Characterization of solid radwaste generated at Virginia Power's Surry and North Anna stations

International Nuclear Information System (INIS)

Lippard, D.W.; Elguindy, H.; Nelson, R.A.

1987-01-01

This paper describes the results of a study on characterization of the major constituents of the solid radwaste generated at Virginia Power's North Anna and Surry Power Stations. The characterization consisted of identifying the individual constituents of the dry active waste (DAW) and estimating the fraction of the total DAW (both weight and volume) made up by each constituent. The analysis of the characterization of solid waste streams generated at both North Anna and Surry stations has lead to recommending techniques for both source minimization and waste volume reduction

Development of core sampling technique for ITER Type B radwaste

Energy Technology Data Exchange (ETDEWEB)

Kim, S. G.; Hong, K. P.; Oh, W. H.; Park, M. C.; Jung, S. H.; Ahn, S. B. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Type B radwaste (intermediate level and long lived radioactive waste) imported from ITER vacuum vessel are to be treated and stored in basement of hot cell building. The Type B radwaste treatment process is composed of buffer storage, cutting, sampling/tritium measurement, tritium removal, characterization, pre-packaging, inspection/decontamination, and storage etc. The cut slices of Type B radwaste components generated from cutting process undergo sampling process before and after tritium removal process. The purpose of sampling is to obtain small pieces of samples in order to investigate the tritium content and concentration of Type B radwaste. Core sampling, which is the candidates of sampling technique to be applied to ITER hot cell, is available for not thick (less than 50 mm) metal without use of coolant. Experimented materials were SS316L and CuCrZr in order to simulate ITER Type B radwaste. In core sampling, substantial secondary wastes from cutting chips will be produced unavoidably. Thus, core sampling machine will have to be equipped with disposal system such as suction equipment. Core sampling is considered an unfavorable method for tool wear compared to conventional drilling.

Summary of the ORNL-sponsored reactor radwaste management workshop

International Nuclear Information System (INIS)

Kibbey, A.H.

1977-01-01

On January 12 to 14, 1977, Oak Ridge National Laboratory (ORNL) sponsored a Radwaste Management Workshop in New Orleans, Louisiana, the object of which was to obtain operating data on the uses of evaporation, ion exchange, filtration, and on solid radwaste practices at nuclear power plants. The collected data are being used to update three earlier generic reports done by ORNL on the status of evaporation, ion exchange, and solid radwaste practices at nuclear power plants and to prepare a new one on filtration. All segments of the nuclear power industry were invited to participate, and a total of 188 representatives came. There were four major Workshop groups: volume reduction, solidification, physical and chemical separations, and corrosion. The major findings of each group are reported

Radwastes management in Qinshan Nuclear power plants

International Nuclear Information System (INIS)

Zhou Huan; Ling Kechi; Wang Qingrong; Luo Jingfan

1987-01-01

The source terms input used as the basic data for designing the radwaste treatment systems of Qinshan Nuclear Power Plant [300 MW(e)] is presented. The classification of radioactive liquid wastes, off-gases and solid wastes, and their treatment techniques, as well as on-site storage facilities for solid wastes are described. For liquid waste, the method of filtration-evaporation-ion exchange will be used as the main treatment technique. For off-gas, Holdup-decay treatment will be used. For evaporator concentrates, indrumsolidification method with normal domestic portland cement will be used. The assessment of impact of effluents to environment at normal operation of the NPP is also made. The results show that it will be safe for inhabitants nearby during normal operation and it can meet the requirements of national standard ''Regulation of Radiation Protection''

NRC licensing criteria for portable radwaste systems

International Nuclear Information System (INIS)

Hayes, J.J. Jr.

1983-01-01

The shortcomings of various components of the liquid and solid radwaste systems at nuclear power reactors has resulted in the contracting of the functions performed by these systems to various contractors who utilize portable equipment. In addition, some streams, for which treatment was not originally anticipated, have been processed by portable equipment. The NRC criteria applicable to portable liquid and solid radwaste systems is presented along with discussion on what is required to provide an adequate 10 CFR Part 50.59 review for those situations where changes are made to an existing system. The criteria the NRC is considering for facilities which may intend to utilize portable incinerators is also presented

System cuts radwaste-disposal cost

International Nuclear Information System (INIS)

May, J.R.

1978-01-01

Pilot-plant and full-scale prototype-system test data on a new volume-reduction system for low-level radioactive wastes, of the type generated by nuclear plants, indicate that total present costs for radwaste disposal can be reduced by more than 50%. In 1975, Newport News Industrial Corp. and Energy Inc. decided to develop cooperatively a fluidized-bed process that would combine the features of a calciner and an incinerator. The new radwaste-volume-reduction system, designated RWR-1, can reduce the volume of concentrated liquids, ion-exchange resin beads, filter sludges, and various combustible solids, such as protective clothing, rags, paper, wood, and plastics

The Morsleben radwaste repository. Preparing for decommissioning

International Nuclear Information System (INIS)

Mehnert, M.; Schmitt, R.

2001-06-01

The publication is intended to illustrate with a brief chronology the history and the present situation of the Morsleben radwaste repository, including specific aspects such as the geology of the site and construction and engineering activities, the particulars of waste form emplacement and log-term storage conditions, topical issues relating to radiological safety during operation and after decommissioning. The brochure is designed for the general audience interested in background information on all aspects of the uses, operation and decommissioning of a radwaste repository in Germany. (orig./CB) [de

Planning of optimal work path for minimizing exposure dose during radiation work in radwaste storage

International Nuclear Information System (INIS)

Kim, Yoon Hyuk; Park, Won Man; Kim, Kyung Soo; Whang, Joo Ho

2005-01-01

Since the safety of nuclear power plant has been becoming a big social issue, the exposure dose of radiation for workers has been one of the important factors concerning the safety problem. The existing calculation methods of radiation dose used in the planning of radiation work assume that dose rate dose not depend on the location within a work space, thus the variation of exposure dose by different work path is not considered. In this study, a modified numerical method was presented to estimate the exposure dose during radiation work in radwaste storage considering the effects of the distance between a worker and sources. And a new numerical algorithm was suggested to search the optimal work path minimizing the exposure dose in pre-defined work space with given radiation sources. Finally, a virtual work simulation program was developed to visualize the exposure dose of radiation during radiation works in radwaste storage and provide the capability of simulation for work planning. As a numerical example, a test radiation work was simulated under given space and two radiation sources, and the suggested optimal work path was compared with three predefined work paths. The optimal work path obtained in the study could reduce the exposure dose for the given test work. Based on the results, the developed numerical method and simulation program could be useful tools in the planning of radiation work

Disposal of solid radioactive waste of nuclear power plant

International Nuclear Information System (INIS)

YU Shichen.

1986-01-01

The contaminations of marine enviroment by the disposal of radwastes should not been expected, then ocean disposal has been stoped in some countries, and land disposal of solid radwastes should been a better method for mankind and environment protection. Ground burial near the surface is currently considered to be feasible. Storage in spent pit or in plant area also should been adapted in several countries

Radwaste management and spent fuel management in JAVYS

International Nuclear Information System (INIS)

Bozik, M.; Strazovec, R.

2010-01-01

In this work authors present radwaste management and spent fuel management in JAVYS, a.s. Processing of radioactive wastes (RAW) in the Bohunice Radioactive Waste Processing Center and surface storage of RAW in National RAW Repository as well as Interim Spent fuel storage in Jaslovske Bohunice are presented.

Solidification of liquid concentrate and solid waste generated as by-products of the liquid radwaste treatment systems in light-water reactors

International Nuclear Information System (INIS)

Neilson, R.M. Jr.; Colombo, P.

1977-01-01

The treatment of liquid concentrate and solid waste produced in light-water reactors as by-products of liquid radwaste treatment systems consists of five basic operations: waste collection, waste pretreatment, solidification agent handling, mixing/packaging (solidification) and waste package handling. This paper will concern itself primarily with the solidification operation, however, the other operations enumerated as well as the types of wastes treated and their origins will be briefly described, especially with regards to their effects on solidification. During solidification, liquid concentrate and solid wastes are incorporated with a solidification agent to form a monolithic, free-standing solid. The basic solidification agent types either currently used in the United States or proposed for use include absorbants, hydraulic cement, urea-formaldehyde, other polymer systems, and bitumen. The operation, formulations and limitations of these agents as used for radwaste solidification will be discussed. Properties relevant to the evaluation of solidified waste forms will be identified and relative comparisons made for wastes solidified by various processes

Waste management tasks of the Radwaste Collecting Centers of the Laender

International Nuclear Information System (INIS)

Dreisvogt, H.

1994-01-01

The paper outlines the manifold activities of the Radwaste Collecting Centers of the Laender. According to section 9 a, sub-sec. 3 of the Atomic Energy Act, the various Laender in Germany are obliged to establish such centers whose purpose among other things is to serve as interim storage site for radwaste accrued at medical, industrial, or research facilities. (HP) [de

Novel conditioning methods for radwaste and residues

International Nuclear Information System (INIS)

Rittscher, D.

1993-01-01

Due to the fact that a federal radwaste repository is not yet available and on-site or afr interim storage capacities are limited, new conditioning techniques and strategies for avoiding accruement of radwaste from nuclear power plant operation have been developed, leading to a reduction of annual radwaste amounts from 1800 m 3 (BWR) and 650 m 3 (PWR) in the year 1980 to 160 m 3 (BWR) and 40 m 3 (PWR) in 1990. This very significant reduction of waste amounts was achieved by (1) improvements in on-site waste management, (2) application of volume-reducing, new condititioning techniques (as e.g. dehydration of liquid waste instead of embedding in cement, (3) consequent application of radiologically safe recycling techniques for steel scrap (production of cast steel containers, e.g.), and (4) the use of optimized packaging forms (e.g. containers instead of 200-l waste drums). (orig./DG) [de

The instrumentation for express characterization of historical radwaste storages and contaminated soil

International Nuclear Information System (INIS)

Volkovich, A.G.; Ignatov, S.M.; Danilovich, A.S.; Potapov, V.N.; Ivanov, O.P.; Stepanov, V.E.; Smirnov, S.V.

2008-01-01

A variety of special radiation measurement problems arise in planning and performance of rehabilitation activities at the radwaste disposal site (RWDS), including acquisition and refinement of data on composition, location and activity of radwaste (RW) in the old repositories, evaluation of activity of radwaste to be removed, measurement of radioactive contamination of repository structures and soil, monitoring of dose rates [1]. The old repositories are characterized by nonuniform RW distribution over the repository volume. The radwaste in the old repositories are mixed with soil, concrete and other materials. A number of new instruments and systems were developed to conduct the necessary measurements. New instruments with collimated scintillation detectors operating both in current and spectrometry modes were developed for measurements of the distribution of the RW specific activity over layers in the old repositories. The measurements are taken in exploratory wells that are drilled in the old repositories prior to their opening. The technique of specific activity measurements with collimated detectors was used when examining radioactive contamination of soil in a number of Russian contaminated territories and demonstrated a good agreement with results of sampling performed at the same time. (author)

The community's R and D programme on radioactive waste management and storage

International Nuclear Information System (INIS)

1978-01-01

The objective of the R and D actions is the demonstration of either the technical potential or, for further advanced projects, the feasibility and even the industrial availability of methods for treating and storing radwaste. The following aspects are investigated: processing of solid waste from reactors, reprocessing plants and the plutonium manufacture; intermediate and terminal storage of high activity and alpha waste; advanced waste management methods as the storage of gaseous waste. In addition to the scientific-technical R and D actions, a survey of the legal, administrative and financial problems encountered in radwaste management and storage is an essential part of the Communities' programme

Geological factors of disposal site selection for low-and intermediate-level solid radwastes in China

International Nuclear Information System (INIS)

Chen Zhangru

1993-01-01

For disposal of low- and intermediate-level solid radioactive wastes, shallow-ground disposal can provide adequate isolation of waste from human for a fairly long period of time. The objective of disposal site selection is to ensure that the natural properties of the site together with the engineered barrier site shall provide adequate isolation of radionuclides from the human beings and environment, so the whole disposal system can keep the radiological impact within an acceptable level. Since the early 1980's, complying with the national standards and the expert's conception as well as the related IAEA Criteria, geological selection of disposal sites for low-and intermediate-level solid radwastes has been carried out in East China, South China, Northwest China and Southwest China separately. Finally, 5 candidate sites were recommended to the CNNC

The Community's R and D Programme on radioactive waste management and storage

International Nuclear Information System (INIS)

1980-01-01

The objective of the R and D actions to be achieved by 1980 is the demonstration of either the technical potential or, for further advanced projects, the feasibility and even the industrial availability of methods for treating and storing radwaste. The following aspects are investigated: - processing of solid waste from reactors, reprocessing plants and the plutonium fuel fabrication; - intermediate and terminal storage of high activity and alpha wastes; - advanced waste management methods as the storage of gaseous wastes. This report presents the most important results achieved under the programme. In addition to the scientific-technical R and D actions, a survey of the legal, administrative and financial problems encountered in radwaste management and storage is an essential part of the Communities' programme

Simulation of the saturation process of a radwaste storage cell

International Nuclear Information System (INIS)

Robbe, M.F.; Clouard, A.

2001-01-01

This paper presents a simulation of the saturation of the barrier and the plug of a storage cell by the surrounding host rock. Generally speaking, the unsaturated barrier and plug start saturating immediately in the vicinity of the quasi-saturated host rock. Then the saturation front propagates towards the canisters and the symmetry axis. Apart from the part in contact with the plug, the barrier is saturated at about 30 years. The part of the barrier near the plug is saturated around 80 years. If the top of the plug is saturated very soon, the part in the corner near the gallery and the symmetry axis is not completely saturated after 100 years. In the site, we observe a small desaturation during the first month, at the limit with the plug and the barrier, and especially in the corner limited by both FoCa clay pieces. This transient phenomenon may be assigned to the time difference between the immediate suction of water by the unsaturated materials and the delayed water flows coming from the saturated host rock to compensate the water suction. The purpose of this computation was at once to estimate the time necessary for the saturation of the clay layers surrounding the radwaste canisters and to evaluate the hydro-mechanical behaviour of the storage cell during the saturation process. Therefore a mechanical simulation was performed using the present hydraulic results to initiate the mechanical computation. (authors)

Low-level radwaste solidification

International Nuclear Information System (INIS)

Naughton, M.D.; Miller, C.C.; Nelson, R.A.; Tucker, R.F.

1983-01-01

This paper reports on a study of ''Advanced Low-Level Radioactive Waste Treatment Systems'' conducted under an EPRI contract. The object of the study is to identify advanced lowlevel radwaste treatment systems that are commercially available or are expected to be in the near future. The current state-ofthe-art in radwaste solidification technology is presented. Related processing technologies, such as the compaction of dry active waste (DAW), containers available for radwaste disposal, and the regulatory aspects of radwaste transportation and solidification, are described. The chemical and physical properties of the currently acceptable solidification agents, as identified in the Barnwell radwaste burial site license, are examined. The solidification agents investigated are hydraulic cements, thermoplastic polymers, and thermosetting polymers. It is concluded that solidification processes are complex and depend not only on the chemical and physical properties of the binder material and the waste, but also on how these materials are mixed

Principles and criteria for creation of a concept for national radwaste repository

International Nuclear Information System (INIS)

Milanov, M.; Strezov, A.; Kojuharov, D.

1993-01-01

General principles and criteria based on the international experience and requirements as well as on specific Bulgarian conditions are used in the creation of the Concept for Radwaste Repository Construction as a first stage of the Bulgarian nuclear programme. The Concept contains about 70 projects of common or more specific character. The Bulgarian territory is categorized and several prospective areas are selected as a final result of the analysis performed. A model for development of a National System for Radwaste Management is considered. The formation of a working group appointed by governmental authorities as a solution of the existing highly complex situation connected with the treatment and storage of radwaste in the country is proposed. 1 fig., 14 refs. (author)

Industrial Complex for Solid Radwaste Management at Chernobyle Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Ahner, S.; Fomin, V. V.

2002-02-26

In the framework of the preparation for the decommissioning of the Chernobyl Nuclear Power Plant (ChNPP) an Industrial Complex for Solid Radwaste Management (ICSRM) will be built under the EC TACIS Program in the vicinity of ChNPP. The paper will present the proposed concepts and their integration into existing buildings and installations. Further, the paper will consider the safety cases, as well as the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian regulations and licensing requirements. The paper will provide information on the status of the interim design and the effects of value engineering on the output of basic design phase. The paper therefor summarizes the design results of the involved design engineers of the Design and Process Providers BNFL (LOT 1), RWE NUKEM GmbH (LOT 2 and General) and INITEC (LOT 3).

Low-level radwaste engineering economics

International Nuclear Information System (INIS)

Jacobs, M.H.; Miller, C.C.; Young, L.G.

1984-07-01

This topical report on engineering economics for low-level radwaste systems details the methodologies used for economic analyses of radwaste treatment systems and provides examples of radwaste economic evaluations. All of the parameters and cost items used in an evaluation are defined. Examples of the present-value-of-revenue-requirements method, levelized-revenue-requirements method, and the equivalent-capital-investment method are provided. Also, the calculation to determine the maximum justifiable capital expenditure for a radwaste system is illustrated. The report also provides examples of economic evaluations for many current radwaste treatment options. These options include evaporation versus demineralization, dewatering resins versus solidification of resins, and several volume reduction systems. 15 figures, 6 tables

Low-level radwaste transportation in Taiwan

International Nuclear Information System (INIS)

Lo, L.F.; Huang, C.C.

