlled and understandable manner. The same is true of the little studied interfacial regions, where so much important chemistry occurs in solvent extraction and other systems. The studies of the adsorption phenomena on clays are an illustration of the new and useful modeling of geochemical phenomena that is now possible. And finally, the chemist is called upon to participate in the developement and evaluation of models for nuclear waste isolation requiring extrapolations of hundreds to hundreds of thousands of years into the future. It is shown that chemistry may be useful in keeping the extrapolations in the shorter time spans, and also in selecting the best materials for containment. 36 figures.

  20. Chemistry of nuclear resources, technology, and waste

    International Nuclear Information System (INIS)

    Chemistry is being called on today to obtain useful results in areas that have been found very difficult for it in the past, but new instrumentation and new theories are allowing much progress. The area of hydrolytic phenomena and colloid chemistry, as exemplified by the plutonium polymer problem, is clearly entering a new phase in which it can be studied in a much more controlled and understandable manner. The same is true of the little studied interfacial regions, where so much important chemistry occurs in solvent extraction and other systems. The studies of the adsorption phenomena on clays are an illustration of the new and useful modeling of geochemical phenomena that is now possible. And finally, the chemist is called upon to participate in the developement and evaluation of models for nuclear waste isolation requiring extrapolations of hundreds to hundreds of thousands of years into the future. It is shown that chemistry may be useful in keeping the extrapolations in the shorter time spans, and also in selecting the best materials for containment. 36 figures

  1. Uncertainty analysis of nuclear waste package corrosion

    International Nuclear Information System (INIS)

    This paper describes the results of an evaluation of three uncertainty analysis methods for assessing the possible variability in calculating the corrosion process in a nuclear waste package. The purpose of the study is the determination of how each of three uncertainty analysis methods, Monte Carlo, Latin hypercube sampling (LHS) and a modified discrete probability distribution method, perform in such calculations. The purpose is not to examine the absolute magnitude of the numbers but rather to rank the performance of each of the uncertainty methods in assessing the model variability. In this context it was found that the Monte Carlo method provided the most accurate assessment but at a prohibitively high cost. The modified discrete probability method provided accuracy close to that of the Monte Carlo for a fraction of the cost. The LHS method was found to be too inaccurate for this calculation although it would be appropriate for use in a model which requires substantially more computer time than the one studied in this paper

  2. Safe management of non-nuclear radioactive waste

    International Nuclear Information System (INIS)

    In May 2002, the Swedish Government set up a non-standing committee for the management of radioactive waste unrelated to nuclear technology i.e. outside the nuclear fuel cycle - in this report called non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The author was principal secretary in the Committee. The proposals from the Committee was delivered to the Government by December 3, 2003. Funds for future costs for the management and final storage of waste from nuclear power are collected in a state-governed funding system. The power sector pays a flat fee per kilowatt-hour nuclear power. For non-nuclear radioactive waste, however, there are no means today to secure the funding. If a company goes bankrupt and leaves radioactive waste behind it might be up to the taxpayers to pay for its safe management. This is because the holder of the waste is responsible for its disposal. The costs appear at the time of disposal and it is usually the last owner/holder of a radioactive product that has to pay. Sometimes the costs come as a surprise and the owner might not have the money available. Thus the waste might be kept longer than warranted or end up as orphan waste. To solve this dilemma and other weaknesses in the Swedish system the Committee proposes a funding system paralleling the system for nuclear waste. The cost for the waste should be paid up front, i.e. when a customer buys a product using a radioactive source, the cost for the future waste management should be included in the price. In this way the consumer will not have to pay for this the day he disposes of the product by returning it to the original producer or leaving it to some waste treatment organization. It should be the responsibility of the producer (manufacturer, importer) to guarantee

  3. Corrosion process studies in a nuclear waste container

    International Nuclear Information System (INIS)

    Latest results on corrosion behavior studies on high activity nuclear waste container are reported. Corrosion evaluation on lead base alloys and modeling to predict carbon steel external container cover generalized corrosion, are the main issues of these studies. (author)

  4. Delegated Democracy. The Siting of Swedish Nuclear Waste

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, Hanna Sofia (Stockholm Univ., SCORE, SE-106 91 Stockholm (Sweden))

    2009-12-15

    This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

  5. Searching for acceptable solutions to nuclear-waste disposal

    International Nuclear Information System (INIS)

    Three lettes are presented here, all addressing the problem of nuclear waste disposal. Robert M. Bernero (former director of the Office of Nuclear Material Safety and Safeguards, US NRC) points out there are only 4 options for managing toxic and nuclear waste (recycling, outer space disposal; deep-ocean disposal, geologic disposal) and that the stragegy should prevent people from inadvertently stumbling onto the waste site. Robert Holden (director nuclear Waste Program, National Congress of American Indians) uses Yucca Mountain to illustrate problems and solutions that must be implemented if tribal people's concerns are to be respected. George E. Dials (Manager, Carlsbad Area Office, US DOE) focuses on a positive assessment of WIPP as part of the solution

  6. Tunnel Boring Machine for nuclear waste repository research project

    International Nuclear Information System (INIS)

    A description is presented of a Tunnel Boring Machine and its intended use on a research project underway in Sweden for demonstrating and testing methods for rock investigation at a suitable depth for a deep repository for nuclear waste

  7. Nuclear waste management and problems arising from constitutional law

    International Nuclear Information System (INIS)

    The author discusses the problems arising in the field of nuclear waste management on account of the constitutional law. Especially the difficulties emanating from the conflict between the provisions of section 9a of the Atomic Energy Act and the provisions of constitutional law are dealt with in detail, referring to the monography of H. Hofmann, 'legal aspects of nuclear waste management'. The author comes to the conclusion that the reqquirements laid down in section 9a-9c of the Atomic Energy Act are in agreement with the Basic law. There is, he says, no unreasonable risk for future generations, as the provisions of the nuclear law provide for sufficient safety of sites and equipment selected for the final storage of nuclear waste, ensuring that radioactive leakage is excluded over long periods of time. In the second part of his lecture, the author discusses the problem of competency and delegation of authority with regard to the reprocessing of radioactive waste. (BW)

  8. Nuclear Waste Act revisions put on '95 congressional agenda

    International Nuclear Information System (INIS)

    This article discusses possible revisions of the Nuclear Waste Policy Act, the reasons for the need for such revisions, and the economic, political and environmental concerns which need to be addressed

  9. Application Research of Developed Drummed Nuclear Waste Neutron Counting System

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The application researches such as variety of factors affecting the measurement, calibrating etc. are need before the drummed nuclear waste neutron counting system (WNC) can be really put into use after installed at the site.

  10. Public concerns of nuclear waste issues in Taiwan

    International Nuclear Information System (INIS)

    This paper discusses opinions and comments from randomly selected 1837 general public and 454 professionals compiled and analyzed to obtain their concerns on nuclear waste issues in Taiwan. Results are presented. A public education and promotion program is suggested

  11. Delegated Democracy. The Siting of Swedish Nuclear Waste

    International Nuclear Information System (INIS)

    This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

  12. Iron Phosphate Glasses: An Alternative for Vitrifying Certain Nuclear Wastes

    International Nuclear Information System (INIS)

    Vitrification of nuclear waste in a glass is currently the preferred process for waste disposal. DOE currently approves only borosilicate (BS) type glasses for such purposes. However, many nuclear wastes, presently awaiting disposal, have complex and diverse chemical compositions, and often contain components that are poorly soluble or chemically incompatible in BS glasses. Such problematic wastes can be pre-processed and/or diluted to compensate for their incompatibility with a BS glass matrix, but both of these solutions increases the wasteform volume and the overall cost for vitrification. Direct vitrification using alternative glasses that utilize the major components already present in the waste is preferable, since it avoids pre-treating or diluting the waste, and, thus, minimizes the wasteform volume and overall cost

  13. The waste management program at VUB-AZ: An integrated solution for nuclear biomedical waste management

    International Nuclear Information System (INIS)

    In 1996 the University of Brussels and its Academic hospital (VUB-AZ) started a waste program for the nuclear biomedical waste management. This program, based on selective collection, measurement before decay, storage for decay of short-lived radionuclides, measurement after decay and eventual clearance as non-nuclear waste, has proved its effectiveness over the past 5 years. Effective characterisation for on-site storage for decay of short-lived radionuclides makes selective collection of waste streams mandatory and requires motivated and trained laboratory staff. Dynamic optimisation of this selective collection increases the efficiency of the storage for decay program. The accurate qualitative and quantitative measurement of nuclear biomedical waste before decay has several advantages such as verification of correct selective collection, optimisation of the decay period and possibility of clearance below the minimal detectable activity. Sealed waste packages are assessed for specific activity by an HPGe-detector or by a liquid scintillation counter. The WasteMan software allows a full trace-ability of all waste packages from production to either clearance or disposal. This waste storage program, including the complete measurement set-up and the necessary management software, is already installed in a second university, proving the general applicability of the whole concept for biomedical nuclear waste. Many hospitals and other biomedical centres however produce small quantities of nuclear waste for which investments in measurement equipment and decay rooms are not cost-effective. The installation of a regional centre for nuclear biomedical waste will be presented here as an alternative solution to this problem. (author)

  14. The role of the operator of nuclear power plants in disposal of nuclear waste

    International Nuclear Information System (INIS)

    Public opinion polls show that the French have largely understood the importance of our nuclear programme in maintaining French independence with regard to power supply and its security and that they have confidence in the technicians for the proper construction and operation of these power plants, but that they retain many questions concerning the disposal of nuclear waste. They have the impression that solutions remain to be found, and especially that the Electricite de France (EDF) devised the nuclear power programme without concern for the disposal of waste. This lack of information is fortunately far from reality, EDF, under the supervision of the security authorities, manages the waste produced in the nuclear power plants. Final stocking of waste is handled by a body that is independent of the waste producer, the ''Agence nationale pour la gestion des dechets radioactifs'' (Andra) (National Agency for the Management of Radioactive Waste). (author). 7 refs., 1 tab