1993-01-01

In the past ten years, 273 voyages have been made to ship radwaste produced by nuclear power plants and Institute of Nuclear Energy Research (INER). It more or less lowers the problem of insufficient storage space in Taiwan. Although all organizations followed various regulations to operate the transportation, ten events occurred in marine transport. However, they were ordinary incidents and neither released any radiation to contaminate the environment nor caused any casualty. (J.P.N.)

Radwaste - Multimedia presentation

International Nuclear Information System (INIS)

2000-01-01

Radioactivity is a part of the Nature since the creation of the Earth. We have learned how to use radioactivity in medicine, power industry, and in other areas of life. Similarly as in other activities, waste is generated. We offer you basic information about radioactivity and radioactive waste (radwaste) in four films: Radioactivity, Source of radwaste, Management of radwaste. In the glossary are video presentations: Container (Castor) for radioactive waste; Deep underground repository; Transport vehicle; WWER type reactor. Encyclopedic part of the program contains detailed theoretical and practical information about use of radioactivity and radioactive waste. You will find the explanation in the part Glossary. (authors)

The generation characteristics of solid radioactive wastes in the KEPCO nuclear power plants

International Nuclear Information System (INIS)

Shon, Soon Hwan; Kang, Duck Won; Kim, Hee Keun

1991-01-01

Solid radwastes generation trend and characteristics were discussed for nuclear power plants in KEPCO. Each plant has a specific tendency of solid radwastes generation due to the plant characteristics. The total volume of solid radwastes generated from nine power plants was accumulated in 23,012 drums by the end of 1989. The average annual volume per unit was about 670 drums. The solid radwaste mostly consisted of solidified concentrates and contaminated trash. The contaminated trash has been the major portion of the solid radwastes since 1982. The volume of the contaminated trash was dependent on the availability factor and period of overhaul. Therefore, the contaminated trash was considered to be a prime target for the solid radwastes minimization plan

Technological process of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author introduces the technological process of a multi-purpose radwaste incineration system. It is composed of three parts: pretreatment, incinerating and clean up of off-gas. The waste that may be treated include combustible solid waste, spent resins and oils. Technological routes of the system is pyrolysis incinerating for solid waste, spray incinerating for spent oils, combination of dry-dust removing and wet adsorption for cleaning up off-gas

Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

International Nuclear Information System (INIS)

Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

1997-01-01

Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

Development of commercial robots for radwaste handling

International Nuclear Information System (INIS)

Colborn, K.A.

1988-01-01

The cost and dose burden associated with low level radwaste handling activities is a matter of increasing concern to the commercial nuclear power industry. This concern is evidenced by the fact that many utilities have begun to revaluate waste generation, handling, and disposal activities at their plants in an effort to improve their overall radwaste handling operations. This paper reports on the project Robots for Radwaste Handling, to identify the potential of robots to improve radwaste handling operations. The project has focussed on the potential of remote or automated technology to improve well defined, recognizable radwaste operations. The project focussed on repetitive, low skill level radwaste handling and decontamination tasks which involve significant radiation exposure

Radwastes management program of the IEN

International Nuclear Information System (INIS)

Peres, S.S.; Godoy, J.M.O

2000-01-01

Low level radioactive wastes are produced during the operation of the radioactive and nuclear installations of the Nuclear Engineering Institute (Instituto de Engenharia Nuclear, IEN) situated in Rio de Janeiro City, Brazil. These wastes can be generated during the operation and maintenance of the CV-28 Cyclotron, the radioisotopes production, the research activities using natural thorium and uranium in chemical laboratories and, eventually, during the operation Argonauta Reactor. In accordance to the methodology of the radwastes management adopted in the IEN, the wastes are segregated and treated depending on theirs physical, chemical, biological and radiological properties. The wastes with important levels of activity are separate and collected in special containers. Wastes containing short-lived radionuclides are also separated and left away for decaying. Solid wastes are constituted of materials used in laboratories, such as papers, rubber gloves, plastics, over shoes, broken glassware, metal pieces, etc. These wastes are classified as compressible, combustible, non-compressible and non- combustible. The solid wastes are collected in suitable containers placed throughout the working area. Basically, the treatment methods used for these wastes are activity decay, decontamination and compaction. Liquid wastes are generated in small volumes and, generally, containing little quantities of radionuclides. These wastes are classified as aqueous and non-aqueous, acid, alkaline. The diluted aqueous wastes produced in hot laboratories are collected in liquid effluent collection stations for analysis by gamma spectrometry. If the activity concentration is smaller than the established limits in waste management national standards, they are discharge inside of the local sanitary sewer system. Otherwise, these wastes are retained for treatment. The treatment methods used for liquid wastes are activity decay, chemical precipitation, ion exchange and immobilization in inert

Selection of detailed items for periodic safety review on PWR radwaste management system

Energy Technology Data Exchange (ETDEWEB)

Sung, K. B.; Ahn, Y. S.; Park, Y. S.; Kim, S. H.; Kim, J. T. [Korea Hydric and Nuclear Power Company, Taejon (Korea, Republic of)

2003-10-01

Selection of detailed-items for Periodic Safety Review on PWR radwaste management system, the main component could be faithfully clarified according to the purpose of establishment on each system and basic purpose. It is proper to select detailed-items those of radioactivities in the reactor coolant activity levels and the released volume of liquid and gaseous radioactive material on safety performance. It's also proper to select solid radwaste production quantities as detailed-item that it would be predict the next ten years trends after PSR.

Natural analogue for storage of radwaste in crystalline rocks

International Nuclear Information System (INIS)

Brookins, D.G.; Abashian, M.S.; Cohen, L.H.; Wollenberg, H.A. Jr.

1982-01-01

The Bryan-Eldora stock (Colorado) intruded the Precambrian Idaho Springs Formation metamorphic rocks 58 million years ago. Geochronologic-geochemical work by Hart et al. [S.R. Hart et al., in Radiometric Dating for Geologists, E.I. Hamilton, R.S. Farquhar, eds. (Wiley-Interscience, New York, 1968) pp. 73-110] has demonstrated that the heat from the cooling intrusive rocks was sufficient to affect mineral isotopic systematics up to 2000 m from the contact, and the nature of these isotopic perturbations can be explained by a simple diffusion model in turn based on various heat flow models. Our new studies are focused on elemental exchange between stock and intruded rock as a function of distance from the contact; the assumption is made that the stock is a very large, high heat source analogous to a waste form emplaced in the metamorphic rocks without benefit of canister or engineered backfill. Data for U, Th and the REE indicate actinide and lanthanide immobility except perhaps in the 0 to 2m contact zone where some infiltration of the country rocks by stock-derived fluids occurred. Beyond 4m no stock-derived U, Th, REE or *Pb are noted. Further, whole rock Rb-Sr and stable O isotopic data indicate conductive cooling as opposed to convective, water-induced cooling. The intruded rocks possess low porosity and permeability; this helped prevent elemental migration during the 10 5 to 10 6 years of stock crystallization. The petrographic and geochemical studies show that the Idaho Springs (or equivalent) metamorphic rocks are well suited for radwaste storage. 1 figure, 1 table

Radwaste storage in crystalline rocks: a natural analog

International Nuclear Information System (INIS)

Brookins, D.G.; Abashian, M.S.; Cohen, L.H.; Wollenberg, H.A.

1982-01-01

The Eldora-Bryan Stock (Colorado) intruded the 1.4-1.6 billion year old metamorphic rocks of the Idaho Springs Formation 55 million years ago. The stock may be considered a giant analog of a radwaste form without canister or engineered backfill barriers. The authors' lanthanide studies show the following: (1) The intrusive rocks remained as a closed system. (2) Lanthanide/chondrite versus ionic radius plots show only local redistribution in the immediate contact zone, and that rocks in this zone have not gained lanthanides from the magma. (3) No whole rock perturbations for the lanthanides are noted at distances greater than 3 m from the contact. Stable oxygen isotopic variations show a narrow 9.0 +- 0.3 per mille range for the intrusive rocks and whole rock values from 7.6 to 10.0 per mille for the intruded rocks. The authors conclude: (1) The Idaho Springs Formation was not penetrated by hydrothermal fluids from the Eldora-Bryan magma except possibly on a local scale within 3 m of the contact. (2) The light lanthanides may be locally redistributed in the immediate contact zone, but without additions from the magma. (3) The oxygen isotopic data imply lack of hydrothermal fluids from the magma penetrating the intruded rocks, even in the highest temperature contact zones. Whole rock data imply closed system conditions for Rb, Sr, Th, U, Pb even where mineral ages have been lowered. Data for Co, Cr, Sc, Fe, Cs also indicate retention in whole rock systems and no exchange with the magma. The combined chemical, isotopic, petrographic and theoretical data and calculations indicate suitability of rocks of the Idaho Springs Formation, and thus of many types of crystalline rocks as well, for possible use for the storage of radioactive waste

Optimization and characterization of cement products incorporating ashes from radwaste incineration

International Nuclear Information System (INIS)

Donato, A.; Pace, A.; Ricci, G.

1989-01-01

The incineration is presently condidered a very good way to obtain strong volume reduction of intermediate and low activity solid radwastes obtaining at the same time a product apparently easy to be conditioned. In some cases nevertheless the ash solidification by cementation can give in the practice some problems. In this work the optimization of the cementation of two ash types named Nust 1 and Nust 2 has been studied. The Nust 1 ash come from the incineration of the exhausted ion exchange resins already conditioned in urea-formaldehyde. The Nust 2 ash comes from the incineration of the same materials as the Nust 1 mixed with ordinary nuclear power plant solid radwastes. Both ashes have been produced from wastes stored at the Caorso (Italy) Nuclear Power Plant. The two ash types have been characterized by a series of physico-chemical analysis whose results are reported as well as the results of the preliminary tests performed on the products obtained from their cementation

Radwaste volume reduction and solidification by General Electric

International Nuclear Information System (INIS)

Green, T.A.; Weech, M.E.; Miller, G.P.; Eberle, J.W.

1982-01-01

Since 1978 General Electric has been actively engaged in developing a volume reduction and solidifcation system or treatment of radwaste generated in commercial nuclear power plants. The studies have been aimed at defining an integrated system that would be directly responsive to the rapid evolving needs of the industry for the volume reduction and solidification of low-level radwaste. The resulting General Electric Volume Reduction System (GEVRS) is an integrated system based on two processes: the first uses azeotropic distillation technology and is called AZTECH, and the second is controlled-air incineration...called INCA. The AZTECH process serves to remove water from concentrated salt solutions, ion exchange resins and filter sludge slurries and then encapsulates the dried solids into a dense plastic product. The INCA unit serves to reduce combustible wastes to ashes suitable for encapsulation into the same plastic product produced by AZTECH

Solid radioactive waste management in Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Huang Laixi; He Wenxin; Chen Degan

2004-01-01

This paper introduces the solid radwaste management system, treatment methods and its continuous improvement during the past 9 years in Guangdong Daya Bay Nuclear Power Station (GNPS). GNPS has paid great attention and made a lot of efforts to implement the principle of waste minimization with source control, improvement of treatment process and strict management, so the output of solid radwastes has annually decreased since 1994. In 2002, the output of solid radwastes in GNPS was 63.5 m 3 , only 50% of 1995 (127 m 3 ), reached the advanced level as the same type NPPs in France. During the period 1994-2002, the accumulated production of solid radwaste Packages in GNPS is 1563.51 m 3 only 18% of the design value; all the packages meet the standard and requirement for safe disposal. Besides, this paper analyzes some new technical processes and presents some proposals for further decreasing the solid radwaste production

An incinerator for combustable radwastes

International Nuclear Information System (INIS)

Li Jingquan; Jiang Yun; Zhang Yinsheng; Chen Boling; Zhang Shihang

1989-01-01

An incinerator has been built up in Shanghai. In this paper, the devices of the incinerator, main parameters of the process, and the results of non-radioactive waste and simulated radwaste combustion tests were contributed. That provides reference information for radwaste treatment with incineration process

An analysis on radwaste management in China

International Nuclear Information System (INIS)

Chen Haicheng; Qu zhimin

1999-05-01

Considerable masses of radwastes have been produced in China during past period of four decades. The government has paid great attentions to the management of those radwastes and much progress has been made. The development of nuclear power has led the national radwaste management into a new era, meanwhile has brought about new challenges and issues for the existing management system. The analysis indicates that the existing management system is comprehensive but needs to be further improved: (1) regulations system of radwaste management needs to be perfected; (2) a special operational agency for managing radwastes has to be founded; (3) a financing system for long-term management is expected to be created; (4) information and interaction programs should be carried out and involved in the national management strategy

The experience of liquid radwaste evaporator performance improvement

International Nuclear Information System (INIS)

Kwon, S. H.

1997-01-01

Ulchin NPP has only one monobloc evaporation column which treated all radwaste liquid for two units. Since commercial operation in 1988 the evaporator performance is very poor. I think that the bad condition of evaporator is because of the bad quality of liquid radwaste, the large volume of liquid radwaste to treated, the poor skill of operation and some mistake in equipment design. Because of above conditions the average released activity by liquid radwaste is 35.153mCi/year in last eight years(1988∼1995). So it is necessary that we have to improve the evaporator performance and to reduce the liquid radwaste volume to evaporate

Operational experience on reduction of feedwater iron and liquid radwaste input for Kuosheng Nuclear Power Plant

International Nuclear Information System (INIS)

Wen, T.J.; Huang, Theresa Chen; Liu, Wen Tsung; Liu, T.C.; Shyur, Tzu Sheng; Shen, S.C.

1998-01-01

Other than cobalt alloys, or low cobalt materials, feedwater iron content plays an important role in crud activation and transport causing the growth of out-of-core radiation fields and associated with radwaste generation. Before installing prefilter in the upstream of condensate deep-bed demineralizer, increasing demand for suspended solid removal required new backwash and regeneration technique in Kuosheng Nuclear Power Plant. At steady state full power operation, the average iron concentration in condensate demineralizer influent was 8-15 ppb. Considering both the necessity of backwash and reduction of liquid radwaste input, several actions had been taken to promote the crud removal capabilities without using ultrasonic resin cleaner and controlled feedwater iron content between 0.5 and 2.0 ppb. This modified resin backwash technique would also generate minimum liquid radwaste. Meanwhile, significant efforts have been made to promote the quality of waste water by carefully control input streams as well as backwash modification to reduce liquid radwaste generation. The daily quantity of liquid radwaste has decreased dramatically in the past two years and is effectively controlled under the expected average daily input of design basis. (author)

Analysis on long-term strategy for radwaste management in China

Energy Technology Data Exchange (ETDEWEB)

Chen Haicheng [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-08-01

Radwaste presents a worldwide issue in the management of environmental protection. Most countries carrying out nuclear programs have developed strategies for their radwastes management. China has been executing its strategy, but the development of nuclear power is representing new challenges for the national radwastes management. This paper tries an analysis on the long-term management of radwastes in China. The exiting system of China`s radwastes management is explained. Two important issues on radwastes management i.e. economics and social issues are analyzed. The future issues that will affect China`s radwastes management are discussed. A short summary of the national radwastes management in NEA countries is involved in the paper. The analysis indicates that in China the exiting system of radwastes management is comprehensive but remains to be perfected. Improvements of long-term management need to be made in the aspects of economics and social issue. A financing system for long-term management, as a supplement for the exiting system of radwastes management, is expected to be created. (author)

Analysis on long-term strategy for radwaste management in China

International Nuclear Information System (INIS)

Chen Haicheng

1998-08-01

Radwaste presents a worldwide issue in the management of environmental protection. Most countries carrying out nuclear programs have developed strategies for their radwastes management. China has been executing its strategy, but the development of nuclear power is representing new challenges for the national radwastes management. This paper tries an analysis on the long-term management of radwastes in China. The exiting system of China's radwastes management is explained. Two important issues on radwastes management i.e. economics and social issues are analyzed. The future issues that will affect China's radwastes management are discussed. A short summary of the national radwastes management in NEA countries is involved in the paper. The analysis indicates that in China the exiting system of radwastes management is comprehensive but remains to be perfected. Improvements of long-term management need to be made in the aspects of economics and social issue. A financing system for long-term management, as a supplement for the exiting system of radwastes management, is expected to be created. (author)

Cement radwaste solidification studies third annual report

International Nuclear Information System (INIS)

Brown, D.J.; James, J.M.; Lee, D.J.; Smith, D.L.; Walker, A.T.

1982-03-01

This report summarises cement radwaste studies carried out at AEE Winfrith during 1981 on the encapsulation of medium and low active waste in cement. During the year more emphasis has been placed on the work which is directly related to the solidification of SGHWR active sludge. Information has been obtained on the properties of 220 dm 3 drums of cemented waste. The use of cement grouts for the encapsulation of solid items has also been investigated during 1981. (U.K.)

Operation of Temporary Radioactive waste stoprage facility

Energy Technology Data Exchange (ETDEWEB)

Kinseem, A A; Abulfaraj, W H; Sohsah, M A; Kamal, S M; Mamoon, A M [Nuclear Engineering Department, Faculty of Engineering, King Abdelazizi University jeddah-21413, Saudi Arabia (Saudi Arabia)

1997-12-31

Radionuclides of various half lives have been in use for several years years at different Departments of king Abdulaziz university, the university hospital, and research center. The use of unsealed radionuclides in many laboratories, resulted in considerable amounts of solid and liquid radwaste, mainly radiopharmaceuticals. To avoid accumulation of radwastes in working areas, a temporary radioactive waste storage facility was built. Segregation of radwastes according to type was carried out, followed by collection into appropriate containers and transfer to the storage facility. Average radiation dose rate inside the store was maintained at about 75 {mu} h{sup -1} through use of appropriate shielding. The dose rates at points one meter outside the store walls were maintained at about 15-20 {mu}Sv h{sup -1}. Utilization of radioisotopes during the period of 1991-1995 resulted in a volume of about 1.8 m{sup 3} of solid radwaste and about 200 L of liquid radwaste. Records of the store inventory are maintained in a computer database, listing dates, types, activities and packaging data pertinent to the radwastes delivered to the store. Quality assurance procedures are implemented during the different stages of the radwaste collection, transportation, and storage. Construction and operation of the storage facility comply with radiation safety requirements for the workers handling the radwastes, the public and the environment. The capacity of the storage facility is such that it will accommodate storage of generated radwastes of long half life up to year 2016. Permanent disposal of such radwastes may be indicated afterwards. 2 figs., 3 tabs.

The Communities R and D Programme: radioactive waste management and storage

International Nuclear Information System (INIS)

1977-01-01

The European Community's programme is the first and to this date the only joint international action dealing with those issues, which might well become decisive for the future of nuclear energy -the management and storage of radioactive waste. The first Annual Progress Report describes the scope and the state of advancement of this indirect action programme. At present 24 research contracts with research institutes in almost every member country of the EC are either signed or in the final stages of negociation. The objective of the R and D actions to be achieved by 1980 is the demonstration of either the technical potential or, for further advanced projects, the feasibility and even the industrial availability of methods for treating and stoping radwaste. The following aspects are investigated: processing of solid waste from reactors, reprocessing plants and the plutonium manufacture; intermediate and terminal storage of high activity and alpha wastes; advanced waste management methods as the storage of gaseous waste and the separation and transmutation of actinides. In addition to the scientific-technical R and D actions, a survey of the legal, administrative and financial problems encountered in radwaste management and storage is an essential part of the Communities' programme

Advanced liquid radwaste decontamination by using a centrifuge system

International Nuclear Information System (INIS)

Tscheschlok, K.; Szukala, M.

1999-01-01

Waste water streams basically include undissolved suspended solids which contain almost the main part of the activated products. The centrifuge system, called LRS (Liquid Radwaste Treatment System), is able to remove these solids from the liquid content and fills the dewatered product into disposal containers. For this purpose a chemical pre-treatment step is often used for selective precipitation of special radionuclides and flocculents to agglomerate smaller sized particles (colloids) to make them separatable with the LRS. The plant arrangement, the process optimization and the collected operational experiences are described. 2 refs., 1 tab., 8 figs

North Sea focus on radwaste disposal

International Nuclear Information System (INIS)

Cope, D.

1990-01-01

At the recent North Sea Conference in the Netherlands possible future strategies for managing radioactive waste (radwaste) proved to be a contentious issue. Several of its North Sea littoral neighbours sought a categorical assurance that the UK would forego the option of constructing a subterranean radwaste repository which though accessed from land, extends under the coastline, or a sub-seabed facility reached from an offshore structure. It was pointed out that the UK has no present plans for such a radwaste repository. However, sub-seabed designs as a possibility for future repositories were not ruled out. NIREX has decided to concentrate its exploration work at two sites -Sellafield and Dounreay. Both sites are coastal locations and the government is aware that detailed geological exploration may favour extension of a radwaste repository beyond the shoreline, even if initially developed entirely on land. The design of such a radioactive waste repository is outlined. The position of NIREX and the Radioactive Waste Management Advisory Committee is discussed. (author)

Radwaste volume reduction economics: an overview

International Nuclear Information System (INIS)

Naughton, M.D.

1984-01-01

Today, utilities are faced with mounting charges related to the disposal of radioactive waste from their nuclear power plants. Numerous factors complicate economic analysis of radwaste processing options. This paper details two recent key EPRI studies bearing upon radwaste operations and economics. The first study, RP1557-3, characterizes low level wastes from nuclear power plants during the period 1978 to 1982. This paper presents information on the quantity of waste by type, waste composition, specific activities and major isotopes and radiation fields of final disposal packages. The second study, RP1557-11,12,13, involved the development of a computer code for evaluating radwaste disposal economics. Capital and operating cost estimates were prepared for 11 diferent processing-disposal options. These costs are utilized along with a burial site pricing algorithm in VRTECH, a computer radwaste economic assessment program. This paper discusses the VRTECH code and the results of the generic analyses conducted in the study

Human engineering in mobile radwaste systems

International Nuclear Information System (INIS)

Jones, D.; McMahon, J.; Motl, G.

1988-01-01

To a large degree, mobile radwaste systems are replacing installed plant systems at US nuclear plants due to regulatory obsolescence, high capital and maintenance costs, and increased radiation exposure. Well over half the power plants in the United States now use some sort of mobile system similar to those offered by LN Technologies Corporation. Human engineering is reflected in mobile radwaste system design due to concerns about safety, efficiency, and cost. The radwaste services business is so competitive that vendors must reflect human engineering in several areas of equipment design in order to compete. The paper discusses radiation exposure control, contamination control, compact components, maintainability, operation, and transportability

Radwaste treatment complex. DRAWMACS planned maintenance system

International Nuclear Information System (INIS)

Keel, A.J.

1992-07-01

This document describes the operation of the Planned Maintenance System for the Radwaste Treatment Complex. The Planned Maintenance System forms part of the Decommissioning and Radwaste Management Computer System (DRAWMACS). Further detailed information about the data structure of the system is contained in Database Design for the DRAWMACS Planned Maintenance System (AEA-D and R-0285, 2nd issue, 25th February 1992). Information for other components of DRAWMACS is contained in Basic User Guide for the Radwaste Treatment Plant Computer System (AEA-D and R-0019, July 1990). (author)

Correlation between radwaste processing and hazardous waste treatment processes

International Nuclear Information System (INIS)

Block, O.U.J.; Tulipano, F.J.

1988-01-01

The basic framework under SARA has established that preferred remedies are those which permanently and significantly reduce toxicity, mobility or volume of wastes. In the 1970's radwaste process designs at power plants received pressure to satisfy essentially the same criteria when increased emphasis was placed on limited disposal sites which resulted in rapidly escalating disposal costs. This paper provides a historical perspective of radwaste experience and discusses valuable insight to hazardous waste treatment technologies. The radwaste system experience is discussed in terms of providing a source of proven and reliable technologies. Discussion is presented on specific radwaste processes which are applicable technologies for hazardous waste treatment. The technologies presented include (a) Solidification, (b) Evaporation, and (c) Incineration. Experience is presented which establishes assurance that the treatment technologies will provide a permanent remedy to hazardous waste treatment. This paper describes typical radwaste solidification, evaporation and incineration processes at power plants. The design requirements and implementation of radwaste equipment is correlated to design requirement of hazardous waste equipment. Specific discussion is provided on how the available process equipment can reduce toxicity, mobility, and volume of waste. Discussion is presented on how the standard off the shelf processing equipment needs to be modified for radwaste and hazardous waste applications

SOLID-STATE STORAGE DEVICE WITH PROGRAMMABLE PHYSICAL STORAGE ACCESS

DEFF Research Database (Denmark)

2017-01-01

a storage device action request, and the storage device evaluating a first rule of the one or more rules by determining if the received request fulfills request conditions comprised in the first rule, and in the affirmative the storage device performing request actions comprised in the first rule......Embodiments of the present invention includes a method of operating a solid-state storage device, comprising a storage device controller in the storage device receiving a set of one or more rules, each rule comprising (i) one or more request conditions to be evaluated for a storage device action...... request received from a host computer, and (ii) one or more request actions to be performed on a physical address space of a non-volatile storage unit in the solid-state storage device in case the one or more request conditions are fulfilled; the method further comprises: the storage device receiving...

Radwaste disposal by incorporation in matrix

International Nuclear Information System (INIS)

Curtiss, D.H.; Heacock, H.W.

1976-01-01

A process of safe disposal, handling, or storae of radwaste associated with nuclear power productin is described. A feature of the invention is to incorporate the radwaste in a hardenable, matrix-forming mass employing a cement-type binding agent to which alkali or alkaline-earth silicate is added, among other things, to increase liquid absorption. 9 claims

Radwaste assessment program for nuclear station modifications by design engineering

International Nuclear Information System (INIS)

Eble, R.G.

1988-01-01

Radwaste burial for Duke Power Company's (DPC's) seven nuclear units has become a complicated and costly process. Burial costs are based on overall volume, surcharges for radioactivity content and weight of containers, truck and cask rental, driver fees, and state fees and taxes. Frequently, radwaste costs can be as high as $500 per drum. Additionally, DPC is limited on the total burial space allocated for each plant each year. The thrust of this program is to reduce radwaste volumes needing burial at either Barnwell, South Carolina, or Richland, Washington. A limited number of options are available at our sites: (a) minimization of radwaste volume production, (b) segregation of contamination and noncontaminated trash, (c) decontamination of small hardware, (d) volume reduction of compatible trash, (e) incineration of combustible trash (available at Oconee in near future), and (f) burial of below-regulatory-concern very low level waste on site. Frequently, costs can be reduced by contracting services outside the company, i.e., supercompaction, decontamination, etc. Information about radwaste volumes, activities, and weight, however, must be provided to the nuclear production department (NPD) radwaste group early in the nuclear station modification (NSM) process to determine the most cost-effective method of processing radwaste. In addition, NSM radwaste costs are needed for the NPD NSM project budget. Due to the advanced planning scope of this budget, NSM construction costs must be estimated during the design-phase proposal

SOLID RADIOACTIVE WASTE STORAGE TECHNOLOGIES: PERFORMANCE OF A POLYMER SEALANT COATING IN AN ARCTIC MARINE ENVIRONMENT

International Nuclear Information System (INIS)

COWGILL, M.G.; MOSKOWITZ, P.D.; CHERNAENKO, L.M.; NAZARIAN, A.; GRIFFITH, A.; DIASHEV, A.; ENGOY, T.

2000-01-01

This first project, under the auspices of the Arctic Military Environmental Cooperation (AMEC) forum, Project 1.4-1 Solid Radioactive Waste Storage Technologies, successfully demonstrated the feasibility of using a polymer-based coating to seal concrete and steel surfaces from permanent radioactive contamination in an Arctic marine environment. A mobile, self-sufficient spraying device, was developed to specifications provided by the Russian Ministry of Defence Northern Navy and was deployed at the RTP Atomflot site, Murmansk, Russia. Demonstration coatings of Polibrid 705 were applied to concrete surfaces exposed to conditions ranging from indoor pedestrian usage to heavy vehicle passage and container handling in a loading bay. A large steel container was also coated with the polymer, filled with solid radwaste, sealed, and left out of doors and exposed to the full 12 month Arctic weather cycle. The field tests were accompanied by a series of laboratory qualification tests carried out at the research laboratory of ICC Nuclide in St. Petersburg. During the 12-month field tests, the sealant coating showed little sign of degradation except for a few chips and gouge marks on the loading bay surface that were readily repaired. Contamination resulting from radwaste handling was easily removed and the surface was not degraded by contact with the decontamination agents. In the laboratory testing, Polibrid 705 met all the Russian qualification requirements with the exception of flammability. In this last instance, it was decided to restrict application of the coating to land-based facilities. The Russian technical experts from the Ministry of Defence quickly familiarized themselves with the equipment and were able to identify several areas of potential improvement as deployment of the equipment progressed. The prime among these was the desirability of extending the range of the equipment through enlarged gasoline tanks (to permit extended operational times) and longer

SOLID RADIOACTIVE WASTE STORAGE TECHNOLOGIES: PERFORMANCE OF A POLYMER SEALANT COATING IN AN ARCTIC MARINE ENVIRONMENT

Energy Technology Data Exchange (ETDEWEB)

COWGILL,M.G.; MOSKOWITZ,P.D.; CHERNAENKO,L.M.; NAZARIAN,A.; GRIFFITH,A.; DIASHEV,A.; ENGOY,T.

2000-06-14

This first project, under the auspices of the Arctic Military Environmental Cooperation (AMEC) forum, Project 1.4-1 Solid Radioactive Waste Storage Technologies, successfully demonstrated the feasibility of using a polymer-based coating to seal concrete and steel surfaces from permanent radioactive contamination in an Arctic marine environment. A mobile, self-sufficient spraying device, was developed to specifications provided by the Russian Ministry of Defence Northern Navy and was deployed at the RTP Atomflot site, Murmansk, Russia. Demonstration coatings of Polibrid 705 were applied to concrete surfaces exposed to conditions ranging from indoor pedestrian usage to heavy vehicle passage and container handling in a loading bay. A large steel container was also coated with the polymer, filled with solid radwaste, sealed, and left out of doors and exposed to the full 12 month Arctic weather cycle. The field tests were accompanied by a series of laboratory qualification tests carried out at the research laboratory of ICC Nuclide in St. Petersburg. During the 12-month field tests, the sealant coating showed little sign of degradation except for a few chips and gouge marks on the loading bay surface that were readily repaired. Contamination resulting from radwaste handling was easily removed and the surface was not degraded by contact with the decontamination agents. In the laboratory testing, Polibrid 705 met all the Russian qualification requirements with the exception of flammability. In this last instance, it was decided to restrict application of the coating to land-based facilities. The Russian technical experts from the Ministry of Defence quickly familiarized themselves with the equipment and were able to identify several areas of potential improvement as deployment of the equipment progressed. The prime among these was the desirability of extending the range of the equipment through enlarged gasoline tanks (to permit extended operational times) and longer

Introduction to the outlines of radwaste administration policy of the Republic of China

International Nuclear Information System (INIS)

Huang, C.C.; Tsai, C.M.

1992-01-01

This paper discusses the Radwaste Administration Policy (ORAP) which first drafted by the Radwaste Administration (RWA), a subordinate organization of the Atomic Energy Council (AEC) of the Republic of China, and was approved by the Executive Yuan (Cabinet) on September 16, 1988. ORAP has laid down the guidelines for both radwaste administration by RWA and radwaste management by Taiwan Power Company (TPC or Taipower) and other radwaste producers. ORAP will govern radwaste-related activities in the Republic of China in the foreseeable future. The text of ORAP is shown in the Appendix of this paper

The strategy of radwaste management in Slovenia

International Nuclear Information System (INIS)

Loose, A.; Babsek, B.; Jeran, M.

1994-01-01

This paper's intention is to show the present situation and future activities of the Agency for radwaste management. It was established by the slovene government to provide the strategy for a safe management of radioactive waste. The safety is the main concern of the Agency, since the situation in Slovenia is quite complex as it is a small country with a limited number of suitable locations and a strong public opposition towards anything connected with nuclear power generation or radioactivity in general. The emphasis of the Agency's activities at the moment is siting and technology selection for low level waste and intermediate level waste repository as well as solutions on interim storage of high level waste

Duke Power's liquid radwaste processing improvement efforts

International Nuclear Information System (INIS)

Baker, R.E. Jr.; Bramblett, J.W.

1995-01-01

The rising cost of processing liquid radwaste and industry efforts to reduce offsite isotopic contributions has drawn greater attention to the liquid radwaste area. Because of economic pressures to reduce cost and simultaneously improve performance, Duke Power has undertaken a wide ranging effort to cost effectively achieve improvements in the liquid radwaste processing area. Duke Power has achieved significant reductions over recent years in the release of curies to the environment from the Liquid Radwaste Treatmentt systems at its Catawba, McGuire, and Oconee stations. System wide site curie reductions of 78% have been achieved in a 3 year period. These curie reductions have been achieved while simultaneously reducing the amount of media used to accomplish treatment. The curie and media usage reductions have been achieved at low capital cost expenditures. A large number of approaches and projects have been used to achieve these curie and media usage reductions. This paper will describe the various projects and the associated results for Duke Power's processing improvement efforts. The subjects/projects which will be described include: (1) Cooperative philosophy between stations (2) Source Control (3) Processing Improvements (4) Technology Testing

Perry Nuclear Plant's Plans for on-site storage

International Nuclear Information System (INIS)

Ratchen, J.T.

1993-01-01

Because of current radwaste disposal legislation and the eventual denial of access to the Barnwell, Richland, and Beatty burial sites, it was imperative for the Perry nuclear power plant to develop alternative means for handling its generated radioactive waste. The previous radwaste facilities at Perry were developed for processing, packaging, short-term storage, and shipment for burial. In order to meet the changing needs, new facilities have been constructed to handle the processing, packaging, and 5-yr interim storage of both dry active waste (DAW) and dewatered or solidified resin, filter media, etc

Maximized liquid radwaste volume reduction through a total integrated process: A new technology success story

International Nuclear Information System (INIS)

Rae, G.A.

1996-01-01

A fundamental nuclear industry goal is the minimization of the generation of radioactive waste. This goal has been dramatically reinforced over the past few years due to the spiraling increased costs of both commercial and DOE disposal. To assist in meeting these goals and reducing the industry's costs, NUKEM initiated a new technology program to maximize the reduction of liquid radwaste through the use of a systematic approach or TIPS (Total Integrated Process System). This concept evaluates the total life cycle of various technologies in a combination that results in the final waste form being minimized to the pure solids content of the waste stream. Additionally, it allows for a final waste form that maximizes the utilization of the waste package and is conditioned to be readily acceptable to additional processing to meet new waste form requirements at future disposal sites, should interim storage of the waste be required. The TIPS, although first introduced at commercial facilities, has broad applications for DOE's liquid waste streams

Sacramento Municipal Utility district's interim onsite storage building for low level radioactive waste

International Nuclear Information System (INIS)

Gillis, E.