  15. Nuclear waste repository in basalt: preconceptual design guidelines

    International Nuclear Information System (INIS)

    The development of the basalt waste isolation program parallels the growing need for permanent, environmentally safe, and secure means to store nuclear wastes. The repository will be located within the Columbia Plateau basalt formations where these ends can be met and radiological waste can be stored. These wastes will be stored such that the wastes may be retrieved from storage for a period after placement. After the retrieval period, the storage locations will be prepared for terminal storage. The terminal storage requirements will include decommissioning provisions. The facility boundaries will encompass no more than several square miles of land which will be above a subsurface area where the geologic makeup is primarily deep basaltic rock. The repository will receive, from an encapsulation site(s), nuclear waste in the form of canisters (not more than 18.5 feet x 16 inches in diameter) and containers (55-gallon drums). Canisters will contain spent fuel (after an interim 5-year storage period), solidified high-level wastes (HLW), or intermediate-level wastes (ILW). The containers (drums) will package the low-level transuranic wastes (LL-TRU). The storage capacity of the repository will be expanded in a time-phased program which will require that subsurface development (repository expansion) be conducted concurrently with waste storage operations. The repository will be designed to store the nuclear waste generated within the predictable future and to allow for reasonable expansion. The development and assurance of safe waste isolation is of paramount importance. All activities will be dedicated to the protection of public health and the environment. The repository will be licensed by the US Nuclear Regulatory Commission (NRC). Extensive efforts will be made to assure selection of a suitable site which will provide adequate isolation

  16. Chemical digestion of low level nuclear solid waste material

    International Nuclear Information System (INIS)

    A method is described for processing low level, light weight, bulky, combustible nuclear solid waste material comprising the steps of reacting said solid waste material with concentrated sulfuric acid at a temperature within the range of 230 deg - 300 deg C and simultaneously, subsequently, or both simultaneously and subsequently contacting said waste with concentrated nitric acid or nitrogen oxides whereby carbonaceous material is oxidized to gaseous byproducts and a low volume residue. (author)

  17. Underlying chemistry research for the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    This document reviews the underlying chemistry research part of the Canadian Nuclear Fuel Waste Management Program, carried out in the Research Chemistry Branch. This research is concerned with developing the basic chemical knowledge and under-standing required in other parts of the Program. There are four areas of underlying research: Waste Form Chemistry, Solute and Solution Chemistry, Rock-Water-Waste Interactions, and Abatement and Monitoring of Gas-Phase Radionuclides

  18. Benefits and risks of P and T of nuclear waste

    International Nuclear Information System (INIS)

    Efforts on waste transmutation are coordinated in a research programme called RAS. One of the aims of this RAS program is to inform the public and advise the authorities on methods for transmutation/conditioning of nuclear waste, and on techniques which are being developed. Such new procedures for the treatment of waste should of course not lead to significant risks for the present population. Small risks might be accepted, but these should sufficiently be compensated for by favours to future generations

  19. HEAVY METAL PARTITIONING IN A NUCLEAR WASTE TREATMENT PLANT

    Institute of Scientific and Technical Information of China (English)

    J. Wochele; Chr. Ludwig; H.-J. Lau; W. Heep

    2006-01-01

    The fate of different trace elements and radio nuclides in the new ZWILAG nuclear waste treatment plant(Switzerland) has been modelled, in order to predict and check the transport behaviour of the volatile species and their distribution in the plant. Calculations show that for active waste from medicine, industry, research (MIR waste) only Zn and Cs have stable gaseous species at 1200℃. The investigations confirm the efficiency of the examined flue gas cleaning system.

  20. Method for calcining nuclear waste solutions containing zirconium and halides

    Science.gov (United States)

    Newby, Billie J.

    1979-01-01

    A reduction in the quantity of gelatinous solids which are formed in aqueous zirconium-fluoride nuclear reprocessing waste solutions by calcium nitrate added to suppress halide volatility during calcination of the solution while further suppressing chloride volatility is achieved by increasing the aluminum to fluoride mole ratio in the waste solution prior to adding the calcium nitrate.

  1. Nuclear Waste Cross Site Transfer Pump Operational Resonance Resolution

    International Nuclear Information System (INIS)

    Two single-volute, multi-stage centrifugal pumps are installed at a nuclear waste transfer station operated by the Department of Energy in Hanford, WA. The two parallel 100% pumps are Variable Frequency Drive operated and designed to transport waste etc

  2. Mobile fission and activation products in nuclear waste disposal

    International Nuclear Information System (INIS)

    This document gathers 33 oral presentations that were made at this workshop dedicated to the mobility of some radionuclides in nuclear waste disposal. The workshop was organized into 6 sessions: 1) performance assessment, 2) speciation/interaction in aqueous media, 3) radioactive wastes, 4) redox processes at interfaces, 5) diffusion processes, and 6) retention processes

  3. The Settling and Compaction of Nuclear Waste Slurries

    International Nuclear Information System (INIS)

    The settling and compaction of simulated and real nuclear waste slurries were extensively studied. Experiments were carried out with simulated wastes at laboratory and large-scale sizes, and the results compared. A model of settling was derived and a method developed to correlate and scale-up settling data for different slurries and vessel sizes

  4. Responsibility, fairness and credibility - ethical dilemmas concerning nuclear waste

    International Nuclear Information System (INIS)

    This book is written with the aim to stimulate discussion and studies on ethical aspects of nuclear waste management. It does not penetrate the technical details of the different stages of waste handling, but concentrates on questions such as our responsibility towards future generations etc

  5. Process considerations for hot pressing ceramic nuclear waste forms

    International Nuclear Information System (INIS)

    Spray calcined simulated ceramic nuclear waste powders were hot pressed in graphite, nickel-lined graphite and ZrO2-lined Al2O3 dies. Densification, initial off-gas, waste element retention and pellet-die interactions were evaluated. Indicated process considerations and limitations are discussed. 15 figures

  6. The Settling and Compaction of Nuclear Waste Slurries

    Energy Technology Data Exchange (ETDEWEB)

    MACLEAN, G.T.

    1999-11-15

    The settling and compaction of simulated and real nuclear waste slurries were extensively studied. Experiments were carried out with simulated wastes at laboratory and large-scale sizes, and the results compared. A model of settling was derived and a method developed to correlate and scale-up settling data for different slurries and vessel sizes.

  7. Low-level waste management at the Nuclear Research Center

    International Nuclear Information System (INIS)

    A general overview of low-level radioactive waste management at the Nuclear Investigation Centre (CIN) of Uruguay is presented. The CIN is a pilot centre of research and development of techniques for implementing measurements for radioactive waste storage and control. (M.C.K.)

  8. THE NOX SYSTEM IN HOMOGENEOUS AND HETEROGENEOUS NUCLEAR WASTE

    Science.gov (United States)

    This report summarizes advances of the above-mentioned EMSP project during the period July 1, 2001 - June 30, 2002. The project focuses on the effects of organic chemicals in stored nuclear waste and their impact on pretreatment and tank closure issues. Managing the tank wastes a...

  9. Mobile fission and activation products in nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Umeki, H.; Evans, N.; Czervinski, K.; Bruggeman, Ch.; Poineau, F.; Breynaert, A.; Reiler, P.; Pablo, J. de; Pipon, Y.; Molnar, M.; Nishimura, T.; Kienzler, B.; Van Iseghem, P.; Crovisier, J.L.; Wieland, E.; Mace, N.; Pablo, J. de; Spahiu, K.; Cui, D.; Lida, Y.; Charlet, L.; Liu, X.; Sato, H.; Goutelard, F.; Savoye, S.; Glaus, M.; Poinssot, C.; Seby, F.; Sato, H.; Tournassat, Ch.; Montavon, G.; Rotenberg, B.; Spahiu, K.; Smith, G.; Marivoet, J.; Landais, P.; Bruno, J.; Johnson, H.; Umeki, L.; Geckeis, H.; Giffaut, E.; Grambow, B.; Dierckx, A

    2007-07-01

    This document gathers 33 oral presentations that were made at this workshop dedicated to the mobility of some radionuclides in nuclear waste disposal. The workshop was organized into 6 sessions: 1) performance assessment, 2) speciation/interaction in aqueous media, 3) radioactive wastes, 4) redox processes at interfaces, 5) diffusion processes, and 6) retention processes.

  10. Modeling transient heat transfer in nuclear waste repositories.

    Science.gov (United States)

    Yang, Shaw-Yang; Yeh, Hund-Der

    2009-09-30

    The heat of high-level nuclear waste may be generated and released from a canister at final disposal sites. The waste heat may affect the engineering properties of waste canisters, buffers, and backfill material in the emplacement tunnel and the host rock. This study addresses the problem of the heat generated from the waste canister and analyzes the heat distribution between the buffer and the host rock, which is considered as a radial two-layer heat flux problem. A conceptual model is first constructed for the heat conduction in a nuclear waste repository and then mathematical equations are formulated for modeling heat flow distribution at repository sites. The Laplace transforms are employed to develop a solution for the temperature distributions in the buffer and the host rock in the Laplace domain, which is numerically inverted to the time-domain solution using the modified Crump method. The transient temperature distributions for both the single- and multi-borehole cases are simulated in the hypothetical geological repositories of nuclear waste. The results show that the temperature distributions in the thermal field are significantly affected by the decay heat of the waste canister, the thermal properties of the buffer and the host rock, the disposal spacing, and the thickness of the host rock at a nuclear waste repository. PMID:19376651

  11. All the Spent Nuclear Wastes to Low and Intermediate Level Wastes: PyroGreen

    International Nuclear Information System (INIS)