1986-01-01

In order to meet current and anticipated needs for the low level radwaste management program at the Rancho Seco Nuclear Generating Station, the Sacramento Municipal Utility District has a design and construction program underway which will provide an onsite interim storage facility that can be expanded in two and one-half year increments. The design approach utilized allows capital investment to be minimized and still provides radwaste management flexibility in anticipation of delays in resolution of the nationwide long term radwaste disposal situation. The facility provides storage and material accountability for all low level radwastes generated by the plant. Wastes are segregated by radioactivity level and are stored in two separate storage areas located within one facility. Lower activity wastes are stored in a lightly shielded structure and handled by lift trucks, while the higher activity wastes are stored in a highly shielded structure and handled remotely by manual bridge crane. The layout of the structure provides for economy of operation and minimizes personnel radiation exposure. Design philosophy and criteria, building layout and systems, estimated costs and construction schedule are discussed

Safety analysis report for radwaste foam transport cask

International Nuclear Information System (INIS)

Ku, J. H.; Lee, J. C.; Bang, K. S.; Seo, K. S.; Lee, D. W.; Kim, J. H.; Park, S. W.; Lee, J. W.; Kim, K. H.

1999-08-01

For the tests and examinations of radwaste foam which generated in domestic nuclear power plants a radioactive material transport cask is needed to transport the radwaste foam from the power plants to KAERI. This cask should be easy to handle in the facilities and safe to maintain the shielding safety of operators. According to the regulations, it should be verified that this cask maintains the thermal and structural integrities under prescribed load conditions by the regulations. The basic structural functions and the integrities of the cask under required load conditions were evaluated. Therefore, it was verified that the cask is suitable to transport radwaste foam from nuclear power plants to KAERI. (author). 11 refs., 10 tabs., 25 figs

Peculiarities of the High-Level Concrete-Encased Radwaste Repository Disposition at the Radwaste Disposal Site of the Russian Research Center 'Kurchatov Institute'

International Nuclear Information System (INIS)

Volkov, V.G.; Ponomarev-Stepnoi, N.N.; Gorodetsky, G.G.; Zverkov, Yu.A.; Ivanov, O.P.; Lemus, A.V.; Semenov, S.G.; Stepanov, V.E.; Chesnokov, A.V.; Shisha, A.D.

2006-01-01

The paper presents peculiarities of organization and performance of activities on disposition of the old repository that contained high-level waste and located at the radwaste disposal site of the Russian Research Center 'Kurchatov Institute' in Moscow. The repository was constructed in the late 1950's. A large number of cases with high-level waste were placed in the repository along with low- and intermediate-level waste. When the repository was filled in 1973, the entire radwaste mass was encased in concrete matrix which caused difficulties with the radwaste extraction and made the work on the repository disposition highly hazardous in terms of radiation conditions. Based on results of the preliminary radiation survey of the repository, technologies and equipment to be used in disposition works were selected, and a decision on construction of external radiation shielding around the repository to maintain normal radiation conditions during these works was made. Specific features of the selected radiation shielding design constructed around the repository and of a technology used for the radwaste extraction from the repository are provided. According to the technology, conventional construction machines equipped with a hydraulic hammer or a clamshell were used for destruction of the concrete-encased radwaste mass and extraction of low-level waste. Intermediate- and high-level waste was extracted by remotely controlled robots operating inside the radiation shielding structure. Video cameras and a gamma imager were used for detection of high-level waste or fragments of such radwaste in the mass concrete being destroyed and for guiding remotely controlled robots. Peculiarities of rapid control of changes in radiation conditions in the working areas are presented. This control was performed using a gamma locator with on-line transmission of its data to a PC for their processing. With disposition of this not easily accessible repository, the stage of remediation of old

Establishment and status of the radwaste management standards in China

International Nuclear Information System (INIS)

Zhuo Fengguan

1993-01-01

In the last 30 years and more, with the development of nuclear industry in China, the government, nuclear industry circles and scientists have paid great attention to the safety management of radwastes. Especially in past 10 years, with the implementation of the nuclear power programmes, the safety management of radwastes has been legalized steadily NEPA (National Environment Protection Agency, China), NNSA (National Nuclear Safety Administration) and the competent authorities concerned have engaged in establishing and promulgating policies, regulations, and a series of technical standards on the safety management of radwaste, and efforts are being made to complete and perfect related regulations and standards. The status and programs of radwaste safety management standards in China are briefly introduced, including principles, organizations and procedure for drafting the standards

Fluidized bed volume reduction of diverse radwastes

International Nuclear Information System (INIS)

McFee, J.N.; McConnell, J.W.; Waddoups, D.A.; Gray, M.F.; Harwood, L.E.; Clayton, N.J.; Drown, D.C.

1981-01-01

Method and apparatus for a fluidized bed radwaste volume reduction system are claimed. Low level radioactive wastes, combustible solids, ion exchange resins and filter sludges, and liquids, emanating from a reactor facility are introduced separately through an integrated waste influent system into a common fluidized bed vessel where volume reduction either through incineration or calcination occurs. Addition of a substance to the ion exchange resin before incineration inhibits the formation of low-melting point materials which tend to form clinkers in the bed. Solid particles are scrubbed or otherwise removed from the gaseous effluent of the vessel in an off-gas system, before the cooled and cleaned off-gas is released to the atmosphere. Iodine is chemically or physically removed from the off-gas. Otherwise, the only egress materials from the volume reduction system are containerized dry solids and tramp material. The bed material used during each mode may be circulated, cleaned, stored and exchanged from within the bed vessel by use of a bed material handling system. An instrumentation and control system provides operator information, monitors performance characteristics, implements start up and shut down procedures, and initiates alarms and emergency procedures during abnormal conditions

Development of sampling techniques for ITER Type B radwaste

International Nuclear Information System (INIS)

Hong, Kwon Pyo; Kim, Sung Geun; Jung, Sang Hee; Oh, Wan Ho; Park, Myung Chul; Kim, Hee Moon; Ahn, Sang Bok

2016-01-01

There are several difficulties and limitation in sampling activities. As the Type B radwaste components are mostly metallic(mostly stainless steel) and bulk(∼ 1 m in size and ∼ 100 mm in thickness), it is difficult in taking samples from the surface of Type B radwaste by remote operation. But also, sampling should be performed without use of any liquid coolant to avoid the spread of contamination. And all sampling procedures are carried in the hot cell red zone with remote operation. Three kinds of sampling techniques are being developed. They are core sampling, chip sampling, and wedge sampling, which are the candidates of sampling techniques to be applied to ITER hot cell. Object materials for sampling are stainless steel or Cu alloy block in order to simulate ITER Type B radwaste. The best sampling technique for ITER Type B radwaste among the three sampling techniques will be suggested in several months after finishing the related experiment

Development of sampling techniques for ITER Type B radwaste

Energy Technology Data Exchange (ETDEWEB)

Hong, Kwon Pyo; Kim, Sung Geun; Jung, Sang Hee; Oh, Wan Ho; Park, Myung Chul; Kim, Hee Moon; Ahn, Sang Bok [KAERI, Daejeon (Korea, Republic of)

2016-05-15

There are several difficulties and limitation in sampling activities. As the Type B radwaste components are mostly metallic(mostly stainless steel) and bulk(∼ 1 m in size and ∼ 100 mm in thickness), it is difficult in taking samples from the surface of Type B radwaste by remote operation. But also, sampling should be performed without use of any liquid coolant to avoid the spread of contamination. And all sampling procedures are carried in the hot cell red zone with remote operation. Three kinds of sampling techniques are being developed. They are core sampling, chip sampling, and wedge sampling, which are the candidates of sampling techniques to be applied to ITER hot cell. Object materials for sampling are stainless steel or Cu alloy block in order to simulate ITER Type B radwaste. The best sampling technique for ITER Type B radwaste among the three sampling techniques will be suggested in several months after finishing the related experiment.

A reliability-risk modelling of nuclear rad-waste facilities

International Nuclear Information System (INIS)

Lehmann, P.H.; El-Bassioni, A.A.

1975-01-01

Rad-waste disposal systems of nuclear power sites are designed and operated to collect, delay, contain, and concentrate radioactive wastes from reactor plant processes such that on-site and off-site exposures to radiation are well below permissible limits. To assist the designer in achieving minimum release/exposure goals, a computerized reliability-risk model has been developed to simulate the rad-waste system. The objectives of the model are to furnish a practical tool for quantifying the effects of changes in system configuration, operation, and equipment, and for the identification of weak segments in the system design. Primarily, the model comprises a marriage of system analysis, reliability analysis, and release-risk assessment. Provisions have been included in the model to permit the optimization of the system design subject to constraints on cost and rad-releases. The system analysis phase involves the preparation of a physical and functional description of the rad-waste facility accompanied by the formation of a system tree diagram. The reliability analysis phase embodies the formulation of appropriate reliability models and the collection of model parameters. Release-risk assessment constitutes the analytical basis whereupon further system and reliability analyses may be warranted. Release-risk represents the potential for release of radioactivity and is defined as the product of an element's unreliability at time, t, and the radioactivity available for release in time interval, Δt. A computer code (RARISK) has been written to simulate the tree diagram of the rad-waste system. Reliability and release-risk results have been generated for cases which examined the process flow paths of typical rad-waste systems, the effects of repair and standby, the variations of equipment failure and repair rates, and changes in system configurations. The essential feature of this model is that a complex system like the rad-waste facility can be easily decomposed into its

SOLID-STATE STORAGE DEVICE FLASH TRANSLATION LAYER

DEFF Research Database (Denmark)

2017-01-01

Embodiments of the present invention include a method for storing a data page d on a solid-state storage device, wherein the solid-state storage device is configured to maintain a mapping table in a Log-Structure Merge (LSM) tree having a C0 component which is a random access memory (RAM) device...

Safety and optimization aspects of radioactive waste long-term storage at the ''Vector'' site

International Nuclear Information System (INIS)

Tokarevs'kij, O.V.; Kondrat'jev, S.M.; Aleksjejeva, Z.M.; Ribalka, N.V.

2015-01-01

The paper analyzes links between the final disposal option and needs for long-term storage of radioactive waste taking into proposals on possible changes in radwaste classification as regards disposal. It considers the conceptual approach to design facilities for long-term storage of long-lived radioactive waste at the Vector site and approaches to apply requirements of regulatory documents, radiation safety principles and criteria for long-term storage of radwaste and safety assessment.

Calcined solids storage facility closure study

International Nuclear Information System (INIS)

Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C.

1998-02-01

The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a open-quotes Settlement Agreementclose quotes (or open-quotes Batt Agreementclose quotes) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed

Calcined solids storage facility closure study

Energy Technology Data Exchange (ETDEWEB)

Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C. [and others

1998-02-01

The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a {open_quotes}Settlement Agreement{close_quotes} (or {open_quotes}Batt Agreement{close_quotes}) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed.

Verification test of an engineering-scale multi-purpose radwaste incinerator

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The verification test of an engineering-scale multi-purpose radwaste incinerator was implemented. The test items include performance determination for the system when solid wastes (include resins) or spent oil were incinerating and off gas was cleaning, tracer test for determining decontamination factor and 72 h continuos running test. 500 h tests verify the reliability and feasibility of designs of technological process, main structure, instrument control and system safety. The incineration system ran smoothly, devices and instruments worked stably. The specifications such as capacity, volume reduction factor, carbon remainder in ash and decontamination factor all meet the design requirements

Integrated data base for spent fuel and radwaste: inventories

International Nuclear Information System (INIS)

Notz, K.J.; Carter, W.L.; Kibbey, A.H.

1982-01-01

The Integrated Data Base (IDB) program provides and maintains current, integrated data on spent reactor fuel and radwaste, including historical data, current inventories, projected inventories, and material characteristics. The IDB program collects, organizes, integrates, and - where necessary - reconciles inventory and projection (I/P) and characteristics information to provide a coherent, self-consistent data base on spent fuel and radwaste

Integrated radwaste treatment system. Final report

International Nuclear Information System (INIS)

Baker, M.N.; Houston, H.M.

1997-10-01

In May 1988, the West Valley Demonstration Project (WVDP) began pretreating liquid high-level radioactive waste (HLW). This HLW was produced during spent nuclear fuel reprocessing operations that took place at the Western New York Nuclear Service Center from 1966 to 1972. Original reprocessing operations used plutonium/uranium extraction (PUREX) and thorium extraction (THOREX) processes to recover usable isotopes from spent nuclear fuel. The PUREX process produced a nitric acid-based waste stream, which was neutralized by adding sodium hydroxide to it. About two million liters of alkaline liquid HLW produced from PUREX neutralization were stored in an underground carbon steel tank identified as Tank 8D-2. The THOREX process, which was used to reprocess one core of mixed uranium-thorium fuel, resulted in about 31,000 liters of acidic waste. This acidic HLW was stored in an underground stainless steel tank identified as Tank 8D-4. Pretreatment of the HLW was carried out using the Integrated Radwaste Treatment System (IRTS), from May 1988 until May 1995. This system was designed to decontaminate the liquid HLW, remove salts from it, and encapsulate the resulting waste into a cement waste form that achieved US Nuclear Regulatory Commission (NRC) criteria for low-level waste (LLW) storage and disposal. A thorough discussion of IRTS operations, including all systems, subsystems, and components, is presented in US Department of Energy (DOE) Topical Report (DOE/NE/44139-68), Integrated Radwaste Treatment System Lessons Learned from 2 1/2 Years of Operation. This document also presents a detailed discussion of lessons learned during the first 2 1/2 years of IRTS operation. This report provides a general discussion of all phases of IRTS operation, and presents additional lessons learned during seven years of IRTS operation

Hot Isostatic Press (HIP) vitrification of radwaste concretes

International Nuclear Information System (INIS)

Siemer, D.D.; Scheetz, B.; Gougar, M.L.D.

1995-01-01

Properly formulated and properly ''canned'' radwaste concretes can be readily hot-isostatically-pressed (HIPed) into materials that exhibit performance equivalent to typical radwaste-type glasses. The HIPing conditions (temperature/pressure) required to turn a concrete waste form into a ''vitrified'' waste form are quite mild and therefore consistent with both safety and high productivity. This paper describes the process and its products with reference to its potential application to Idaho Chemical Processing Plant (ICPP) reprocessing wastes

Cost-benefit analysis for environmental impacts and radwaste system for nuclear power plant

International Nuclear Information System (INIS)

Mun, K.N.; Yook, C.C.

1982-01-01

During operation of nuclear power plant, radioactive material is inevitably formed. This radioactive material must be safely processed by radwaste system so that essentially zero activity is released to the environment. However zero released activity is not really practicable and population doses resulted from released activity are proportional to total annual cost for the radwaste system. In this study, cost-benefit analysis for the radwaste system of the Korean Nuclear Units 5 and 6 is performed to evaluate the optimization between the total annual cost for the radwaste system and population doses within 80 km from the plants. From the analysis, the following results are obtained; 1. the total population dose is estimated 4.04 x 10 3 man-rem/year, 2. total annual cost for the radwaste system is required $ 1.74 x 10 6 , 3. cost-benefit ratio is estimated $ 429/man-rem. (Author)

Minimum radwaste system to support commercial operation-what equipment can be deferred

International Nuclear Information System (INIS)

Marshall, R.W.; Tafazzoli, M.M.

1984-01-01

Because of cash flow problems being experienced by utilities as nuclear power stations approach completion, areas of the plant for which the completion of the construction effort could be deferred past commercial operation should be reviewed. The radwaste treatment systems are prime candidates for such a deferral because of the availability, either temporary or permanent, of alternative treatment methods for the waste streams expected to be produced. In order to identify the radwaste equipment, components and associated hardware in the radwaste building which could be deferred past commercial operation, a study was performed by Impell Corporation to evaluate the existing radwaste treatment system and determine the minimum system necessary to support commercial operation of a typical BWR. The study identified the minimum-installed radwaste treatment system which, in combination with portable temporary equipment, would accommodate the waste types and quantities likely to be produced in the first few years of operation. In addition, the minimum-installed system had to be licensable and excessive radiation exposures should not be incurred during the construction of the deferred portions of the system after commercial operation. From this study, it was concluded that a significant quantity of radwaste processing equipment and the associated piping, valves and instrumentation could be deferred. The estimated savings, in construction manhours (excluding field distributables) alone, was over 102,000 M-H

CNAEM waste processing and storage facility

International Nuclear Information System (INIS)

Osmanlioglu, A.E.; Kahraman, A.; Altunkaya, M.

1998-01-01

Radioactive waste in Turkey is generated from various applications. Radioactive waste management activities are carried out in a facility at Cekmece Nuclear Research and Training Center (CNAEM). This facility has been assigned to take all low-level radioactive wastes generated by nuclear applications in Turkey. The wastes are generated from research and nuclear applications mainly in medicine, biology, agriculture, quality control in metal processing and construction industries. These wastes are classified as low- level radioactive wastes and their activities are up to 10 -3 Ci/m 3 (except spent sealed sources). Chemical treatment and cementation of liquid radwaste, segregation and compaction of solid wastes and conditioning of spent sources are the main processing activities of this facility. A.so, analyses, registration, quality control and interim storage of conditioned low-level wastes are the other related activities of this facility. Conditioned wastes are stored in an interim storage building. All waste management activities, which have been carried out in CNAEM, are generally described in this paper. (author)

Radwaste reduction experience at Oyster Creek and Three Mile Island Nuclear Power Plants

International Nuclear Information System (INIS)

Ross, M.

1993-01-01

True radwaste minimization at an operating nuclear power plant means straddling the line between ''what is'' and ''what-can-be'' and then regularly moving that line so that dreams become reality. This effort involves keeping track of and maintaining successful programs of the past while searching out and incorporating the best of the upcoming processes, equipment, and contractors. Some of the tactics used for waste minimization have appreciable results and some have small direct results. But even those with small results add to a final total of volume saved. In addition, the approaches with smaller results demonstrate an unmistakable attitude on the part of management that any unnecessary radwaste production is not acceptable. This attitude is understood and assimilated by engineering, operations, and maintenance in such a way that it becomes a matter of pride to reduce radwaste production to quantities below those officially projected. The GPUN plants at Oyster Creek and Three Mile Island Unit-1 limit the quantity of materials allowed onsite under the premise that an item that stays out of contaminated areas cannot become radwaste. For material exiting contaminated zones, the plants have used a combination of preventative avoidance of radwaste generation and careful processing. This includes sorting and screening of materials leaving contaminated areas to reduce the number of items to eventually be treated, preplanning of work efforts to minimize radwaste that must be generated, wood planning, onsite decontamination units, onsite contractor supplied equipment, and offsite radwaste processors in order to minimize the final amount of radwaste to be buried. Sometimes when employing one of these methods, it is necessary to consider not only the waste generated by the process directly but also secondary wastes caused by interactions with other areas of plant operation, such as equipment maintenance

Treatment of LL and ML liquid radwaste. The SGN experience

International Nuclear Information System (INIS)

Tchemitcheff, E.; Roux, P.

1993-01-01

SGN (Societe Generale pour les Techniques Nouvells) with considerable know-how and thirty years of feed-back in industrial management of liquid effluents from the entire French nuclear industry, has accordingly completed many low- and medium-level liquid radwaste treatment, relying on two major industrially proven technologies: evaporation and chemical coprecipitation. The low level and medium level radwaste in France and evaluated

Breaking the paradigm: Revitalizing the liquid radwaste program at River Bend Station

International Nuclear Information System (INIS)

Mallory, C.C. II; Lewis, C.A.

1996-01-01

In December 1995, River Bend Station established the goal of becoming a liquid radwaste open-quotes zero dischargeclose quotes plant by 1998. A new paradigm was required to reduce River Bend Station's annual discharge volume from over 7.5 million gallons in 1995 to open-quotes zeroclose quotes gallons in two years. Changes instituted to date include. (1) Creation of a cross-discipline natural work team (NWT) responsible for radwaste improvements. (2) Enhanced walnut shell filter performance using a polymer filter aid. (3) Activated charcoal to reduce total organic carbon (TOC). (4) Improved operating practices based upon data review and trending. (5) Improved operability of radwaste equipment. Results are encouraging. The volume discharged January through May 1996, including a 39 day refueling outage, is 1.25 million gallons. Only one discharge has occurred since March 2. Historically, discharge volume during a similar five month period has exceeded 3 million gallons. No additional discharges are planned for 1996. Additional improvements are being actively evaluated. These include more effective radwaste train media, UV/O3 decomposition of TOC, adding non-precoated filters to the radwaste stream, reverse osmosis and real-time trending of inleakage volume and TOC and source term reduction

On giving radwaste management some status

International Nuclear Information System (INIS)

Dickson, H.W.; Walker, E.E.; Thiesing, J.W.

1987-01-01

Radwaste management is receiving ever increasing attention in the nuclear industry. The reasons for this include limited allocations for burial, increasing costs of handling and disposal, increased regulatory attention, and ALARA requirements. These issues have lead to an increasing awareness of the disadvantages of running a ''dirty'' plant and a variety of sophisticated systems have been proposed to fix the problem. Instead of these technologically difficult, and sometimes very expensive fixes, this paper focuses on several relatively simple ''low tech,'' and inexpensive solutions. Much can be done with organizational alternatives and assigned responsibilities and authorities to improve the situation. Applying controls on the front end of a radiological task rather than attempting to reduce the magnitude at the back end is the only realistic method for proper radwaste management

Fire propagation through arrays of solid-waste storage drums

International Nuclear Information System (INIS)

Smith, S.T.; Hinkle, A.W.

1995-01-01

The extent of propagation of a fire through drums of solid waste has been an unresolved issue that affects all solid-waste projects and existing solid-waste storage and handling facilities at the Hanford site. The issue involves the question of how many drums of solid waste within a given fire area will be consumed in a design-basis fire for given parameters such as drum loading, storage arrays, initiating events, and facility design. If the assumption that all drums of waste within a given fire area are consumed proves valid, then the construction costs of solid waste facilities may be significantly increased

Solid-solid phase change thermal storage application to space-suit battery pack

Science.gov (United States)

Son, Chang H.; Morehouse, Jeffrey H.

1989-01-01

High cell temperatures are seen as the primary safety problem in the Li-BCX space battery. The exothermic heat from the chemical reactions could raise the temperature of the lithium electrode above the melting temperature. Also, high temperature causes the cell efficiency to decrease. Solid-solid phase-change materials were used as a thermal storage medium to lower this battery cell temperature by utilizing their phase-change (latent heat storage) characteristics. Solid-solid phase-change materials focused on in this study are neopentyl glycol and pentaglycerine. Because of their favorable phase-change characteristics, these materials appear appropriate for space-suit battery pack use. The results of testing various materials are reported as thermophysical property values, and the space-suit battery operating temperature is discussed in terms of these property results.

Program plan for the development of Solid Waste Storage Area 7 at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Lomenick, T.F.; Gonzales, S.; Byerly, D.W.

1984-02-01

The need for additional waste-burial facilities for low-level radwastes generated at Oak Ridge National Laboratory mandates development of a program to identify and evaluate an acceptable new Solid Waste Storage Area (SWSA 7). Provisions of this program include plans for identifying and evaluating SWSA 7 as well as plans for the necessary technical efforts for designing and monitoring a waste-burial facility. The development of the program plan is in accordance with general procedures issued by ORNL, and if adhered to, should meet proposed criteria and guidelines issued by such organizations as the Nuclear Regulatory Commission, the Environmental Protection Agency, the Department of Energy, and the Tennessee Department of Health. The major parts of the program include plans for (1) the acquisition of data necessary for geotechnical evaluation of a site, (2) the engineering design and construction of a facility which would be compatible with the geology and the classification and particular character of the wastes to be disposed, and (3) a monitoring system for achieving health and safety standards and environmental protection. The objective of the program, to develop SWSA 7, can only be achieved through sound management. Plans provided in this program which will ensure successful management include quality assurance, corrective measures, safety analysis, environmental impact statements, and schedule and budget

The history of radwaste at Zion Station - its problems and solutions

International Nuclear Information System (INIS)

Bennett, K.J.

1982-01-01

Zion Station is located adjacent to Lake Michigan about 40 miles north of Chicago. The twin Zion units are four loop PWR's each rated at 1080 MWE with units 1 and 2 beginning commercial operation in 1973 and 1974 respectively. The radwaste system at Zion Station was designed in 1967 when radwaste operations of a nuclear power plant received little consideration. At Zion, the system was to be automated with occasional operator interface to pump down a tank when full or to solidify waste. The solidification equipment purchased was designed for the 40 year life of the station; due to the under estimation of the input to radwaste, this was not the case

Integrated radwaste treatment system lessons learned from 2 1/2 years of operation

International Nuclear Information System (INIS)

Baker, M.N.; Fussner, R.J.

1997-05-01

The Integrated Radwaste Treatment System (IRTS) at the West Valley Demonstration Project (WVDP) is a pretreatment scheme to reduce the amount of salts in the high-level radioactive waste (vitrification) stream. Following removal of cesium-137 (Cs-137) by ion-exchange in the Supernatant Treatment System (STS), the radioactive waste liquid is volume-reduced by evaporation. Trace amounts of Cs-137 in the resulting distillate are removed by ion-exchange, then the distillate is discharged to the existing plant water treatment system. The concentrated product, 37 to 41 percent solids by weight, is encapsulated in cement producing a stable, low-level waste form. The Integrated Radwaste Treatment System (IRTS) operated in this mode from May 1988 through November 1990, decontaminating 450,000 gallons of high-level waste liquid; evaporating and encapsulating the resulting concentrates into 10,393 71-gallon square drums. A number of process changes and variations from the original operating plan were required to increase the system flow rate and minimize waste volumes. This report provides a summary of work performed to operate the IRTS, including system descriptions, process highlights, and lessons learned

Preparation and characterization of a novel polymeric based solid-solid phase change heat storage material

International Nuclear Information System (INIS)

Xi Peng; Gu Xiaohua; Cheng Bowen; Wang Yufei

2009-01-01

Here we reported a two-step procedure for preparing a novel polymeric based solid-solid phase change heat storage material. Firstly, a copolymer monomer containing a polyethylene glycol monomethyl ether (MPEG) phase change unit and a vinyl unit was synthesized via the modification of hydrogen group of MPEG. Secondly, by copolymerization of the copolymer monomer and phenyl ethylene, a novel polymeric based solid-solid phase change heat storage material was prepared. The composition, structure and properties of the novel polymeric based solid-solid phase change material were characterized by IR, 1 H NMR, DSC, WAXD, and POM, respectively. The results show that the novel polymeric based solid-solid phase change material possesses of excellent crystal properties and high phase change enthalpy.

National Radwaste Repository Mochovce

International Nuclear Information System (INIS)

2000-01-01

In this leaflet the National Radioactive Waste Repository in Mochovce (Repository) is described. The Mochovce National Radioactive Waste Repository is a surface multi-barrier type storage facility for solid and treated solidified radioactive wastes generated from the Slovak Republic nuclear power plants operation and decommissioning, research institutes, laboratories and hospitals. The Repository comprises a system of single- and double-row storage boxes. The first double-row is enclosed by a steel-structure building. The 18 x 6 x 5.5 m storage boxes are made of reinforced concrete. The wall thickness is 600 mm. Two-double-rows, i.e. 80 storage boxes were built as part of Stage I (1 row = 20 storage boxes). Each storage box has a storage capacity of 90 fibre concrete containers of 3.1 m 3 volume. The total storage capacity is 7200 containers with the overall storage volume of 22320 m 3

The economics of radwaste volume reduction strategies

International Nuclear Information System (INIS)

Giuffre, M.; Ensminger, D.; Nalbandian, J.; Naughton, M.

1984-01-01

A recently concluded EPRI study has generated much of the information needed by utilities when they consider the purchase of volume reduction equipment. This paper presents some of the study's results on volume reduction economics. The paper contains two types of results. The first is a detailed look at the economics of fourteen equipment options at a hypothetical reactor station. Costs were calculated with VRTECH, a radwaste economics computer program developed by TASC. This analysis illustrates the major points of the project conclusions. Second, the effects of the major assumptions used in the hypothetical case are examined. This analysis shows that the radwaste generation rate and the burial cost escalation rate are primary considerations when evaluating the benefit of each option

Evaluation of radwaste minimization program of dry and wet active waste in the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Luna-Garza, Hector

2001-01-01

A growing rate of radwaste volume production combined with an increase of both, costs and associated dose involved in its treatment and disposition processes have created a serious problem to the Laguna Verde Nuclear Power Plant (BWR, two Units, 682 Mwe each) in Mexico. Due the lack of a Final Repository in the country, the solution in the short or long terms relies on the success of a continuous and aggressive minimization program mainly based on modifications and upgrades applied to these processes. Technical and administrative strategies adopted by LVNPP for the reduction of Liquid Effluents and Dry and Wet Active Waste in the next three years are described. Based on the results of the LVNPP current radwaste process systems, an estimated accumulation of 11,502 m 3 by the year 2035 will exceed the actual on-site storage capacity. If the strategies succeed, this production would fall to an expected manageable volume of 4067 m 3 . (author)

Standardized Testing Program for Solid-State Hydrogen Storage Technologies

Energy Technology Data Exchange (ETDEWEB)

Miller, Michael A. [Southwest Research Institute; Page, Richard A. [Southwest Research Institute

2012-07-30

In the US and abroad, major research and development initiatives toward establishing a hydrogen-based transportation infrastructure have been undertaken, encompassing key technological challenges in hydrogen production and delivery, fuel cells, and hydrogen storage. However, the principal obstacle to the implementation of a safe, low-pressure hydrogen fueling system for fuel-cell powered vehicles remains storage under conditions of near-ambient temperature and moderate pressure. The choices for viable hydrogen storage systems at the present time are limited to compressed gas storage tanks, cryogenic liquid hydrogen storage tanks, chemical hydrogen storage, and hydrogen absorbed or adsorbed in a solid-state material (a.k.a. solid-state storage). Solid-state hydrogen storage may offer overriding benefits in terms of storage capacity, kinetics and, most importantly, safety.The fervor among the research community to develop novel storage materials had, in many instances, the unfortunate consequence of making erroneous, if not wild, claims on the reported storage capacities achievable in such materials, to the extent that the potential viability of emerging materials was difficult to assess. This problem led to a widespread need to establish a capability to accurately and independently assess the storage behavior of a wide array of different classes of solid-state storage materials, employing qualified methods, thus allowing development efforts to focus on those materials that showed the most promise. However, standard guidelines, dedicated facilities, or certification programs specifically aimed at testing and assessing the performance, safety, and life cycle of these emergent materials had not been established. To address the stated need, the Testing Laboratory for Solid-State Hydrogen Storage Technologies was commissioned as a national-level focal point for evaluating new materials emerging from the designated Materials Centers of Excellence (MCoE) according to

Radwaste '86: proceedings volume

International Nuclear Information System (INIS)

Ainslie, L.C.

1986-12-01

The volume contains all the papers presented at the above Conference, which was held in Cape Town, South Africa from 7 to 12 September 1986. A total of 55 contributions cover the full spectrum of the theme of the Conference, which was subdivided into four sessions. Conditioning, treatment and management of radioactive waste: 12 papers reporting on experiences in various countries, as well as specialist topics such as the extraction of radioactive contaminants from reactor pool water. Containment, safe handling and long-term integrity of ILLW packages: 2 papers dealing with cask design. Transport and storage of radwaste and spent fuel: 7 papers ranging from broad overviews to specific operations in different parts of the world. Radioactive waste disposal and environmental impact: 32 papers covering topics from site selection, design and operation, to modelling and monitoring studies. South Africa's Vaalputs radioactive waste disposal facility is comprehensively described. The volume is a useful reference for anyone interested in the disposal of radioactive waste, especially in arid environments, as well as its treatment and management prior to disposal, and will appeal to a wide range of disciplines including engineers, geologists, geophysicists, life scientists and environmentalists. Of particular interest would be the intensive studies undertaken in South Africa prior to the establishment of a radioactive waste repository in that country

Latest development in project site radwaste treatment facility (SRTF) Sanmen

International Nuclear Information System (INIS)

Mennicken, K.; Lohmann, P.

2015-01-01

Westinghouse Electric Germany GmbH (WEG) was successful in being awarded a contract as to the planning, delivery, installation and commissioning of radwaste treatment systems for the AP1000 units at Sanmen site, PR China. Operational low and intermediate level radioactive waste will be processed in the Site Radwaste Treatment Facility (SRTF). This paper explains the latest developments of the project, especially the experience with customer-hired Chinese planning partners, installation companies and Customer operating personnel. (authors)

Evaluation of brazilian bentonites as additive in the radwaste cementation

International Nuclear Information System (INIS)

Tello, C.C.O. de.

1988-01-01

The behavior of some Brazilian bentonites has been evaluated, concerning to their use as additive in the radwaste cementation. The purpose of the bentonite is to retain the radioelements in the final product in leaching process. Experiments to determine properties such as compressive strenght, viscosity, set time leaching and cesium sorption have been carried out to this evaluation. After one-year test, the results show that the bentonites greatly reduce the cesium release. A literature survey about cementation process and plants and about the cement product characteristics has been made in order to obtain a reliable final product, able to be transported and storaged. Some leaching test methods and mathematical models, that could be applied in the evaluation of cement products with bentonite have been evaluated. (author) [pt

Preliminary safety assessment and preliminary safety report for the treated radwaste store, Winfrith

International Nuclear Information System (INIS)

Staples, A.T.

1992-06-01

It is the purpose of this assessment to define the categorisation of the Treated Radwaste Store, TRS, B55 at the Winfrith Technology Centre. Its further purpose is to cover all relevant sections required for a Preliminary Safety Report (PSR) encompassing the TRS and the integral Quality Assessment Unit (QUA). The TRS is designed for the interim storage of intermediate level radioactive wastes. All waste material stored in the TRS will be contained within 500 litre stainless steel drums acceptable to NIREX. It is proposed that the TRS will receive 500 litre stainless steel NIREX drums containing either irradiated DRAGON fuel or encapsulated sludge waste. (author)

Retrofit of radwaste solidification systems in Spain

International Nuclear Information System (INIS)

Rorcillo, R.; Virzi, E.