    Spent nuclear wastes are inevitable issues to use nuclear power as a sustainable energy. Therefore, every country has their fuel cycles which are best for their environmental and/or political circumstances for the use of nuclear energy. These days agreements are made that spent nuclear fuels should be recycled to minimize waste volume and its toxicity all around the world. Republic of Korea also has a plan to recycle the spent nuclear fuels by using Gen-IV concept burner reactors and pyro-process plants. Not many options of national nuclear strategies are exist because Korea has too many people for its limited land space. KAERI already has been proposing a national fuel cycle concept called 'KIEP-21' that encompasses all the requirements of the advanced nuclear fuel cycle such as reduction of volume, toxicity, HLW heat load and so on. Authors suggest non-national fuel cycle concept called 'PyroGreen' for the sustainable nuclear energy system. PyroGreen is also comprised of transmutation reactor and pyro-process plant such as typical advanced fuel cycle system. However, to make all the spent nuclear fuels to low and intermediate level wastes several strategies are provided. Radioactive nuclear wastes are classified into HLW and LILW considering its heat load, concentration, and its migration capabilities into environments. If the concentration limit is satisfied heat load limit is not important. However, migration of radioactive elements from disposed waste forms is not negligible. Therefore, PyroGreen considers deep geological disposal of nuclear wastes to mitigate the effect of concentration limits based on the human intrusion scenario. Ceramic waste forms which has extremely low leach rate of loaded elements can be used as a waste form to solve the migration issues and decrease exclusion area of disposal site. To decrease waste toxicity, decontamination factor of TRUs through whole pyro-process should be as high as possible. To maximize the decontamination factor

  12. Building world-wide nuclear industry success stories - Safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    Full text: This WNA Position Statement summarizes the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the WNA will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations. Accumulating experience and

  13. Radioactive wastes of the nuclear industry: radiological impact and characterization

    International Nuclear Information System (INIS)

    These conference days, organized by the French society of radioprotection (SFRP), aim at presenting the radioprotection aspects linked with the management of radioactive wastes coming from the nuclear industry, at identifying the stakes of their radiological characterization, and at describing applicable methods adapted to the needs. The principles of characterization are developed and a large place is given to the experience feedback of the industrial applications of measurements performed on wastes coming from the exploitation and dismantling of various facilities (reactors, fuel cycle plants, reprocessing plants). The strategy enforced in Spain is analyzed through the experience of wastes characterization at the El Cabril storage center. A round table on the perspectives of evolution of the management of low and medium activity wastes with respect to the protection needs closes the conference. Content: 1 - characterization needs and stakes: definition of industrial radioactive wastes; radioprotection aspects linked with wastes; regulatory aspects liked with waste management and the associated studies; 2 - wastes management examples: application at Cogema; application at EdF: zoning; main nuclear waste files at the CEA; 3 - inventory of wastes from different origins and the associated radioprotection: wastes from EdF's reactors exploitation and the radioprotection aspects; nuclear wastes generated by the exploitation of La Hague plant; management of dismantling wastes at the Monts d'Arree site; 4 - radioprotection aspects linked with nuclear industry wastes: radioprotection impact of Socodei activities; impact on the public of long-term waste storage facilities; 5 - methods of radiological characterization: destructive and non-destructive analysis for wastes characterization; description of surface contamination measurement techniques; description of gamma activities and gamma imaging measurement techniques; description of neutron activation measurement

  14. Concepts and strategies for management of nuclear wastes

    International Nuclear Information System (INIS)

    Three modes of reactor strategies are chosen and discussed; (1) Once-through type light water reactor, (2) U-Pu cycle light water reactor, and (3) U-Pu cycle fast breeder reactor. The arising of wastes in each mode of nuclear fuel cycle is first estimated for unit nuclear power generation of 1 GWe.year and the amount of wastes to be managed in each year is then calculated. Assuming the 2nd and the 3rd reprocessing plants are not operative, the decrease of waste arising is also estimated, which, nevertheless, claims the need for spent fuel storage pools. In addition, the arisings of decommissioning wastes are evaluated to identify their effect on waste management. Based on above fact, a generic logic of waste management is brought about, placing major emphasis on volume reduction, barrier- and decay-effects. According to the characteristics, the wastes arisen at each stage of nuclear fuel cycle can be categorized into (1) extremely low-level waste, (2) low- and intermediate-level waste, (3) alpha-waste and (4) high-level waste, and the suitable isolation periods for the specified categories can be set by the aid of hazard index, suggesting that the disposal options may possibly be selected. The waste disposal gives environmental impacts through dispersion and migration of contained nuclides into biosphere; the dispersion and migration paths are investigated and a mathematical expression to evaluate the impacts as dose commitment is presented. A multi-barrier concept is proposed since combined artificial and natural barriers have possibility of lengthening the migration path to enable safe disposal. Finally, items of research/development in waste management are represented from the viewpoints of (1) establishment of management system, (2) safety assessment covering verification of technology and system, and (3) regulation, giving recommendations for national policy making as well as for international co-operation. (JPN)

  15. Microbial Effects on Nuclear Waste Packaging Materials

    Energy Technology Data Exchange (ETDEWEB)

    Horn, J; Martin, S; Carrillo, C; Lian, T

    2005-07-22

    Microorganisms may enhance corrosion of components of planned engineered barriers within the proposed nuclear waste repository at Yucca Mountain (YM). Corrosion could occur either directly, through processes collectively known as Microbiologically Influenced Corrosion (MIC), or indirectly, by adversely affecting the composition of water or brines that come into direct contact with engineered barrier surfaces. Microorganisms of potential concern (bacteria, archea, and fungi) include both those indigenous to Yucca Mountain and those that infiltrate during repository construction and after waste emplacement. Specific aims of the experimental program to evaluate the potential of microorganisms to affect damage to engineered barrier materials include the following: Indirect Effects--(1) Determine the limiting factors to microbial growth and activity presently in the YM environment. (2) Assess these limiting factors to aid in determining the conditions and time during repository evolution when MIC might become operant. (3) Evaluate present bacterial densities, the composition of the YM microbial community, and determining bacterial densities if limiting factors are overcome. During a major portion of the regulatory period, environmental conditions that are presently extant become reestablished. Therefore, these studies ascertain whether biomass is sufficient to cause MIC during this period and provide a baseline for determining the types of bacterial activities that may be expected. (4) Assess biogenic environmental effects, including pH, alterations to nitrate concentration in groundwater, the generation of organic acids, and metal dissolution. These factors have been shown to be those most relevant to corrosion of engineered barriers. Direct Effects--(1) Characterize and quantify microbiological effects on candidate containment materials. These studies were carried out in a number of different approaches, using whole YM microbiological communities, a subset of YM

  16. Microbial Effects on Nuclear Waste Packaging Materials

    International Nuclear Information System (INIS)

    Microorganisms may enhance corrosion of components of planned engineered barriers within the proposed nuclear waste repository at Yucca Mountain (YM). Corrosion could occur either directly, through processes collectively known as Microbiologically Influenced Corrosion (MIC), or indirectly, by adversely affecting the composition of water or brines that come into direct contact with engineered barrier surfaces. Microorganisms of potential concern (bacteria, archea, and fungi) include both those indigenous to Yucca Mountain and those that infiltrate during repository construction and after waste emplacement. Specific aims of the experimental program to evaluate the potential of microorganisms to affect damage to engineered barrier materials include the following: Indirect Effects--(1) Determine the limiting factors to microbial growth and activity presently in the YM environment. (2) Assess these limiting factors to aid in determining the conditions and time during repository evolution when MIC might become operant. (3) Evaluate present bacterial densities, the composition of the YM microbial community, and determining bacterial densities if limiting factors are overcome. During a major portion of the regulatory period, environmental conditions that are presently extant become reestablished. Therefore, these studies ascertain whether biomass is sufficient to cause MIC during this period and provide a baseline for determining the types of bacterial activities that may be expected. (4) Assess biogenic environmental effects, including pH, alterations to nitrate concentration in groundwater, the generation of organic acids, and metal dissolution. These factors have been shown to be those most relevant to corrosion of engineered barriers. Direct Effects--(1) Characterize and quantify microbiological effects on candidate containment materials. These studies were carried out in a number of different approaches, using whole YM microbiological communities, a subset of YM

  17. Nuclear waste/nuclear power: their futures are linked

    International Nuclear Information System (INIS)

    This paper briefly reviews current aspects of radioactive waste disposal techniques and transportation. Addressed are high-level and low-level radioactive wastes, interim spent fuel storage and transportation. The waste options being explored by DOE are listed. Problems of public acceptance will be more difficult to overcome than technical problems

  18. Mechanistic Understanding Of Caustic Cracking Of Carbon Steels

    International Nuclear Information System (INIS)

    Liquid waste generated by the PUREX process for separation of nuclear materials is concentrated and stored in Type IV single-shell carbon steel tanks at the Savannah River Site (SRS). The Type IV tanks for this waste do not have cooling coils and have not undergone heat treatment to stress-relieve the tanks. After the waste is concentrated by evaporation, it becomes very alkaline and can cause stress corrosion cracking (SCC) and pitting corrosion of the tank materials. SRS has experienced leakage from non-stress-relieved waste tanks constructed of A285 carbon steel and pitting of A212 carbon steel tanks in the vapor space. An investigation of tank materials has been undertaken at SRS to develop a basic understanding of caustic SCC of A285 and A212 grade carbon steels exposed to aqueous solutions, primarily containing sodium hydroxide (NaOH), sodium nitrate (NaNO3), and sodium nitrite (NaNO2) at temperatures relevant to the operating conditions of both the F and H area plants. This report presents the results of this corrosion testing program. Electrochemical tests were designed using unstressed coupons in a simulated tank environment. The purpose of this testing was to determine the corrosion susceptibility of the tank materials as a function of chemical concentration, pH, and temperature. A285 and A516 (simulates A212 carbon steel) coupons were used to investigate differences in the corrosion of these carbon steels. Electrochemical testing included measurement of the corrosion potential and polarization resistance as well as cyclic potentiodynamic polarization (CPP) testing of coupons. From the CPP experiments, corrosion characteristics were determined including: corrosion potential (Ecorr), pitting or breakdown potential (Epit), and repassivation potential (Eprot). CPP results showed no indications of localized corrosion, such as pitting, and all samples showed the formation of a stable passive layer as evidenced by the positive hysteresis during the scan

  19. Industrial Experience on the Caustic Cracking of Stainless Steels and Nickel Alloys - A Review

    Energy Technology Data Exchange (ETDEWEB)

    Rebak, R B

    2005-10-09

    Caustic environments are present in several industries, from nuclear power generation to the fabrication of alkalis and alumina. The most common material of construction is carbon steel but its application is limited to a maximum temperature of approximately 80 C. The use of Nickel (Ni) alloys is recommended at higher temperatures. Commercially pure Ni is the most resistant material for caustic applications both from the general corrosion and the stress corrosion cracking (SCC) perspectives. Nickel rich alloys also offer a good performance. The most important alloying elements are Ni and chromium (Cr). Molybdenum (Mo) is not a beneficial alloying element and it dissolves preferentially from the alloy in presence of caustic environments. Austenitic stainless steels such as type 304 and 316 seem less resistant to caustic conditions than even plain carbon steel. Experimental evidence shows that the most likely mechanism for SCC is anodic dissolution.