1983-01-01

In order to meet current Spanish engineering criteria as well as to provide for likely future Spanish Regulatory requirements, utilities committed to a major policy change in the preferred radwaste solidification media. In the early 1970's Spanish utilities, following the United States experience, purchased inexpensive solidification systems which used urea formaldehyde (UF) as the binding matrix. By the late 1970's the Spanish utilities, seeing the deterioration of the UF position and slow progress toward its improvement, unilaterally changed their binding matrix to cement. This paper illustrates the implementation of this change at the ASCO Nuclear Plant. The problems of layout modifications, shortened delivery schedule and criteria unique for Spain are addressed. Also presented is the operating experience acquired during the pre-operational start-up of the ASCO I Radwaste System

Thermal Analysis of Fission Moly Target Solid Waste Storage

Energy Technology Data Exchange (ETDEWEB)

Son, Hyung Min; Park, Jonghark [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

There are various ways to produce Mo-99. Among them, nuclear transmutation of uranium target became the major one owing to its superior specific activity. After the fission molybdenum (FM) target is irradiated, it is transported to treatment facility to extract wanted isotope. During the process, various forms of wastes are produced including filter cake and other solid wastes. The filter cake is mostly consisted of decaying uranium compounds. The solid wastes are then packaged and moved to storage facility which will stay there for considerable amount of time. Being the continuous source of heat, the solid wastes are required to be cooled for the certain amount of time before transported to the storage area. In this study, temperature evaluation of the storage facility is carried out with pre-cooling time sensitivity to check its thermal integrity. In this study, thermal analysis on the FM target solid waste storage is performed. Finite volume method is utilized to numerically discretize and solve the geometry of interest. Analysis shows that the developed method can simulate temperature behavior during storage process, but needs to be checked against other code to see calculation accuracy. Highest temperature distribution is observed when every hole is filled with waste containers. Sensitivity results on pre-cooling time shows that at least 13 months of cooling is necessary to keep the structure integrity.

Advanced materials for solid state hydrogen storage: “Thermal engineering issues”

International Nuclear Information System (INIS)

Srinivasa Murthy, S.; Anil Kumar, E.

2014-01-01

Hydrogen has been widely recognized as the “Energy Carrier” of the future. Efficient, reliable, economical and safe storage and delivery of hydrogen form important aspects in achieving success of the “Hydrogen Economy”. Gravimetric and volumetric storage capacities become important when one considers portable and mobile applications of hydrogen. In the case of solid state hydrogen storage, the gas is reversibly embedded (by physisorption and/or chemisorption) in a solid matrix. A wide variety of materials such as intermetallics, physisorbents, complex hydrides/alanates, metal organic frameworks, etc. have been investigated as possible storage media. This paper discusses the feasibility of lithium– and sodium–aluminum hydrides with emphasis on their thermodynamic and thermo-physical properties. Drawbacks such as poor heat transfer characteristics and poor kinetics demand special attention to the thermal design of solid state storage devices. - Highlights: • Advanced materials suitable for solid state hydrogen storage are discussed. • Issues related to thermodynamic and thermo-physical properties of hydriding materials are brought out. • Hydriding and dehydriding behavior including sorption kinetics of complex hydrides with emphasis on alanates are explained

Storage of long lived solid waste

International Nuclear Information System (INIS)

Ozarde, P.D.; Agarwal, K.; Gupta, R.K.; Gandhi, K.G.

2009-01-01

Long lived solid waste, generated during the fuel cycle mainly includes high level vitrified waste product, high level cladding hulls and low and intermediate level alpha wastes. These wastes require storage in specially designed engineered facilities before final disposal into deep geological repository. Since high-level vitrified waste contain heat generating radionuclides, the facility for their storage is designed for continuous cooling. High level cladding hulls undergo volume reduction by compaction and will be subsequently stored. (author)

Discussion of the question whether a local authority can claim to be affected in its planning competence by a permit issued for construction of a radwaste processing plant. High Administrative Court Lueneburg, judgement of 21.1.1993 - 7 K 5/90

International Nuclear Information System (INIS)

Czajka, D.

1993-01-01

A local authority has taken legal action against the first partial permit for the construction of a radwaste conditioning pilot plant at Gorleben, claiming to be affected in its planning competence by the fact that transport of spent fuel elements between the spent fuel storage facility and the pilot plant 2 km away would have to proceed on the rural district road. The action has been discussed. Appealable head notes: A local authority is not affected in its planning competence by a permit issued for construction of a facility for radwaste processing, although the operation of said facility may result in radwaste being transported by a road crossing the local authority's territory. (orig.) [de

Volume reduction and solidification of liquid and solid low-level radioactive waste

International Nuclear Information System (INIS)

May, J.R.

1979-01-01

This paper presents a brief background of the development of a method of radioactive waste volume reduction using a unique fluidized bed calciner/incinerator. The volume reduction system is capable of processing a variety of liquid chemical wastes, spent ion exchange resin beads, filter treatment sludges, contaminated lubricating oils, and miscellaneous combustible solids such as paper, rags, protective clothing, wood, etc. All of these wastes are processed in one chemical reaction vessel. Detailed process data is presented that shows the system is capable of reducing the total volume of disposable radioactive waste generated by light water reactors by a factor of 10. Equally important to reducing the volume of power reactor radwaste is the final form of the stored or disposable radwaste. This paper also presents process data related to a new radwaste solidification system, presently being developed, that is particularly suited for immobilizing the granular solids and ashes resulting from volume reduction by calcination and/or incineration

Storage and Disposal of Solid Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

Pomarola, J. [Head of Technical Section, Monitoring and Protection Division, Atomic Energy Commission, Saclay (France)

1960-07-01

This paper deals with solutions for the problem of final disposal of solid radioactive waste. I. It is first essential to organize a proper system of temporary storage. II. Final Storage In order to organize final storage, it is necessary to fix, according to the activity and form of the waste, the site and the modes of transport to be used within and outside the nuclear centre. The choice of solutions follows from the foregoing essentials. The paper then considers, in turn, final storage, on the ground, in the sub-soil and in the sea. Economic considerations are an important factor in determining the choice of solution. (author)

Radwaste requirements at a biomedical research facility

International Nuclear Information System (INIS)

Brannegan, D.P.; Wolter, W.; Merenda, J.M.; Figdor, S.K.

1993-01-01

The low-level radioactive waste (LLRW) federal legislation that was passed during the 1980s was intended to provide an orderly system of LLRW disposal as the country's three waste sites proceeded toward excluding out-of-state generators. The system was based on a regional interstate compact system. As originally envisioned, several contiguous states were to form an association (compact) with one state receiving radwaste from the compact. Everyone is aware of the difficulties that followed as attempts were made to implement these laws and to meet the prescribed milestones to avoid financial penalties. Although the states (compacts) have labored for over 12 yr along this rocky road, no compact has developed and licensed a new disposal site prior to the January 1, 1993 deadline. A recent report by the Center for the Study of American Business at Washington University in St. Louis states that open-quotes The current regional interstate compact system for disposal of low-level radioactive waste is fatally flawed on both technical and practical political grounds.close quotes Thus, the system has broken down and the three original LLRW sites closed their gates (with the possible exception of Barnwell) as planned on January 1, 1993. It would appear that the fate of LLRW will be the same as that of high-level waste (HLW); it will be stored at the site of the generator until a solution to the problem is found. For the nonutility generator, storage is an entirely new problem. It must be appreciated that almost all nonutility generators are in the business of research or medical treatment and not in the business of storing LLRW. Thus, storage represents a new turn of events and a new aspect of doing business. It also means the diversion of limited resources to a problem that should not exist. Lastly, on-site LLRW storage for the nonutility generator will also require additional regulatory approval for the handling, storage, and ongoing monitoring of this waste

Solid radwaste processing and conditioning. The SGN experience

International Nuclear Information System (INIS)

Tucoulat, D.; Tchemitcheff, E.

1993-01-01

Solid wastes are generated in the operation of the installations in France. These solid wastes display different levels of radioactivity. Some of them arising from research centres or reprocessing plants even contain relatively significant quantities of alpha-bearing radionuclides. In order to produce an ultimate waste package that satisfies the requirements set by safety authorities and the organizations in charge of final waste disposal in the concerned countries, solid waste conditioning takes place in a number of successive steps

The concept of partitioning/transmutation in radwaste management

International Nuclear Information System (INIS)

Guillaumont, R.

1993-01-01

It is trite to say that radwaste is more difficult to handle than conventional industrial waste because of its radioactivity. If many toxic chemical compounds can be destroyed by simple thermal incineration, non-radioactive substances whose radioactivity is linked to the presence of toxic elements give rise, because they undergo ''infinite decay'', to the same problems as long-lived radwaste. Radioactivity, because it involves the self-destruction of radionuclides, is more an advantage, as long as it does not result in stable toxic daughter elements, and as long as radioactive decay remains compatible with their reliable confinement. Disposal of A waste (low level waste), for which the radioactive decay period of the beta and/or gamma emitting radionuclides is of human-scale time periods, has become an industrial practice and there is no conceptual problem for this waste. However, management of B and C waste (alpha and high level waste) and, their storage, remain to day in the design stage. It is because they contain sizeable quantities of alpha, beta and gamma emitting radionuclides with radioactive decay periods much greater than human-scale time periods and because C waste generates heat, that the final stage of their management poses problems. These problems are of a complex nature for reasons of 1) science, 2) ethics 3) economics 4) sociology. The idea of modifying alpha and beta radioactivity in C waste to the point where it could disappear is not in itself a new idea. Over the past twenty years, in response to studies on the disposal of vitrified nuclear waste, this option has been raised on several occasions. It has suddenly resurfaced in the light as the topic of Partitioning Transmutation Concept (PTC). Japan and more recently France announced for the first time consistent research programmes. The idea of reduction of alpha radioactivity of the actual B waste is no more a new idea. It has recently come in light as a complementary idea, possibly

Mobilization and mixing of settled solids in horizontal storage tanks

International Nuclear Information System (INIS)

Cummins, R.L.

1995-01-01

Studies were conducted using submerged jets for the mobilization and mixing of settled solids to form a suspension that can easily be removed from storage tanks. These studies focus on the specific problems relating to horizontal, cylindrical storage tanks. Of primary consideration are the storage tanks located at the Oak Ridge National Laboratory which are used for the collection of remote-handled, radioactive liquid wastes. These wastes are in two phases. A layer of undissolved, settled solids varying from 2 to 4 feet in depth under a layer of supernate. Using a surrogate of the tank contents and an approximate 2/3 dimensional scale tank, tests were performed to determine the optimum design and location of suction and discharge nozzles as well as the minimum discharge velocity required to achieve complete mobilization of the solids in the tank

Correction: Large-scale electricity storage utilizing reversible solid oxide cells combined with underground storage of CO2 and CH4

DEFF Research Database (Denmark)

Jensen, Søren Højgaard; Graves, Christopher R.; Mogensen, Mogens Bjerg

2017-01-01

Correction for ‘Large-scale electricity storage utilizing reversible solid oxide cells combined with underground storage of CO2 and CH4’ by S. H. Jensen et al., Energy Environ. Sci., 2015, 8, 2471–2479.......Correction for ‘Large-scale electricity storage utilizing reversible solid oxide cells combined with underground storage of CO2 and CH4’ by S. H. Jensen et al., Energy Environ. Sci., 2015, 8, 2471–2479....

Proceedings: 2001 ASME/EPRI Radwaste Workshop

International Nuclear Information System (INIS)

2001-01-01

Nuclear utilities continually evaluate methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has increased the emphasis on this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technology and management improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

Solid Aluminum Borohydrides for Prospective Hydrogen Storage.

Science.gov (United States)

Dovgaliuk, Iurii; Safin, Damir A; Tumanov, Nikolay A; Morelle, Fabrice; Moulai, Adel; Černý, Radovan; Łodziana, Zbigniew; Devillers, Michel; Filinchuk, Yaroslav

2017-12-08

Metal borohydrides are intensively researched as high-capacity hydrogen storage materials. Aluminum is a cheap, light, and abundant element and Al 3+ can serve as a template for reversible dehydrogenation. However, Al(BH 4 ) 3 , containing 16.9 wt % of hydrogen, has a low boiling point, is explosive on air and has poor storage stability. A new family of mixed-cation borohydrides M[Al(BH 4 ) 4 ], which are all solid under ambient conditions, show diverse thermal decomposition behaviors: Al(BH 4 ) 3 is released for M=Li + or Na + , whereas heavier derivatives evolve hydrogen and diborane. NH 4 [Al(BH 4 ) 4 ], containing both protic and hydridic hydrogen, has the lowest decomposition temperature of 35 °C and yields Al(BH 4 ) 3 ⋅NHBH and hydrogen. The decomposition temperatures, correlated with the cations' ionic potential, show that M[Al(BH 4 ) 4 ] species are in the most practical stability window. This family of solids, with convenient and versatile properties, puts aluminum borohydride chemistry in the mainstream of hydrogen storage research, for example, for the development of reactive hydride composites with increased hydrogen content. © 2017 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Deep-well injection of liquid radwaste in Russia - current status and operations

International Nuclear Information System (INIS)

Bradley, D.J.; Foley, M.G.; Rybal'chenko, A.I.

1995-01-01

This paper is submitted as part of a coordinated effort to present the topic of deep-well injection. The companion paper, open-quotes Deep-Well Injection of Liquid Radwaste in Russia - Background and Technical Basis,close quotes focuses on the original decision to inject liquid radwaste, the research behind that decision, and the design and construction of the injection facilities. The emphasis in this paper is on the current status and operation of the well facilities and the control systems used to minimize environmental impact

Proceedings: 2000 ASME/EPRI Radwaste Workshop

International Nuclear Information System (INIS)

2001-01-01

Nuclear utilities are continually evaluating methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has added increased emphasis to this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technological and managerial improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

Bitumen and cement solidifications of LL and ML liquid radwaste. The SGN experience

International Nuclear Information System (INIS)

Tchemitcheff, E.; Roux, P.

1993-01-01

The presentation is focused on the thin-film evaporator technology and the experience gained in the field of the NPPs and research centers on radwaste conditioning. As early as 1970, SGN was licensed by the CEA for the bituminization of LL and ML radwaste. With the support of EDF and COGEMA, SGN has been performing in depth research on cement solidification of borated concentrates and ion exchange resins generated by reactors or reprocessing plant since 1983

Why is the NORM Waste Included in to the Croatian RadWaste Strategy

International Nuclear Information System (INIS)

Prlic, I.; Suric Mihic, M.; Hajdinjak, M.

2016-01-01

Croatian RADWASTE Strategy uses modern approach according to EC Directive 2013/59/EURATOM and Croatian Act on Radiological and Nuclear Safety (Official Gazette 141/13, 39/15) linking the entire field of, till modern times non regulated industrial NORM wastes to properly regulated RADWastes. This approach has brought some obscurities to a professional radiation protection community because the fact that NORM will be treated together with the 'heavy' concept of nuclear and radioactive waste was not acceptable due to a historical division of those two fields of radioactivity. As NORM is still regarded as a slightly technologically blended radioactivity which is of no concern to be a risk for the population and RADWASTE is a 'murder' of any population in its vicinity, the need for terminology harmonization and scientifically correct public education was recognized. It is barely known that during the recent past some Croatian professionals did included the NORM sites into the state documents and reports to international regulatory bodies as pure RADWASTE sites. This fact produces immense regulatory difficulties even today. The one and only legal way to solve both, regulatory issues providing real radiation protection procedures during existing NORM waste site sanation and exempting sites to be reused for a legal public purpose (industrial or any other) was to incorporate the existing Croatian NORM sites into the RADWASTE Strategy and to solve all legal radioactivity burden issues during the governmental acceptance process. This approach is a new one in Croatian regulatory acquits and first responses from the stake holders and public involved are promising. The experience from the field and first responses to a concept of harmonizing the reuse approach of existing NORM waste sites from stake holders and partly from general public will be discussed.(author).

Radwaste Decision Support System

International Nuclear Information System (INIS)

Westrom, G.; Vance, J.N.; Gelhaus, F.E.

1989-01-01

The purpose of the Radwaste Decision Support System (RDSS) is to provide expert advice, analysis results and instructional material relative to the treatment, handling, transport and disposal of low-level radioactive waste produced in nuclear power plants. This functional specification addresses the following topics: Functions of the RDSS, Relationships and interfaces between the function, Development of the decisions and logic tree structures embodied in waste management, Elements of the database and the characteristics required to support the decision-making process, Specific User requirements for the RDSS, Development of the user interface, Basic software architecture, and Concepts for the RDSS usage including updating and maintenance

System analysis for radwaste management

International Nuclear Information System (INIS)

Lennemann, W.L.

1987-01-01

The most logical approach to evaluating radioactive waste management processes and their options is to consider radioactive waste management, handling, and disposal as a complete and complex system from the waste arisings to their disposition. The principal elements that should be considered or taken into account when making a decision involving one or more components of a radwaste management system essentially concern radiation doses or detriments- both radiological and industrial safety and both capital investments and operating costs. This paper discusses the system analysis of the low- and medium-level radioactive waste management

Submergible barge retrievable storage and permanent disposal system for radioactive waste

Science.gov (United States)

Goldsberry, Fred L.; Cawley, William E.