  20. State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992

    International Nuclear Information System (INIS)

    The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada's responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency's oversight responsibilities: (1) Assure that the health and safety of Nevada's citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository

  1. Radioactive waste management at nuclear power plant Cernavoda

    International Nuclear Information System (INIS)

    Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. The general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

  2. Nuclear Waste Management, Nuclear Power, and Energy Choices Public Preferences, Perceptions, and Trust

    CERN Document Server

    Greenberg, Michael

    2013-01-01

    Hundreds of studies have investigated public perceptions and preferences about nuclear power, waste management, and technology. However there is clear lack of uniformity in the style, aims and methods applied.  Consequently, the body of results is inconsistent and it is difficult to isolate relevant patterns or interpretations. Nuclear Waste Management, Nuclear Power and Energy Choices: Public Preferences, Perceptions and Trust presents a theoretical base for public reactions then classifies and reviews the large body of surveys carried out over the past decade.   Particular focus is placed on residents within 50 miles US nuclear waste facilities due to the disproportionate presence of nuclear factors in their lives such as the legacy of nuclear waste disposal and job dependency. The motivations and reasons for their views such as fear, attraction to the economic benefits, trust of site managers and federal agencies, cultural views, personal history, and demographic attributes of the people are also conside...

  3. High-level nuclear waste disposal: Ethical considerations

    International Nuclear Information System (INIS)

    Popular skepticism about, and moral objections to, recent legislation providing for the management and permanent disposal of high-level radioactive wastes have derived their credibility from two major sources: government procrastination in enacting waste disposal program, reinforcing public perceptions of their unprecedented danger and the inflated rhetoric and pretensions to professional omnicompetence of influential scientists with nuclear expertise. Ethical considerations not only can but must provide a mediating framework for the resolution of such a polarized political controversy. Implicit in moral objections to proposals for permanent nuclear waste disposal are concerns about three ethical principles: fairness to individuals, equitable protection among diverse social groups, and informed consent through due process and participation

  4. Progress on Radiochemical Analysis for Nuclear Waste Management in Decommissioning

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Qiao, Jixin; Shi, Keliang;

    With the increaed numbers of nuclear facilities have been closed and are being or are going to be decommissioned, it is required to characterise the produced nuclear waste for its treatment by identification of the radionuclides and qualitatively determine them. Of the radionuclides related...... separation of radionuclides. In order to improve and maintain the Nodic competence in analysis of radionculides in waste samples, a NKS B project on this topic was launched in 2009. During the first phase of the NKS-B RadWaste project (2009-2010), a good achivement has been reached on establishment...

  5. Management of nuclear airborne wastes and tritium retention

    International Nuclear Information System (INIS)

    An overall review is presented of the outcome of the research activities that have been supported by the Community programme (shared cost action) for the last years in the field of management of nuclear airborne wastes. The kinds of waste dealt with originate essentially from the reprocessing of spent nuclear fuel and from certain treatment and conditioning processes of radioactive waste. Consideration is therefore given to the management of the volatile radionuclides Krypton-85, Iodine-129, Carbon-14 and tritium followed by that of nitric oxides and radioactive aerosols. (author)

  6. Corrosion experience in calcination of liquid nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, C A

    1980-01-01

    The Waste Calcining Facility (WCF) at the Idaho National Engineering Laboratory became operational in 1963. Since that time, approximately 13,337,137 litres (3,523,375 gallons) of liquid nuclear wastes, generated during the reprocessing of spent nuclear fuel materials, have been reduced to dry granular solids. The volume reduction is about seven or eight gallons of liquid waste to one gallon of dry granular solids. This paper covers some of the corrosion experiences encountered in over fifteen years of operating that calcination facility. 7 figures, 7 tables.

  7. Advances in reprocessing technology to minimise nuclear fuel waste

    International Nuclear Information System (INIS)

    The responsible and effective management of nuclear wastes generated throughout the nuclear fuel cycle is the key element underpinning the current and future credibility of the industry. This paper presents an overview of the development of existing Purex reprocessing technology in the context of minimising waste streams arising from spent fuel reprocessing. These developments are presented in relation to BNFL's Thorp facility, designed for the reprocessing of oxide fuels. The paper proceeds to discuss potential opportunities for further waste reductions offered by radical reprocessing technologies, such as molten salts conditioning. (author)

  8. Corrosion experience in calcination of liquid nuclear waste

    International Nuclear Information System (INIS)

    The Waste Calcining Facility (WCF) at the Idaho National Engineering Laboratory became operational in 1963. Since that time, approximately 13,337,137 litres (3,523,375 gallons) of liquid nuclear wastes, generated during the reprocessing of spent nuclear fuel materials, have been reduced to dry granular solids. The volume reduction is about seven or eight gallons of liquid waste to one gallon of dry granular solids. This paper covers some of the corrosion experiences encountered in over fifteen years of operating that calcination facility. 7 figures, 7 tables

  9. Treatment and final disposal of nuclear waste

    International Nuclear Information System (INIS)

    The present background report to RD and D-programme 93 'Detailed R and D-programme 1993-1998' gives a detailed description of the state-of-the-art and future plans for safety assessments and supportive research. The technical development that is required for the construction of the encapsulation station and the deep repository for demonstration deposition is described. The report describes the need for performance and safety assessments occasioned by the above plans for activities. Against the background of the time schedule for safety reports etc., an account is given of the state-of-the-art, goals and planned work during the period with regard to the engineered barriers of spent nuclear fuel, canister material and buffer and backfill material. State-of-the-art, goals and planned work within the geosciences for groundwater movements, bedrock stability and geohydrological and rock mechanical calculation models are presented as well as the situation within the chemistry programme, with separate sections on groundwater and geochemistry, radionuclide chemistry and validation of processes in transport model and radionuclide migration. The study of such natural conditions as constitute analogues in certain respects to important chemical sorption and transport processes in a deep repository is presented. The state of knowledge concerning radionuclide transport in the biosphere and modelling of the same, as well as resulting doese to man, are described. R and D efforts associated with the development of technology that is required for repository construction, excavation of tunnels, deposition of waste and possibly necessary retrieval of canisters, as well as backfilling and sealing of the repository are presented

  10. Financial provision for future nuclear waste management in Finland

    International Nuclear Information System (INIS)

    The main principle as regards nuclear waste management in Finland is that the operator that has produced nuclear waste is responsible for the management of all such nuclear waste. It has to take care of its waste (including that of decommissioning) until it has been disposed of in a manner accepted by the authorities. Spent nuclear fuel is considered to be nuclear waste subject to disposal into a final repository. According to the Nuclear Energy Act, all nuclear waste produced in Finland must be handled, stored and disposed of in Finland. The spent fuel and other nuclear wastes are stored at the power plant sites until they are disposed of. At the both two sites there already are the final repositories for low and intermediate level waste. The funding system is based on the principle that, if a nuclear facility would stop its operation and also stop to produce more waste, the money in the Fund and the securities given to the State would, together, always suffice to handle the situation and take care of the management of all the existing waste and dismantling and decommissioning of the plant. As the actual waste management measures would not be taken immediately, the interest accrued, in the meantime, by this existing capital is used to compensate for the inflation and cost escalation. The critical question is how the system takes into account the difficulty of arriving at reliable estimates. The Finnish funding system contains some built-in features to minimise the risk of the State having to contribute additional funds to carrying out these operations. The system continuously requires new updated estimates that must take into account the practical experience accumulating world-wide. The estimates must, however, always be based on technology currently available. Additionally, the law also requires that the uncertainty of available information about prices and costs shall be taken into account, in a reasonable manner, as raising the estimated liability. In the case

  11. Nuclear waste management programme 1999 for the Loviisa and Olkiluoto nuclear power plants; Olkiluodon ja Loviisan voimalaitosten ydinjaetehuollon ohjelma 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    A joint company Posiva Oy founded by nuclear energy producing Teollisuuden Voima Oy (TVO) and Imatran Voima Oy (IVO) coordinates the research work of the companies on nuclear waste management in Finland. in Posiva`s Nuclear Waste Management Programme 1999, an account of the nuclear waste management measures of TVO and IVO is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, nuclear waste management situation and the programme of activities are reported. The nuclear waste management research for the year 1999 and more generally for the years 1999-2003 is presented 3 refs.

  12. Management of radioactive waste generated in nuclear medicine

    International Nuclear Information System (INIS)

    Nuclear medicine is a clinical specialty in which radioactive material is used in non-encapsulated form, for the diagnosis and treatment of patients. Nuclear medicine involves administering to a patient a radioactive substance, usually liquid, both diagnostic and therapeutic purposes. This process generates solid radioactive waste (syringes, vials, gloves) and liquid (mainly the patient's urine). (Author)

  13. Radiation effects in a model ceramic for nuclear waste disposal

    Science.gov (United States)

    Devanathan, Ram; Weber, William J.

    2007-04-01

    The safe immobilization of nuclear waste in geological repositories is one of the major scientific challenges facing humanity today. Crystalline ceramics hold the promise of locking up actinides from nuclear fuel and excess weapons plutonium in their structure thereby isolating them from the environment. This paper presents the atomistic details of radiation damage in a model ceramic, zircon.

  14. Radioactive waste management at the Peruvian Nuclear Energy Institute

    International Nuclear Information System (INIS)

    A brief account of current radioactive liquid waste management practices at the Peruvian Nuclear Energy Institute (IPEN), is presented. The storage and disposal systems and facilities to be provided at the future Peruvian Nuclear Research Centre (CNIP) at Huarangal, 40 km to the North of Lima, are described. (Author)

  15. Shipments of nuclear fuel and waste: are they really safe

    International Nuclear Information System (INIS)

    This paper presents a summarized status report on the potential hazards of shipping nuclear materials. Principles of nuclear shipment safety, government regulations, shipment information, quality assurance, types of radioactive wastes, package integrity, packaging materials, number of shipments, accidents, and accident risk are considered

  16. Shipments of nuclear fuel and waste: are they really safe

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    This paper presents a summarized status report on the potential hazards of shipping nuclear materials. Principles of nuclear shipment safety, government regulations, shipment information, quality assurance, types of radioactive wastes, package integrity, packaging materials, number of shipments, accidents, and accident risk are considered. (LK)

  17. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jooho, W.; Baldwin, G. T.

    2005-04-01

    One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long

  18. Nevada Nuclear Waste Storage Investigations Project: Analysis of horizontal waste emplacement boreholes of a nuclear waste repository in tuff

    International Nuclear Information System (INIS)

    In support of the design of a nuclear waste repository in tuff, two dimensional thermal and thermal-mechanical analyses of horizontal emplacement boreholes were performed using finite-element and boundary-element codes. In the finite-element analyses five different equivalent continuum models of a tuff rock mass were used to investigate the state of deformation and stress around the borehole for times up to 300 years following waste emplacement. These models were an isotropic linear elastic model, an ubiquitous joint model with single and orthogonal joints, an a compliant joint model also with single and orthogonal joints. The case of boreholes intersected by discrete fractures was analyzed using boundary-element models. The results of analyses using the various models of the borehole were consistent and indicated stable conditions even when low estimates of the strength of the joints within the tuff rock mass were assumed. 25 refs

  19. Safety aspects of nuclear waste disposal in space

    Science.gov (United States)

    Rice, E. E.; Edgecombe, D. S.; Compton, P. R.

    1981-01-01

    Safety issues involved in the disposal of nuclear wastes in space as a complement to mined geologic repositories are examined as part of an assessment of the feasibility of nuclear waste disposal in space. General safety guidelines for space disposal developed in the areas of radiation exposure and shielding, containment, accident environments, criticality, post-accident recovery, monitoring systems and isolation are presented for a nuclear waste disposal in space mission employing conventional space technology such as the Space Shuttle. The current reference concept under consideration by NASA and DOE is then examined in detail, with attention given to the waste source and mix, the waste form, waste processing and payload fabrication, shipping casks and ground transport vehicles, launch site operations and facilities, Shuttle-derived launch vehicle, orbit transfer vehicle, orbital operations and space destination, and the system safety aspects of the concept are discussed for each component. It is pointed out that future work remains in the development of an improved basis for the safety guidelines and the determination of the possible benefits and costs of the space disposal option for nuclear wastes.

  20. Radioactive waste management of the nuclear medicine services

    International Nuclear Information System (INIS)

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  1. Conditioning of nuclear cladding wastes by melting

    International Nuclear Information System (INIS)

    This paper discusses a cold-crucible induction melting process to condition cladding waste from irradiated fast breeder reactor fuel. The process has been developed by the CEA at Marcoule (France) as part of a major R and D program. It has been qualified at industrial scale on nonradioactive waste, and at laboratory scale on radioactive waste: several radioactive ingots have been produced from actual stainless steel or zircaloy hulls. The results confirm the numerous advantages of this containment method

  2. Leaching of nuclear power reactor wastes forms

    International Nuclear Information System (INIS)

    The leaching tests for power reactor wastes carried out at IPEN/CNEN-SP are described. These waste forms consist mainly of spent resins and boric acid concentrates solidified in ordinary Portland cement. All tests were conducted according to the ISO and IAEA recommendations. 3 years leaching results are reported, determining cesium and strontium diffusivity coefficients for boric acid waste form and ion-exchange resins. (Author)

  3. State control of low-level nuclear waste disposal

    International Nuclear Information System (INIS)

    The siting and licensing of nuclear plants has been hampered by regulatory conflicts between individual states and the Federal government, although the states have moved to exercise control over low-level radioactive waste management. Recommendations for a national waste management plan reflect public concerns about health and safety rather than any evidence that state control has been inadequate. Congressional study of waste management identified several needs to be met in order to have uniform standards of protection for public health and the environment. A Nuclear Regulatory Commission (NRC) task force, concurring with the desirability of a national plan, concluded that no legislation is presently needed to reassert Federal control. The status involved indicated a need to continue direct involvement and control as a condition for receiving nuclear wastes. The New Mexico moratorium on licensing is viewed as an illustration of a state asserting control when responsibility is not clearly defined

  4. Regulatory safety aspects of nuclear waste management operations in India

    International Nuclear Information System (INIS)

    The Department of Atomic Energy in India as part of its programme to harness the nuclear energy for generation of nuclear power has been operating a whole range of nuclear fuel cycle facilities including waste management plants for more than four decades. The waste management plants include three high level waste immobilisation plants, one in operation, one under commissioning and one more under construction. Atomic Energy Regulatory Board is mandated to review and authorise from the safety angle the siting, the design, the construction and the operation of the waste management plants. The regulatory procedures, which involve multi-tier review adopted for ensuring the safety of these facilities, are described in this paper. (author)

  5. Rietveld analysis of ceramic nuclear waste forms

    International Nuclear Information System (INIS)

    Powder X-ray diffraction patterns were collected from three titanate waste forms - a calcine powder, a prototype ceramic without waste, and a ceramic containing 10 wt% JW-A simulated waste - and interpreted quantitatively using the Rietveld method. The calcine consisted of fluorite, pyrochlore, rutile, and amorphous material. The prototype waste form contained rutile, hollandite, zirconolite and perovskite. The phase constitution of the JW-A ceramic was freudenbergite, loveringite, hollandite, zirconolite, perovskite and baddeleyite. Procedures for the collection of X-ray data are described, as are assumptions inherent in the Rietveld approach. A selection of refined crystal data are presented

  6. Leaching of nuclear power reactor waste forms

    International Nuclear Information System (INIS)

    The leaching tests for immobilized power reactor wastes carried out at IPEN are described. These wastes forms consist mainly of spent resins and boric acid concentrates solidified in ordinary Portland cement. All tests were conducted according to the ISO and IAEA recommendations. Three years leaching results are reported. The cesium diffuvity coefficients determined out of these results are about 1 x 10-8 cm2/s for boric acid waste form and 9 x 10-9 cm2/s for ion-exchange resin waste. Strontium diffusivity coefficients found are about 3 x 10-11 cm2/s and 9 x 10-11 cm2/s respectively. (Author)

  7. Responsible disposal of high level nuclear waste

    International Nuclear Information System (INIS)

    In the United States today are approximately 100 million gallons of high-level radioactive waste [HLW] containing more than 1 billion curies of radioactivity. This waste has been generated primarily from reprocessing operations used in the production of plutonium and tritium for defense needs. The waste is most often handled and stored in a liquid or semi-liquid form and placed in large underground tanks. Many of these tanks are now over a quarter of a century old and materials problems and concerns have arisen. This paper reports on what is now needed, a more effective means for not only storing this waste, but for permanently disposing of it

  8. Rietveld analysis of ceramic nuclear waste forms

    Energy Technology Data Exchange (ETDEWEB)

    White, T.J. [Univ. of South Australia, Ingle Farm (Australia); Mitamura, H. [Japan Atomic Energy Research Institute, Ibaraki (Japan)

    1994-12-31

    Powder X-ray diffraction patterns were collected from three titanate waste forms - a calcine powder, a prototype ceramic without waste, and a ceramic containing 10 wt% JW-A simulated waste - and interpreted quantitatively using the Rietveld method. The calcine consisted of fluorite, pyrochlore, rutile, and amorphous material. The prototype waste form contained rutile, hollandite, zirconolite and perovskite. The phase constitution of the JW-A ceramic was freudenbergite, loveringite, hollandite, zirconolite, perovskite and baddeleyite. Procedures for the collection of X-ray data are described, as are assumptions inherent in the Rietveld approach. A selection of refined crystal data are presented.

  9. Management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    The importance of radioactive wastes from nuclear power plants (NPPs) results primarily from their large amounts. In NPPs more radioactive wastes arise than in all other plants of the nuclear fuel cycle, with the exception of uranium mills. Although the volume is great, NPP wastes are relatively low in activity and radiotoxicity and short in half-life. Several methods for treatment of NPP wastes are available that meet all the relevant requirements and they have attained high technical standards and are highly reliable. Consequently, the discharge of radionuclides with liquid and gaseous effluents and the resulting dose commitment to the general public are far below established limits. The quality of the conditioned wastes conforms to the requirements for ultimate disposal. The final disposal of NPP wastes has already been demonstrated successfully in several places and the feasibility of NPP decommissioning and management of the wastes arising in this process have been proved. The problems associated with the management of radioactive wastes from NPPs have been solved both scientifically and technically; there is no urgent need for improvement. This is why for new developments cost-benefit aspects must be considered, including the dose commitment to the operating staff and general aspects such as public acceptance and socio-ethical questions. Spectacular new developments are not to be expected in the near future. However, by continuous improvement of details and optimization of the whole system useful contributions can still be made to develop nuclear technology further. (author)

  10. Expected brine movement at potential nuclear waste repository salt sites

    Energy Technology Data Exchange (ETDEWEB)

    McCauley, V.S.; Raines, G.E.