1981-01-01

A submergible barge and process for submerging and storing radioactive waste material along a seabed. A submergible barge receives individual packages of radwaste within segregated cells. The cells are formed integrally within the barge, preferably surrounded by reinforced concrete. The cells are individually sealed by a concrete decking and by concrete hatch covers. Seawater may be vented into the cells for cooling, through an integral vent arrangement. The vent ducts may be attached to pumps when the barge is bouyant. The ducts are also arranged to promote passive ventilation of the cells when the barge is submerged. Packages of the radwaste are loaded into individual cells within the barge. The cells are then sealed and the barge is towed to the designated disposal-storage site. There, the individual cells are flooded and the barge will begin descent controlled by a powered submarine control device to the seabed storage site. The submerged barge will rest on the seabed permanently or until recovered by a submarine control device.

Storage facility for highly radioactive solid waste

International Nuclear Information System (INIS)

Kitano, Shozo

1996-01-01

A heat insulation plate is disposed at an intermediate portion between a ceiling wall of a storage chamber and an upper plate of a storage pit in parallel with them. A large number of highly radioactive solid wastes contained in canisters are contained in the storage pit. Cooling air is introduced from an air suction port, passes a channel on the upper side of the heat insulation plate formed by the ceiling of the storage chamber and the heat insulation plate, and flows from a flow channel on the side of the wall of the storage chamber to the lower portion of the storage pit. Afterheat is removed by the air flown from the lower portion to ventilation tubes at the outer side of container tubes. The air heated to a high temperature through the flow channel on the lower side of the heat insulation plate between the heat insulation plate and the upper plate of the storage pit, and is exhausted to an exhaustion port. Further, a portion of a heat insulation plate as a boundary between the cooling air and a high temperature air formed on the upper portion of the storage pit is formed as a heat transfer plate, so that the heat of the high temperature air is removed by the cooling air flowing the upper flow channel. This can prevent heating of the ceiling wall of the storage chamber. (I.N.)

Safety Analysis of Spent Nuclear Fuel and Radwaste Facilities

International Nuclear Information System (INIS)

Poskas, P.; Ragaisis, V.

2001-01-01

The overview of the activities in the Laboratory of Heat Transfer in Nuclear Reactors related with the assessment of thermal, neutronic and radiation characteristics in spent nuclear fuel and radwaste facilities are performed. Activities related with decommissioning of Ignalina NPP are also reviewed. (author)

Data acquisition and monitoring of radwaste cementation plants

International Nuclear Information System (INIS)

Cable, A.S.; Lee, D.J.; Samways, J.; Weller, F.C.; Williams, J.R.A.

1988-03-01

This paper summarises the progress made in the two years to June 1987 on the DOE funded programme for Data acquisition and monitoring of Radwaste Cementation Plants. The results of the computer based data logging and processing system fitted to an in-drum mixing station, cement powder plant and sludge handling plant are reported. (author)

Radwaste knowledge management in cooperation with the IAEA

International Nuclear Information System (INIS)

Batyukhnova, O.G.; Dmitriev, S.A.; Ozhovan, M.I.; Drejs, Z.; )

2010-01-01

The authors report on the emerging of the term knowledge management, and the practice of accumulation and preservation of nuclear knowledge. They emphasize that in addition to collecting and keeping scientific knowledge and identification of practical skills, management of nuclear knowledge includes setting the priorities to take into account the expected departure of retiring experts, and creating the mechanisms for attracting and training future employees. Education and training in radwaste management, as in the entire nuclear sector, is of a multi-disciplinary nature. It requires understanding of subjects such as geology, civil construction, mining, hydrogeology, chemistry, geophysics, mechanics, computing, etc. Moreover, this field is plagued with difficulty of reaching scientific, technical and even social consensus. Creation of effective and efficiently-operating systems for maintaining and disseminating knowledge is a complex and labour-consuming task. The role of the IAEA in the field of radwaste knowledge management is underlined. The SUE SIA Radon Moscow' experience and practice in training specialists of various professions and levels (including regulatory personnel) are described [ru

Clay minerals in sandstone uranium deposits: radwaste applications

International Nuclear Information System (INIS)

Brookins, D.G.

1990-01-01

Clay minerals play an important role in the genesis of uranium deposits in sandstones. They incorporate the rate earths (REE), U, Sb, Th, Cs, Rb, Sr, Y, Ba, and even small amounts of chalcophiles. These minerals possess analog elements for many of the radwaste fission products as well as actinides and some actinide daughters. In sandstone uranium deposits, clay minerals are also associated with sulfide minerals, usually pyrite, and organic carbonaceous matter. The primary clay minerals are usually smectites, illites, chlorites and mixed layer varieties. The integrity of these clay minerals is demonstrated by their retention of formational-mineralization ages determined by Rb-Sr geochronologic investigation of the Grants Mineral Belt of the United States. The importance of the clay minerals as analog for parts of the multi-barrier concept in radwaste disposal is their ability to impede water penetration into - and movement of key elements out of uranium rich zones. The clay minerals further sorb and in other ways incorporate into their structures many fission products and actinide analogs from man-made nuclear wastes. 22 refs., 1 fig., 3 tabs

Human engineering considerations in the design of New Virginia Power Radwaste facilities

International Nuclear Information System (INIS)

Bankley, A.V.; Morris, L.L.; Lippard, D.W.

1988-01-01

Human engineering principles were considered by Virginia Power in the recent design of new radwaste facilities (NRFs) for both the Surry and North Anna power stations. Virginia Power recognized that the rigorous application of human engineering principles to the NRF design was essential to the ultimate success or failure of the facilities. Success of the NRF should not only be measured in the volume of radwaste processed but also by other factors such as (a) availability and maintainability of preferred equipment, (b) as-low-as-reasonably-achievable considerations, (c) actual release rates versus achievable release rates, and (d) flexibility to deal with varying circumstances. Each of these success criteria would suffer as the result of operator/human inefficiencies or error. Therefore, human engineering should be applied to the maximum practical extent to minimize such inefficiencies or errors. No method is ever going to ensure a perfectly human-engineered facility design. Virginia Power believes, however, that significant strides have been made in efforts to design and construct a successful radwaste processing facility, a facility where operating success rests with the ability of the human operators to perform their jobs in an efficient and reliable fashion

Integrated technique for assessing environmental dose of radioactive waste storage installation

Energy Technology Data Exchange (ETDEWEB)

Bor-Jing Chang; Chien-Liang Shih; Ing-Jane Chen [Institute of Nuclear Energy Research, Lungtan, Taiwan (China); Ren-Dih Sheu; Shiang-Huei Jiang [National Tsing Hua University, Hsinchu, Taiwan (China); Shu-Jun Chang [Nuclear Science and Technology Association, Taiwan (China); Ruei-Ying Liao; Pei Yu; Chin-Yi Huang [Taiwan Power Company, Taipei, Taiwan (China)

2000-05-01

The ability to accurately predict exposure rates at large distances from a gamma radiation source is becoming increasingly important. This is because that the related regulation for the control of radiation levels in and around nuclear facilities becomes more stringent. Since the continuous increase of the radwaste storage capacity requirement on site, the requirement of a more realistic evaluation is very necessary. Those doses are usually at past time evaluated by QADCG/INER-2 code for direct dose and by SKYSHINE-III code for skyshine dose in which evaluation were over conservatively considered. This study is to update the evaluation code package accompanied with adequate methodology and to establish integrated analysis procedure. Thereafter, radiation doses can be accurately calculated in a reasonably conservative way. The purpose of the investigation is divided into three categories. First, SPECTRUM-506 is used instead of SPECTUM. Nuclide databases are enlarged from 100 up to 506. And the operation is ported to personal computer. Secondly, the QADCG/INER-3 code is developed to enhance the original QADCG/INER-2 code. The most important difference is the use of the geometric progression (GP) fitting function for the gamma-ray buildup factor. SKYSHINE-III code is replaced by McSKY and SKYDOSE codes. They are well benchmarked by using the Monte Carlo code MCNP and sensitive parameters are detailed investigated. Thirdly, the well developed analysis procedure is applicable for nuclear utility radwaste storage sites. Finally, the case studies were performed by using those packages to assess the radiological impact of utility radwaste storage site. The results are verified in detail by using Monte Carlo code MCNP and the results seems pretty consistent from both method. (author)

Storage process of large solid radioactive wastes

International Nuclear Information System (INIS)

Morin, Bruno; Thiery, Daniel.

1976-01-01

Process for the storage of large size solid radioactive waste, consisting of contaminated objects such as cartridge filters, metal swarf, tools, etc, whereby such waste is incorporated in a thermohardening resin at room temperature, after prior addition of at least one inert charge to the resin. Cross-linking of the resin is then brought about [fr

Final safety-analysis report for the Fifth Calcined Solids Storage Facility

International Nuclear Information System (INIS)

1982-01-01

Radioactive aqueous wastes generated by the solvent extraction of uranium from expended fuels at ICPP will be calcined in the New Waste Calcining Facility (NWCF). The calcined solids are pneumatically transferred to stainless steel bins enclosed in concrete vaults for interim storage of up to 500 years. The Fifth Calcined Solids Storage Facility (CSSF) provides 1000 m 3 of storage and consists of seven annular stainless steel bins inside a reinforced concrete vault set on bedrock. Storage of calcined solids is essentially a passive operation with very little opportunity for release of radionuclides and with no potential for criticality. There will be no potential for fire or explosion. Shielding has been designed to assure that the radiation levels at the vault exterior surfaces will be limited to less than 0.5 mRem/h. A sump in the vault floor will collect any in-leakage that may occur. Any water that collects in the sump will be sampled then removed with the sump jet. There will be an extremely small chance of release of radioactive particulates into the atmosphere as a result of a bin leak. The Design Basis Accident (DBA) postulates the spill of solids from an eroded fill line into the vault coupled with a failure of the vault cooling air radiation monitor. For the DBA, the maximum calculated radiation dose to an exposed individual near the site boundary is less than 1.2 μRem to the bone and lung

Calibration method for a radwaste assay system

International Nuclear Information System (INIS)

Dulama, C.; Dobrin, R.; Toma, Al.; Paunoiu, C.

2004-01-01

A waste assay system entirely designed and manufactured in the Institute for Nuclear Research is used in radwaste treatment and conditioning stream to ensure compliance with national repository radiological requirements. Usually, waste assay systems are calibrated by using various experimental arrangements including calibration phantoms. The paper presents a comparative study concerning the efficiency calibration performed by shell source method and a semiempirical, computational method based on a Monte Carlo algorithm. (authors)

UK national consensus conference on radwaste management

International Nuclear Information System (INIS)

Craven-Howe, Andrew

2000-01-01

UK CEED organised a consensus conference to debate radwaste disposal. It lasted from 21-24 May 1999. Among the witnesses called to give evidence were UKAEA, BNFL, Nuclear Industries' Inspectorate, Department of the Environment, Transport and the Regions, Friends of the Earth and Greenpeace. The end result was a report produced by the panel of members of the public, recording their views and recommendations. Conclusions are presented. (author)

The costs assessment of the RENEL's programme for radwaste management

International Nuclear Information System (INIS)

Barariu, Gh.; Andreescu, N.

1995-01-01

The paper presents first economical assessment of the Radwaste Management Programme of the Romanian Electricity Authority - Nuclear Power Group (RENEL-GEN) until closing all foreseeable activities in the field of nuclear waste processing and disposal. (Author) 1 Tab., 7 Refs

Safety aspects of the design of a PWR gaseous radwaste treatment system using hydrogen recombiners

International Nuclear Information System (INIS)

Glibert, R.; Nuyt, G.; Herin, S.; Fossion, P.

1978-01-01

PWR Gaseous radwaste treatment system is essential for the reduction of impact on environment of the nuclear power plants. Decay tank system has been used for the retention of the radioactive gaseous fission products generated in the primary coolant. The use of a system combining decay tanks and hydrogen recombiner units is described in this paper. Accent is put on the safety aspects of this gaseous radwaste treatment facilitystudied by BN for a Belgian Power Plant. (author)

Radwaste management in Sweden

International Nuclear Information System (INIS)

Ahlstroem, P.E.; Ungermark, S.

1987-01-01

The waste management system planned for handling the radioactive residues from Sweden's 12 nuclear power units is based on the operation of all the units up to the year 2010 in accordance with Parliament's decision to abolish nuclear power by that time. The main strategy for handling spent nuclear fuel is direct disposal without reprocessing. In the design of the radwaste management system the following fundamental principles have been applied. Short-lived waste will be disposed of as soon as possible after it has been generated. Spent fuel will be intermediately stored for about 40 years before final disposal, thereby reducing heat generation in the repository. Other long-lived waste will be disposed of jointly with the final disposal of spent fuel. 3 figs., 1 tab

Use of robotics in a Radwaste treatment plant

International Nuclear Information System (INIS)

Leeks, C.W.E.

1991-01-01

A 762 Unimate Puma, clean room standard Robot has been installed and commissioned in the Radwaste Treatment Plant at the Winfrith Technology Centre. The robot interacts with a variety of purpose designed tools and proprietary welding equipment. It performs 13 dedicated tasks in the final closure and health physics operations, before the 500 litre waste drum is despatched from the plant. (author)

Performance assessment for Nuclear Power Plant Krsko intermediate and low-level rad-waste repository

International Nuclear Information System (INIS)

Jelavic, V.; Skanata, D.; Plecjas, I.

1990-01-01

Performance safety Assessment for NPP Krsko radwaste repository was performed (LLW/ILW). Shallow land and tunnel type concept were analyzed. Because it was based on two unknown referent sites, one for the shallow land concept and the other for the tunnel type, analysis was generic in nature. Scenario selecting process and consequence analysis were performed by using deterministic approach. Results for both concepts of disposal suggests that proposed NPP Krsko radwaste repository reference site and disposal technology will fully meet radiation limits imposed by the Yugoslav regulations and ICRP guidelines. (author)

Review of Solid State Hydrogen Storage Methods Adopting Different Kinds of Novel Materials

Directory of Open Access Journals (Sweden)

Renju Zacharia

2015-01-01

Full Text Available Overview of advances in the technology of solid state hydrogen storage methods applying different kinds of novel materials is provided. Metallic and intermetallic hydrides, complex chemical hydride, nanostructured carbon materials, metal-doped carbon nanotubes, metal-organic frameworks (MOFs, metal-doped metal organic frameworks, covalent organic frameworks (COFs, and clathrates solid state hydrogen storage techniques are discussed. The studies on their hydrogen storage properties are in progress towards positive direction. Nevertheless, it is believed that these novel materials will offer far-reaching solutions to the onboard hydrogen storage problems in near future. The review begins with the deficiencies of current energy economy and discusses the various aspects of implementation of hydrogen energy based economy.

Multiplexed image storage by electromagnetically induced transparency in a solid

Science.gov (United States)

Heinze, G.; Rentzsch, N.; Halfmann, T.

2012-11-01

We report on frequency- and angle-multiplexed image storage by electromagnetically induced transparency (EIT) in a Pr3+:Y2SiO5 crystal. Frequency multiplexing by EIT relies on simultaneous storage of light pulses in atomic coherences, driven in different frequency ensembles of the inhomogeneously broadened solid medium. Angular multiplexing by EIT relies on phase matching of the driving laser beams, which permits simultaneous storage of light pulses propagating under different angles into the crystal. We apply the multiplexing techniques to increase the storage capacity of the EIT-driven optical memory, in particular to implement multiplexed storage of larger two-dimensional amounts of data (images). We demonstrate selective storage and readout of images by frequency-multiplexed EIT and angular-multiplexed EIT, as well as the potential to combine both multiplexing approaches towards further enhanced storage capacities.

Design and operation of the Surry Radwaste Facility

International Nuclear Information System (INIS)

Morris, L.L.; Halverson, W.C.

1993-01-01

In September 1991, Virginia Power started processing radioactive waste with a new Radwaste Facility at the Surry Power Station near Norfolk, Virginia. The Surry Radwaste Facility (SRF) was designed to process and store liquid waste, laundry waste, dry active waste, radioactive filters and spent ion-exchange resin. It also provides on-site decontamination services and a fully equipped hot machine shop. The NRC has recognized that the amount of planning and design, and the attention to detail, that was expended on the SRF Project in order to minimize personnel exposure and ensure efficient operation, is a licensee strength. Through its first year of operation, the facility has proven very successful. Using evaporation and demineralization, over 30 million liters of liquid have been released with no chemical impurities or detectable radioactivity (excluding tritium). Over 623,000 liters of concentrated boric acid waste liquid have been processed with the Bitumen Solidification System yielding 139,880 liters (660 drums) of low level Class A-Stable waste. Additional economic benefits will be realized as the effectiveness of the processing systems continues to improve due to increased operational experience and ergonomics

Design Considerations of a Solid State Thermal Energy Storage

Science.gov (United States)

Janbozorgi, Mohammad; Houssainy, Sammy; Thacker, Ariana; Ip, Peggy; Ismail, Walid; Kavehpour, Pirouz

2016-11-01

With the growing governmental restrictions on carbon emission, renewable energies are becoming more prevalent. A reliable use of a renewable source however requires a built-in storage to overcome the inherent intermittent nature of the available energy. Thermal design of a solid state energy storage has been investigated for optimal performance. The impact of flow regime, laminar vs. turbulent, on the design and sizing of the system is also studied. The implications of low thermal conductivity of the storage material are discussed and a design that maximizes the round trip efficiency is presented. This study was supported by Award No. EPC-14-027 Granted by California Energy Commission (CEC).

Overview of BELGATOM's industrial experience in the field of radwaste bituminization, cementation and radwaste package storage

International Nuclear Information System (INIS)

Glibert, R.; Debieve, P.; Averbeke, J. van; Centner, B.