    1987-08-01

    The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.

  11. Radioactive waste and nuclear power: a personal perspective

    International Nuclear Information System (INIS)

    An overview is given of all major sources of radioactive materials in this country, including spent fuel, high-level waste, TRU waste, low-level waste, mill tailings, remedial action programs, decontamination and decommissioning, and airborne waste. These materials are characterized in terms of location, volume, age, radioactivity, thermal power, physical properties, and chemical properties. The role of nuclear power in an oxidized and oxidizing world is discussed in terms of environmental benefits and the conservation of our limited supply of chemically reduced matter; i.e., material that can be oxidized or burned

  12. Recent developments in waste characterization at Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    The waste characterization program (WCP) at Chalk River Nuclear Laboratories (CRNL) was initiated in 1982 to determine the physical, chemical and radiological properties of wastes intended for disposal in IRUS (Intrusion Resistant Underground Structure), a belowground vault to be constructed at CRNL. During the last year, work on the WCP has centered on determining the radionuclide inventories in candidate wastes for IRUS by gamma-ray monitoring and destructive radiochemical analysis. This paper presents the technical problems associated with monitoring various waste forms (geometry considerations, shielding problems, operating environment, etc.) and also presents details of the destructive radiochemical analysis program

  13. Waste management at the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    In the Karlsruhe Nuclear Research Center the responsibility for waste management is concentrated in the Decontamination Department which serves to collect and transport all liquid waste and solid material from central areas in the center for further waste treatment, clean radioactive equipment for repair and re-use or for recycling of material, remove from the liquid effluents any radioactive and chemical pollutants as specified in legislation on the protection of waters, convert radioactive wastes into mechanically and chemically stable forms allowing them to be transported into a repository. (orig./RW)

  14. Waste management of the Nuclear Technology Development Center - CDTN

    International Nuclear Information System (INIS)

    Liquid and solid wastes of low radiation level are produced at the Nuclear Technology Development Centre (CDTN). Trying to minimise the waste volume and to give proper treatment, the wastes, are segregated at their origin according their radiological, chemistry and physical characteristics. The Radioactive Waste Program was established in 1983 based on CNEN resolution 6/73 and more recently modernized following CNEN Norm NE-6.05. This paper describes all activities involved in CDTN's Program. (B.C.A.). 6 refs, 02 tabs, 01 fig

  15. Knowledge in the area of nuclear wastes 1998

    International Nuclear Information System (INIS)

    The R and D program for nuclear wastes performed by Swedish utilities is critically discussed by the independent committee KASAM. The following major issues are treated: Duration in time of the ethical responsibility; The decision process; Radioactive emissions from nuclear power and from other energy sources; Risks in transport of spent nuclear fuels to the disposal facility; Safety analysis of the repository; Cracks in rock; Processes induced by microorganisms that might influence the repository; Decommissioning; International review; The R and D program of the European Union; Foreign radioactive wastes in Sweden

  16. The development of engineering coursework on nuclear waste management

    International Nuclear Information System (INIS)

    Many nuclear engineering programs offer a course in nuclear waste management to acquaint students with the handling of both high and low-level radioactive waste material and the methods used for their final disposal. Courses on this topic have been taught at the University of Nevada, Las Vegas to serve the needs of the local community involved in Yucca Mountain site characterization and Nuclear Test Site employees. Topic of importance in the engineering curriculum are discussed along with the need for courses at several academic levels

  17. Managing the high level waste nuclear regulatory commission licensing process

    International Nuclear Information System (INIS)

    This paper reports that the process for obtaining Nuclear Regulatory Commission permits for the high level waste storage facility is basically the same process commercial nuclear power plants followed to obtain construction permits and operating licenses for their facilities. Therefore, the experience from licensing commercial reactors can be applied to the high level waste facility. Proper management of the licensing process will be the key to the successful project. The management of the licensing process was categorized into four areas as follows: responsibility, organization, communication and documentation. Drawing on experience from nuclear power plant licensing and basic management principles, the management requirement for successfully accomplishing the project goals are discussed

  18. Public concerns and choices regarding nuclear waste repositories

    Energy Technology Data Exchange (ETDEWEB)

    Rankin, W.L.; Nealey, S.M.

    1981-06-01

    Survey research on nuclear power issues conducted in the late 1970's has determined that nuclear waste management is now considered to be one of the most important nuclear power issues both by the US public and by key leadership groups. The purpose of this research was to determine the importance placed on specific issues associated with high-level waste disposal. In addition, policy option choices were asked regarding the siting of both low-level and high-level nuclear waste repositories. A purposive sampling strategy was used to select six groups of respondents. Averaged across the six respondent groups, the leakage of liquid wastes from storage tanks was seen as the most important high-level waste issue. There was also general agreement that the issue regarding water entering the final repository and carrying radioactive wastes away was second in importance. Overall, the third most important issue was the corrosion of the metal containers used in the high-level waste repository. There was general agreement among groups that the fourth most important issue was reducing safety to cut costs. The fifth most important issue was radioactive waste transportation accidents. Overall, the issues ranked sixth and seventh were, respectively, workers' safety and earthquakes damaging the repository and releasing radioactivity. The eighth most important issue, overall, was regarding explosions in the repository from too much radioactivity, which is something that is not possible. There was general agreement across all six respondent groups that the two least important issues involved people accidentally digging into the site and the issue that the repository might cost too much and would therefore raise electricity bills. These data indicate that the concerns of nuclear waste technologists and other public groups do not always overlap.

  19. Public concerns and choices regarding nuclear-waste repositories

    International Nuclear Information System (INIS)

    Survey research on nuclear power issues conducted in the late 1970's has determined that nuclear waste management is now considered to be one of the most important nuclear power issues both by the US public and by key leadership groups. The purpose of this research was to determine the importance placed on specific issues associated with high-level waste disposal. In addition, policy option choices were asked regarding the siting of both low-level and high-level nuclear waste repositories. A purposive sampling strategy was used to select six groups of respondents. Averaged across the six respondent groups, the leakage of liquid wastes from storage tanks was seen as the most important high-level waste issue. There was also general agreement that the issue regarding water entering the final repository and carrying radioactive wastes away was second in importance. Overall, the third most important issue was the corrosion of the metal containers used in the high-level waste repository. There was general agreement among groups that the fourth most important issue was reducing safety to cut costs. The fifth most important issue was radioactive waste transportation accidents. Overall, the issues ranked sixth and seventh were, respectively, workers' safety and earthquakes damaging the repository and releasing radioactivity. The eighth most important issue, overall, was regarding explosions in the repository from too much radioactivity, which is something that is not possible. There was general agreement across all six respondent groups that the two least important issues involved people accidentally digging into the site and the issue that the repository might cost too much and would therefore raise electricity bills. These data indicate that the concerns of nuclear waste technologists and other public groups do not always overlap

  20. Sulphate in Liquid Nuclear Waste: from Production to Containment

    International Nuclear Information System (INIS)

    Nuclear industry produces a wide range of low and intermediate level liquid radioactive wastes which can include different radionuclides such as 90Sr. In La Hague reprocessing plant and in the nuclear research centers of CEA (Commissariat a l'Energie Atomique), the coprecipitation of strontium with barium sulphate is the technique used to treat selectively these contaminated streams with the best efficiency. After the decontamination process, low and intermediate level activity wastes incorporating significant quantities of sulphate are obtained. The challenge is to find a matrix easy to form and with a good chemical durability which is able to confine this kind of nuclear waste. The current process used to contain sulphate-rich nuclear wastes is bituminization. However, in order to improve properties of containment matrices and simplify the process, CEA has chosen to supervise researches on other materials such as cements or glasses. Indeed, cements are widely used for the immobilization of a variety of wastes (low and intermediate level wastes) and they may be an alternative matrix to bitumen. Even if Portland cement, which is extensively used in the nuclear industry, presents some disadvantages for the containment of sulphate-rich nuclear wastes (risk of swelling and cracking due to delayed ettringite formation), other cement systems, such as calcium sulfo-aluminate binders, may be valuable candidates. Another matrix to confine sulphate-rich waste could be the glass. One of the advantages of this material is that it could also immobilize sulphate containing high level nuclear waste which is present in some countries. This waste comes from the use of ferrous sulfamate as a reducing agent for the conversion of Pu4+ to Pu3+ in the partitioning stage of the actinides during reprocessing. Sulphate solubility in borosilicate glasses has already been studied in CEA at laboratory and pilot scales. At a pilot scale, low level liquid waste has been vitrified. A test was

  1. The Swedish system for funding of nuclear waste management

    International Nuclear Information System (INIS)

    Nuclear activities in Sweden goes back to early 1950's. Research and development on spent fuel disposal in Sweden started in earnest with the report of the AKA-commission 1976, which outlined a complete system for the management of spent fuel and associated waste, including how to handle the costs. Components of the system, mentioned in the AKA-report, such as a sea transportation (MS Sigyn), a central spent fuel storage facility (CLAB) and a final repository for operational waste (SFR) have since been constructed and taken in operation. The research and planning for the additional facilities needed for a complete system is in an advanced stage. A nuclear waste fund has also been created, based on a special fee on nuclear power production. During the 1970's the nuclear power utilities established their own internal funds for future waste management expenses. These funds were transferred to the government-run financing system established in 1981 when the Swedish parliament passed the Act on the Financing of Future Expenses for Spent Nuclear Fuel etc. The fees to be paid into the Fund are to be based on the assumption that each reactor generates electricity for 25 years. These fees, plus the interest on the money already deposited in the Fund, must meet all expenses for handling spent fuel, dismantling facilities and for dealing with radioactive decommissioning waste. A guarantee shall compensate for the eventuality of a nuclear power plant being closed before the end of the 25-year earning period. The type of guarantee must be available until all nuclear waste has been placed in a repository and must cover contingencies for the waste programme. This guarantee will be used if expenses for future nuclear waste management become higher than expected, if these expenses have to be met earlier than expected, or if the actual amount in the Fund is lower than was estimated. The process of yearly cost calculations, review and determination of fees and guarantees is well

  2. Optimized waste management for low and intermediate level nuclear waste at the LOVIISA NPP in Finland

    International Nuclear Information System (INIS)

    The Loviisa NPP has two 488 MWe VVER-440 pressurized water reactors. Unit 1 was taken into use in 1977 and unit 2 in 1980. After the life time extension these units will be operating until the year 2027 and 2030, respectively. The Finnish legislation stipulates that the waste producer is totally responsible for the management of all its radioactive waste, including their disposal. According to this principle the utilities are also responsible for making economical reservations for all future activities. The utilities have to put money into a separate waste management fund to cover all the costs of future waste management activities. Existing legislation and regulations have created a situation, which encourages the utilities to carry out all activities on a safe way, and to optimize the management chain for most economical result. Even before the present legislation the Finnish nuclear utilities, Fortum Power and Heat Oy and Teollisuuden Voima Oyj (TVO), have carried out an intensive R and D program for management of their own nuclear wastes. These utilities have founded a joint company, Posiva Oy, to take care of their spent nuclear fuel. Joining the efforts results in efficient solution for spent nuclear fuel. From start of the operation both nuclear utilities studied different options for management of their low and intermediate level waste. Quite soon the principle was adopted to take care of all low and intermediate level waste at the power plant sites. During these early years of operation a management concept was formed how to handle, treat, store and dispose of both low and intermediate level maintenance waste and decommissioning waste at the power plant site. Since all these steps are managed by the same organization, the whole waste management is optimized from the collection of waste to the final disposal. (orig.)

  3. Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography

    OpenAIRE

    Jonkmans, G.; Anghel, V. N. P.; Jewett, C.; Thompson, M.

    2012-01-01

    This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry stor...

  4. Overcoming barriers to public understanding of nuclear waste management

    International Nuclear Information System (INIS)

    Communication with the public to promote public understanding of, and participation in, nuclear waste issues is crucial. However, such communication with the public is falling short. One of the major reasons for this failure is that the public feels it cannot trust the motivations or actions of USDOE. The biggest barrier to public involvement in nuclear waste issues is the lack of trust in those who invite us to be involved. Many methods could be employed to increase communication and public involvement in complex and technical nuclear matters. This paper discusses the authors' observations of how USDOE's loss of credibility has affected the high-level nuclear waste repository siting process and suggests methods to overcome this primary barrier

  5. General and regulatory aspects of nuclear waste disposal in Finland

    International Nuclear Information System (INIS)

    The Minister of Trade and Industry has recently appointed a committee to review the legislation in the nuclear energy field. The mandate of the committee includes the formulation of a law on nuclear waste management, which problem is also the subject of a current research and development programme. Licensing and control measures for nuclear installations already exist and these do include general safety measures relating to the management of nuclear waste. There are three types of licence - construction licence (including site approval), operating licence and fuel licence - given by the Ministry of Trade and Industry after consultation with various bodies, notably, the Institute of Radiation Protection. Conditions may be imposed on granting a licence, and periodic inspections are carried out during the operation of the installation. This licensing procedure, modified when necessary, could be applied to waste disposal facilities. (NEA)

  6. High Resolution Sensor for Nuclear Waste Characterization

    International Nuclear Information System (INIS)

    Gamma ray spectrometers are an important tool in the characterization of radioactive waste. Important requirements for gamma ray spectrometers used in this application include good energy resolution, high detection efficiency, compact size, light weight, portability, and low power requirements. None of the available spectrometers satisfy all of these requirements. The goal of the Phase I research was to investigate lanthanum halide and related scintillators for nuclear waste clean-up. LaBr3:Ce remains a very promising scintillator with high light yield and fast response. CeBr3 is attractive because it is very similar to LaBr3:Ce in terms of scintillation properties and also has the advantage of much lower self-radioactivity, which may be important in some applications. CeBr3 also shows slightly higher light yield at higher temperatures than LaBr3 and may be easier to produce with high uniformity in large volume since it does not require any dopants. Among the mixed lanthanum halides, the light yield of LaBrxI3-x:Ce is lower and the difference in crystal structure of the binaries (LaBr3 and LaI3) makes it difficult to grow high quality crystals of the ternary as the iodine concentration is increased. On the other hand, LaBrxI3-x:Ce provides excellent performance. Its light output is high and it provides fast response. The crystal structures of the two binaries (LaBr3 and LaCl3) are very similar. Overall, its scintillation properties are very similar to those for LaBr3:Ce. While the gamma-ray stopping efficiency of LaBrxI3-x:Ce is lower than that for LaBr3:Ce (primarily because the density of LaCl3 is lower than that of LaBr3), it may be easier to grow large crystals of LaBrxI3-x:Ce than LaBr3:Ce since in some instances (for example, CdxZn1-xTe), the ternary compounds provide increased flexibility in the crystal lattice. Among the new dopants, Eu2+ and Pr3+, tried in LaBr3 host crystals, the Eu2+ doped samples exhibited low light output. This was mostly because a

  7. Nuclear wastes future: results and forecasting

    International Nuclear Information System (INIS)

    Since many years, the CEA is greatly involved in the research programs on the long-dated management of radioactive wastes. This document presents the CEA development in the following domains: the spent fuel processing, the high separation process, the environmental behavior of wastes packages, the glass performance and the apatites behavior in the new matrix. (A.L.B.)

  8. Nuclear Waste: Increasing Scale and Sociopolitical Impacts

    Science.gov (United States)

    La Porte, Todd R.

    1978-01-01

    Discusses the impact of radioactive waste management system on social and political development. The article also presents (1) types of information necessary to estimate the costs and consequences of radioactive waste management; and (2) an index of radioactive hazards to improve the basis for policy decisions. (HM)

  9. Science, Society, and America's Nuclear Waste: The Waste Management System, Unit 4. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 4 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office Civilian Radioactive Waste Management. The goal of this unit is to explain how transportation, a geologic repository, and the multi-purpose canister will work together to provide short-term and long-term…

  10. Conflict, location, and politics: Siting a nuclear waste repository

    International Nuclear Information System (INIS)

    Nuclear power and the management of high-level radioactive waste is examined with the goal of explaining the forces driving the formulation of the 1982 Nuclear Waste Policy Act and a subsequent decision to site a nuclear waste repository at Yucca Mountain, Nevada. The study draws upon geographic, political, economic, and organizational factors to examine the commitment to dispose of spent fuel in a geologic repository located in Nevada or in Utah, Texas, Mississippi, Louisiana, or at Hanford Washington. Special attention is given to the impact of location, science and technology on the definition of the nuclear waste problem and political agendas, public participation, and the power of the nuclear establishment. The study finds that the choice of a Yucca Mountain Nevada as the preferred site for a repository was based more on technological precedent and political-economic expediency than on the demonstrated superiority of that site's geology. Conflict over a repository location is interpreted as a symptom of more fundamental conflicts concerning: the credibility of nuclear science, the legitimacy of federal authority and administration, and the priorities of environmental protection and a nuclear economy

  11. Shifting strategies and precarious progress: Nuclear waste management in Canada

    International Nuclear Information System (INIS)

    Canada has a lengthy history of trying to find a path for dealing with radioactive spent fuel and nuclear waste from its nuclear reactors. In the last decade, it has taken major strides towards this goal by evolving a process through which a site for a geological repository to sequester nuclear waste is to be selected. The Canadian Nuclear Waste Management Organization (NWMO) is in the early stages of the process of finding a community that is willing to host such a repository. Differences between the broad principles underlying siting and the processes for actually selecting the site have emerged as the NWMO proceeds with engaging local governments and specific communities. These differences and other conflicts, especially over new nuclear reactor construction, might pose hurdles in the path of successfully setting up a repository. - Highlights: • Canada has set up a process for siting a geological repository for nuclear waste. • The current challenge is to find a community willing to host such a repository. • Authorities are luring communities with the promise of jobs and local investment. • Potential new nuclear reactor construction might become a locus of conflict. • Success in actually setting up a repository is by no means guaranteed

  12. Economic evaluation of nuclear waste transportation casks

    International Nuclear Information System (INIS)

    A method is described which allows the systematic economic evaluation of transportation cask designs which meet the requirements of the Test and Evaluation Facility (TEF) program. The heart of the method described is the Waste Management Transportation Model. This model uses a set of computer-based algorithms to assemble specific case information input, combine this input with the data base of transportation information maintained within the model, and calculate the cask types and quantities necessary, the cask utilization factors, and the total costs for each transport line specified. The model is capable of handling a large variety of transportation problems given the specific input related to each type. Three combinations of waste packaging facilities were examined. The first assumes all consolidation and packaging occurs at an existing hot cell. The second assumes all consolidation and packaging is done at the TEF site. The third combination assumes that spent fuels are consolidated at an existing hot cell while waste packaging occurs at the TEF site. Some of the general findings are: (1) defense high-level waste (DHLW) is generally lower in cost than SF as the prime waste form because of the fewer number of shipments required prior to the waste consolidation activity; (2) when DHLW is the prime waste form, it is beneficial to locate the packaging facility (PF) close to the TEF site because the packaged waste form is heavier, more costly to transport; (3) when SF is the prime waste form, it is beneficial to locate the PF close to the waste source to reduce the length of the transport links containing unconsolidated spent fuel assemblies; and (4) truck casks, and legal weight truck casks in particular, are generally superior to the rail casks on an economic basis

  13. Design of Radioactive Waste Management Systems at Nuclear Power Plants

    International Nuclear Information System (INIS)

    This Safety Guide is addressed to the administrative and technical authorities and specialists dealing with the design, construction and operation of nuclear power plants, and in particular waste management facilities at nuclear power plants. This Guide has been prepared as part of the IAEA Waste Handling, Treatment and Storage programme. It is a follow-up document to the Code of Practice on Management of Radioactive Wastes from Nuclear Power Plants published in 1985 in the IAEA Safety Standards, Safety Series No. 69, in which basic principles for management of radioactive wastes at nuclear power plants are set out. The IAEA has established wide ranging programmes to provide Member States with guidance on different aspects of safety and technology related to thermal neutron power reactors and associated nuclear fuel cycle operations, including those for management of radioactive wastes. There are many IAEA publications related to various technical and safety aspects of different nuclear energy applications. All these publications are issued by the Agency for the use of Member States in connection with their own nuclear technological safety requirements. They are based on national experience contributed by experts from different countries and relate to common features in approaches to the problems discussed. However, the final decision and legal responsibility in any regulatory procedure always rest with the Member State. This particular Guide aims to provide general and detailed principles for the design of waste management facilities at nuclear power plants. It emphasizes what and how specific safety requirements for the management of radioactive wastes from nuclear power plants can be met in the design and construction stage. The safety requirements for operation of such facilities will be considered in the Agency's next Safety Series publication, Safety Guide 50-SG-011, Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants

  14. Alternate nuclear waste forms and interactions in geologic media

    International Nuclear Information System (INIS)

    The primary purposes of the conference on Alternate Nuclear Waste Forms and Interactions in Geologic Media were: First, to provide an opportunity for a review of the status of the research on some of the candidate alternative waste forms; second, to provide an opportunity for comparing the characteristics of alternate waste forms to those of glasses; and third, to stimulate increased interactions between those research groups that were engaged in a more basic approach to characterizing waste forms and those who were concerned with more applied aspects such as the processing of these materials. The motivating philosophy behind this third purpose of the conference was based on the idea that by operating from the soundest possible fundamental base for any of the candidate waste forms, hopefully any future unpleasant surprise - such as that alluded to earlier in the case of glass waste forms - could be avoided. Separate abstracts have been prepared for individual papers for inclusion in the Energy Data Base

  15. Addressing ethical considerations about nuclear fuel waste management

    International Nuclear Information System (INIS)

    Ethical considerations will be important in making decisions about the long-term management of nuclear fuel waste. Public discussions of nuclear fuel waste management are dominated by questions related to values, fairness, rights and responsibilities. To address public concerns, it is important to demonstrate that ethical responsibilities associated with the current management of the waste are being fulfilled. It is also important to show that our responsibilities to future generations can be met, and that ethical principles will be applied to the implementation of disposal. Canada's nuclear fuel waste disposal concept, as put forward in an Environmental Impact Statement by Atomic Energy of Canada Limited (AECL), is currently under public review by a Federal Environmental Assessment Panel. Following this review, recommendations will be made about the direction that Canada should take for the long-term management of this waste. This paper discusses the ethical principles that are seen to apply to geological disposal and illustrates how the Canadian approach to nuclear fuel waste management can meet the challenge of fulfilling these responsibilities. The author suggests that our ethical responsibilities require that adaptable technologies to site, design, construct, operate decommission and close disposal facilities should de developed. We cannot, and should not, present future generations from exercising control over what they inherit, nor control whether they modify or even reverse today's decisions if that is what they deem to be the right thing to do. (author)

  16. EU Support towards Romania to Get Safe Nuclear Waste Management

    International Nuclear Information System (INIS)

    European Union's programs continue to provide assistance to Romania for accelerating and completing the safe nuclear waste management. The sources of radioactive waste in Romania are users of radiation and radioactive materials in industry, including nuclear electricity generation, back-end nuclear fuel cycle activities and decommissioning, the operation of research reactors, the use of radiation and radioactive material in medicine, agriculture, industry and research, processing of material containing natural radionuclides. At this moment, in Romania there is a single repository for storage of radioactive waste: National Repository for Low and Intermediate Radioactive Waste (undergoing a modernisation process)-Baita, Bihor county, sited in Apuseni mountains. With EU assistance, ANDRAD has in view the achievement of a final repository for low and medium level waste which will be operational by 2014 and will be situated in the Saligny site (Dobrogea area). This paper presents the current status of the activities carried on in order to complete the safe nuclear waste management disposal in Romania, with assistance from the EU.(author).

  17. Improvements of radioactive waste management at WWER nuclear power plants

    International Nuclear Information System (INIS)

    This report is part of a systematic IAEA effort to improve waste management practices at WWER plants and to make them consistent with the current requirements and standards for safe and reliable operation of nuclear power plants. The report reviews the wet and dry solid waste management practices at the various types of WWER nuclear power plants (NPP) and describes approaches and recent achievements in waste minimization. Waste minimization practices in use at western PWRs are reviewed and compared, and their applicability at WWER plants is evaluated. Radioactive waste volume reduction issues and waste management practices are reflected in many IAEA publications. However, aspects of waste minimization specific to individual WWER nuclear power plant designs and WWER waste management policies are not addressed extensively in those publications. This report covers the important aspects applicable to the improvement of waste management at WWER NPP, including both plant-level and country-level considerations. It is recognized that most WWER plants are already implementing many of these concepts and recommendations with varying degrees of success; others will benefit from the included considerations. The major issues addressed are: - Review of current waste management policies and practices related to WWERs and western PWRs, including the influence of the original design concepts and significant modifications, liquid waste discharge limits and dry solid waste clearance levels applied in individual countries, national policies and laws, and other relevant aspects affecting the nature and quantities of waste arisings; - Identification of strategies and methods for improving the radioactive waste management generated in normal operation and maintenance at WWERs. This report is a composite (combination) of the two separate initiatives mentioned above. The first draft report was prepared at the meeting 26-30 May 1997 by five consultants. The draft was improved during an

  18. Waste management in the Institute for Nuclear Sciences 'Vinca' - Belgrade

    International Nuclear Information System (INIS)

    The Vinca Institute of Nuclear Sciences served for many years as the only Yugoslav (Serbia and Montenegro) nuclear institute. Therefore, it acted for many years as national storage facility for the radioactive waste from all institutional (medical, military, etc.) activities. The interim storage was situated within the Vinca Institute historically at several different places. The main fraction of the wastes is stored in two metallic hangars. In addition, underground stainless steel tanks in concrete shields have been constructed to accept all processed liquid waste from the research reactor RA. The current situation of the interim storage facilities is not satisfactory. However, the principle limitation for improvements of the waste management at the Vinca Institute lies in the fact that long-term solutions cannot be addressed at the moment. Plans for a final repository for radioactive waste do not exist yet in the Serbia and Montenegro. Consequently, waste management can only address an interim solution. In order to conduct all waste management activities in a safe manner, an overall strategy and study for improvement/rearrangement of radioactive waste storage facilities was developed which addresses all wastes and their management. The IAEA is providing assistance to these activities. This support includes a project which has been initiated by the IAEA to improve the waste management at the Vinca Institute. This paper describes the current status of the development of this overall strategy and study for improvement/rearrangement of radioactive waste storage facilities. The information available and the current status of the development of concepts for the processing and storage of the waste are summarised. (author)

  19. Security risks in nuclear waste management: Exceptionalism, opaqueness and vulnerability.

    Science.gov (United States)

    Vander Beken, Tom; Dorn, Nicholas; Van Daele, Stijn

    2010-01-01

    This paper analyses some potential security risks, concerning terrorism or more mundane forms of crime, such as fraud, in management of nuclear waste using a PEST scan (of political, economic, social and technical issues) and some insights of criminologists on crime prevention. Nuclear waste arises as spent fuel from ongoing energy generation or other nuclear operations, operational contamination or emissions, and decommissioning of obsolescent facilities. In international and EU political contexts, nuclear waste management is a sensitive issue, regulated specifically as part of the nuclear industry as well as in terms of hazardous waste policies. The industry involves state, commercial and mixed public-private bodies. The social and cultural dimensions--risk, uncertainty, and future generations--resonate more deeply here than in any other aspect of waste management. The paper argues that certain tendencies in regulation of the industry, claimed to be justified on security grounds, are decreasing transparency and veracity of reporting, opening up invisible spaces for management frauds, and in doing allowing a culture of impunity in which more serious criminal or terrorist risks could arise. What is needed is analysis of this 'exceptional' industry in terms of the normal cannons of risk assessment - a task that this paper begins. PMID:20022419

  20. Nuclear Waste Fund fee adequacy: an assessment. Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    The principal recommendation of this year's analysis is that the ongoing disposal fee should remain at 1.0 mill per kilowatt-hour (kWh) for 1985, based on the following findings: The current 1.0 mill per kWh fee is projected to produce revenues sufficient to offset estimated total system life-cycle costs for a reasonable range of program cost, nuclear generation, and economic environment forecases, as detailed later in this report. For the near term, program indebtedness due to 1983 appropriations cannot be repaid until payment of a substantial fraction of the utilities' $2.3 billion debt from the one-time fee is received. Many of the cost and revenue forecasts analyzed, particularly those for the US Energy Information Administration's (EIA) Mid Case generation forecast, show margins of revenues over costs. Future program cost increases due to general inflation or real price increases could be recovered by indexing the fee to the inflation rate or another cost index. These findings are based on a cash flow analysis that utilized methods very similar to those employed in previous fee adequacy studies. Refinements were made in the areas of system logistics, repository acceptance schedules, repository operating profiles, real interest rates, and treatment of real cost increases. Nuclear wastes produced from defense activities are not considered quantitatively in this report. Preliminary analyses have indicated that economies of co-emplacing defense and civilian wastes could be beneficial to both, but methods of allocating common costs appropriately will not be recommended until cost impacts have been determined more accurately