1993-01-01

Radioactive waste processing experience in Belgium is introduced. BELGATOM partners in Belgium have accumulated experience for over 25 years in the field of rad waste treatment and conditioning by bituminization and cementation and in the storage of the resulting rad waste packages

Light storage in a doped solid enhanced by feedback-controlled pulse shaping

International Nuclear Information System (INIS)

Beil, F.; Buschbeck, M.; Heinze, G.; Halfmann, T.

2010-01-01

We report on experiments dealing with feedback-controlled pulse shaping to optimize the efficiency of light storage by electromagnetically induced transparency (EIT) in a Pr 3+ :Y 2 SiO 5 crystal. A learning loop in combination with an evolutionary algorithm permits the automatic determination of optimal temporal profiles of intensities and frequencies in the driving laser pulses (i.e., the probe and coupling pulses). As a main advantage, the technique finds optimal solutions even in the complicated multilevel excitation scheme of a doped solid, involving large inhomogeneous broadening. The learning loop experimentally determines optimal temporal intensity profiles of the coupling pulses for a given probe pulse. The optimized intensity pulse shapes enhance the light-storage efficiency in the doped solid by a factor of 2. The learning loop also determines a fast and efficient preparation pulse sequence, which serves to optically prepare the crystal prior to light-storage experiments. The optimized preparation sequence is 5 times faster than standard preparation sequences. Moreover, the optimized preparation sequence enhances the optical depth in the medium by a factor of 5. As a consequence, the efficiency of light storage also increases by another factor of 3. Our experimental data clearly demonstrate the considerable potential of feedback-controlled pulse shaping, applied to EIT-driven light storage in solid media.

Method of encapsulating solid radioactive waste material for storage

International Nuclear Information System (INIS)

Bunnell, L.R.; Bates, J.L.

1976-01-01

High-level radioactive wastes are encapsulated in vitreous carbon for long-term storage by mixing the wastes as finely divided solids with a suitable resin, formed into an appropriate shape and cured. The cured resin is carbonized by heating under a vacuum to form vitreous carbon. The vitreous carbon shapes may be further protected for storage by encasement in a canister containing a low melting temperature matrix material such as aluminum to increase impact resistance and improve heat dissipation. 8 claims

Predictive model to describe water migration in cellular solid foods during storage

NARCIS (Netherlands)

Voogt, J.A.; Hirte, A.; Meinders, M.B.J.

2011-01-01

BACKGROUND: Water migration in cellular solid foods during storage causes loss of crispness. To improve crispness retention, physical understanding of this process is needed. Mathematical models are suitable tools to gain this physical knowledge. RESULTS: Water migration in cellular solid foods

Predictive model to describe water migration in cellular solid foods during storage

NARCIS (Netherlands)

Voogt, J.A.; Hirte, A.; Meinders, M.B.J.

2011-01-01

Background: Water migration in cellular solid foods during storage causes loss of crispness. To improve crispness retention, physical understanding of this process is needed. Mathematical models are suitable tools to gain this physical knowledge. Results: Water migration in cellular solid foods

Chapter No.6. Radioactive waste (RAW)

International Nuclear Information System (INIS)

2002-01-01

UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO 2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

Review of decommissioning, spent fuel and radwaste management in Slovakia

International Nuclear Information System (INIS)

Jamrich, J.

2000-01-01

Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Bryant, J.W.; Nenni, J.A.

2003-01-01

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Jeffrey Bryant

2008-01-01

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

Characteristics of soils and saprolite in Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Ammons, J.T.; Phillips, D.H.; Timpson, M.E.

1987-01-01

Solid Waste Storage Area 6 (SWSA-6) is one of the disposal sites for solid low-level radioactive waste at Oak Ridge National Laboratory. Soils and saprolites from the site were characterized to provide base line information to initiate assessment for remedial actions and closure plans. Physical, chemical, mineralogical, and engineering analyses were conducted on soil and saprolite samples

Basic user guide for the radwaste treatment plant computer system

International Nuclear Information System (INIS)

Keel, A.

1990-07-01

This guide has been produced as an aid to using the Radwaste Treatment Plant computer system. It is designed to help new users to use the database menu system. Some of the forms can be used in ways different from those explained and more complex queries can be performed. (UK)

Development of regulatory and legal framework for spent fuel and radwaste management

International Nuclear Information System (INIS)

Bezzubtsev, V.S.

2012-01-01

The Basics of National Policy in Nuclear and Radiation Safety assurance in the Russian Federation define the principles and objectives of nuclear and radiation safety of nuclear facilities during all stages of their life cycle. Russia's National Report at the Fourth Review Meeting of Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management reflected the organizational as well as legal and regulatory changes that have taken place over past three years. Amendments recently made to the Russian Nuclear Energy Law as well as the Law on Radwaste Management adopted in 2011 are discussed. Federal norms and regulations in the field of spent fuel and radwaste management are also presented. Organizational and legal reforms related to state safety regulation are described [ru

Hydrogen storage in TiCr1.2(FeV)x BCC solid solutions

International Nuclear Information System (INIS)

Santos, Sydney F.; Huot, Jacques

2009-01-01

The Ti-V-based BCC solid solutions have been considered attractive candidates for hydrogen storage due to their relatively large hydrogen absorbing capacities near room temperature. In spite of this, improvements of some issues should be achieved to allow the technological applications of these alloys. Higher reversible hydrogen storage capacity, decreasing the hysteresis of PCI curves, and decrease in the cost of the raw materials are needed. In the case of vanadium-rich BCC solid solutions, which usually have large hydrogen storage capacities, the search for raw materials with lower cost is mandatory since pure vanadium is quite expensive. Recently, the substitutions of vanadium in these alloys have been tried and some interesting results were achieved by replacing vanadium by commercial ferrovanadium (FeV) alloy. In the present work, this approach was also adopted and TiCr 1.2 (FeV) x alloy series was investigated. The XRD patterns showed the co-existence of a BCC solid solution and a C14 Laves phase in these alloys. SEM analysis showed the alloys consisted of dendritic microstructure and C14 colonies. The amount of C14 phase increases when the amount of (FeV) decreases in these alloys. Concerning the hydrogen storage, the best results were obtained for the TiCr 1.2 (FeV) 0.4 alloy, which achieved 2.79 mass% of hydrogen storage capacity and 1.36 mass% of reversible hydrogen storage capacity

Development of the Computer Code to Determine an Individual Radionuclides in the Rad-wastes Container for Ulchin Units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Kang, D.W.; Chi, J.H.; Goh, E.O. [Korea Electric Power Research Institute, Taejon (Korea)

2001-07-01

A computer program, RASSAY was developed to evaluate accurately the activities of various nuclides in the rad-waste container for Ulchin units 3 and 4. This is the final report of the project, {sup D}evelopment of the Computer Code to Determine an Individual Radionuclides in the Rad-wastes Container for Ulchin Units 3 and 4 and includes the followings; 1) Structure of the computer code, RASSAY 2) An example of surface dose calculation by computer simulation using MCNP code 3) Methods of sampling and activity measurement of various Rad-wastes. (author). 21 refs., 35 figs., 6 tabs.

The Primary Solid Waste Storage Gaps Experienced By Nairobi ...

African Journals Online (AJOL)

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Key Words: Household Storage, Solid Waste Management; Garbage Bins. Introduction .... depends on people's identification with the SWM system. The character of SWM ..... end up in the right place, and health and safety of those handling the full ... Afullo A (2004) Environmental and occupational health aspects of waste ...

Practical experience for liquid radioactive waste treatment from spent fuel storage pool on RA reactor in Vinca Institute

International Nuclear Information System (INIS)

Plecas, I.; Pavlovic, R.; Pavlovic, S.

2002-01-01

The present paper reports the results of the preliminary removal of sludge from the bottom of the spent fuel storage pool in the RA reactor, mechanical filtration of the pool water and sludge conditioning and storage. Yugoslavia is a country without a nuclear power plant (NPP) on its territory. The law which strictly forbids NPP construction is still valid, but, nevertheless we must handle and dispose radioactive waste. This is not only because of radwaste originating from the use of radioactive materials in medicine and industry, but also because of the waste generated by research in the Nuclear Sciences Institute Vinca. In the last forty years, in the Vinca Institute, as a result of two research reactors being operational, named RA and RB, and as a result of the application of radionuclides in medicine, industry and agriculture, radioactive waste materials of different levels of specific activity were generated. As a temporary solution, radioactive waste materials are stored in two interim storages. Radwaste materials that were immobilized in the inactive matrices are to be placed in concrete containers, for further manipulation and disposal.(author)

40 CFR 266.205 - Standards applicable to the storage of solid waste military munitions.

Science.gov (United States)

2010-07-01

... solid waste military munitions. 266.205 Section 266.205 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR THE MANAGEMENT OF SPECIFIC HAZARDOUS... applicable to the storage of solid waste military munitions. (a) Criteria for hazardous waste regulation of...

A master plan for the radwaste management

International Nuclear Information System (INIS)

Kim, Y.E.; Lee, S.H.; Lee, C.K.; Moon, S.H.; Sung, R.J.; Sung, K.W.

1983-01-01

The accumulated total amount of low-level radioactive wastes to be produced from operating power reactors and nuclear installations up until the year 2007 is estimated to 900,000 drum(approximately 200,000M 3 ). An effective master plan for the safe disposal of the wastes is necessary. Among many different disposal methods available for low-and medium-level radwastes, the engineered trench approach was chosen by an extensive feasibility study as the optimum method for Korea. Site selection, construction and commissioning of such a disposal facility are presumed to take two and a half years, beginning in July 1983. The total cost in opening the site and the unit disposal cost per drum were estimated to be 11 billion won and 40,000 won, respectively. An agency(KORDA) managing the operation of the disposal site is recommended to be established by 1987, assuming that the agency's economic feasibility can be justified by that time. When the disposal site is commissioned, a regulatory guide for ground disposal will be available, and supporting R and D work on the disposal site will be complete. Studies on the technology of radwaste treatment will continue through this period. For the longer term, staff training and future planning have been undertaken to ensure that a master plan, which can be expected to be used as a guideline for disposal of all radioactive waste arising, is fully adequate. (Author)

Characterization during storage and dissolution of Solid dispersions containing furosemide and hydroxypropyl methylcellulose

DEFF Research Database (Denmark)

Nielsen, Line Hagner; Rades, T.; Müllertz, A.

2013-01-01

Solid dispersions containing furosemide and various amounts of hydroxypropyl methylcellulose (HPMC) were prepared by spray drying to investigate if the physical stability of amorphous furosemide during storage and dissolution could be improved by formulating the drug as a solid dispersion. All...

Radwaste inventories and projections: an overview

International Nuclear Information System (INIS)

Notz, K.J.

1982-07-01

The Integrated Data Base program was set up to provide fully integrated and reconciled inventories, characteristics, and projections for spent nuclear fuel and all categories of radioactive waste. Eight summary papers, six of which were presented at an ANS special session in Los Angeles in June 1982, are included in this report: data base needs and functions: national planning; integrated data base for spent fuel and radwaste: inventories; integrated data base projections; RAWSYM: radioactive waste management system; NWTS program waste projection data needs; low-level waste management data base system; waste sludge composition at the Savannah River Plant; and summary of characteristics of transuranic waste found at DOE sites

Storage facility for solid medium level waste at Eurochemic

International Nuclear Information System (INIS)

Balseyro-Castro, M.

1976-01-01

An engineered surface storage facility is described; it will serve for the interim storage of solid and solidified medium-level waste resulting from the reprocessing of irradiated fuels. Up till now, two storage bunkers have been constructed. Each of them is 64 m long, 12 m wide and 8 m high and can take up to about 5,000 drums of 220 1 volume. The drums are stored in a vertical position and in four layers. The waste product drums are transported by a wagon to the entrance of the bunkers from where they are transferred in to the bunker by an overhead crane which is remotely controlled by high-frequency modulated laser beams. A closed-circuit camera is used to watch the handling operations. The waste stored is fully retrievable, either by means of an overhead crane of a lift-truck and can then be transported to an ultimate storage site

Research and development related to the Nevada Nuclear Waste Storage Investigations. Progress report, January 1-March 31, 1981

International Nuclear Information System (INIS)

Erdal, B.R.; Daniels, W.R.; Wolfsberg, K.

1981-07-01

Storage of radwaste in tuff was studied. Adsorption experiments were conducted with 85 Sr, 95 Tc, 137 Cs, 133 Ba, and 152 Eu. The geochemistry and mineralogy-petrology of tuff were studied. Organic and inorganic Eh buffers were investigated. Rock physics studies were also conducted

The chemical behaviour of iodine-129 in the process of radwaste conditioning

International Nuclear Information System (INIS)

Schon, T.

1993-11-01

During radwaste reprocessing, elemental I-129 may almost completely be transferred to the dissolver off-gas stream. The AC 6120 adsorbent, consisting of high-heated, amorphous silicic acid impregnated with silver nitrate, proved to be particularly efficient for removing the iodine from the off-gas. In a gas-solid reaction, the elemental iodine is converted into solid silver iodide and silver iodate. The reaction's stoichiometry depends on the loading temperature, with temperatures between 30 and 80 C resulting in a ratio of five between the reaction products of AgI and AgIO 3 , while with temperatures higher than that, up to 150 C, the ratio is three. For assessing the acceptability of the iodine-bearing AC 6120 as a waste product to be emplaced in a salt rock repository, the ratio of the reaction products is one of the main criteria. The products solubility and its complexation reactions with chloride-bearing brines are two other important criteria, especially with a view to the not completely hypothetical accident type of 'water ingress into the salt cavern'. Leaching experiments have shown that in this event, between 30 and over 60% of the waste product's iodine inventory would be leached out within only seven days. Thus AC 6120 is not a candidate adsorbent for immobilization of iodine 129 in a waste product. (orig./HP) [de

SWSA [Solid Waste Storage Area] 6 tumulus disposal demonstration

International Nuclear Information System (INIS)

Van Hoesen, S.D.; Clapp, R.B.

1987-01-01

A facility to demonstrate the above-grade disposal of solid low-level radioactive wastes (LLW) is being constructed in the Solid Waste Storage Area 6 (SWSA 6) at the Oak Ridge National Laboratory (ORNL). The demonstration facility will utilize the ''Tumulus'' technology, which basically involves sealing the waste in concrete vaults, placing the vaults on a grade level concrete pad, and covering the pad with a soil cover after vault placement is complete. Loading of the demonstration unit is scheduled to begin in June, and will continue one to one and a half years until the 28,000 ft 3 capacity is exhausted

Evaluation of existing Hanford buildings for the storage of solid wastes

International Nuclear Information System (INIS)

Carlson, M.C.; Hodgson, R.D.; Sabin, J.C.

1993-05-01

Existing storage space at the Hanford Site for solid low-level mixed waste (LLMW) will be filled up by 1997. Westinghouse Hanford Company (WHC) has initiated the project funding cycle for additional storage space to assure that new facilities are available when needed. In the course of considering the funding request, the US Department of Energy (DOE) has asked WHC to identify and review any existing Hanford Site facilities that could be modified and used as an alternative to constructing the proposed W-112 Project. This report documents the results of that review. In summary, no buildings exist at the Hanford Site that can be utilized for storage of solid LLMW on a cost-effective basis when compared to new construction. The nearest approach to an economically sensible conversion would involve upgrade of 100,000 ft 2 of space in the 2101-M Building in the 200 East Area. Here, modified storage space is estimated to cost about $106 per ft 2 while new construction will cost about $50 per ft 2 . Construction costs for the waste storage portion of the W-112 Project are comparable with W-016 Project actual costs, with escalation considered. Details of the cost evaluation for this building and for other selected candidate facilities are presented in this report. All comparisons presented address the potential decontamination and decommissioning (D ampersand D) cost avoidances realized by using existing facilities

Estimating Residual Solids Volume In Underground Storage Tanks

International Nuclear Information System (INIS)

Clark, Jason L.; Worthy, S. Jason; Martin, Bruce A.; Tihey, John R.

2014-01-01

The Savannah River Site liquid waste system consists of multiple facilities to safely receive and store legacy radioactive waste, treat, and permanently dispose waste. The large underground storage tanks and associated equipment, known as the 'tank farms', include a complex interconnected transfer system which includes underground transfer pipelines and ancillary equipment to direct the flow of waste. The waste in the tanks is present in three forms: supernatant, sludge, and salt. The supernatant is a multi-component aqueous mixture, while sludge is a gel-like substance which consists of insoluble solids and entrapped supernatant. The waste from these tanks is retrieved and treated as sludge or salt. The high level (radioactive) fraction of the waste is vitrified into a glass waste form, while the low-level waste is immobilized in a cementitious grout waste form called saltstone. Once the waste is retrieved and processed, the tanks are closed via removing the bulk of the waste, chemical cleaning, heel removal, stabilizing remaining residuals with tailored grout formulations and severing/sealing external penetrations. The comprehensive liquid waste disposition system, currently managed by Savannah River Remediation, consists of 1) safe storage and retrieval of the waste as it is prepared for permanent disposition; (2) definition of the waste processing techniques utilized to separate the high-level waste fraction/low-level waste fraction; (3) disposition of LLW in saltstone; (4) disposition of the HLW in glass; and (5) closure state of the facilities, including tanks. This paper focuses on determining the effectiveness of waste removal campaigns through monitoring the volume of residual solids in the waste tanks. Volume estimates of the residual solids are performed by creating a map of the residual solids on the waste tank bottom using video and still digital images. The map is then used to calculate the volume of solids remaining in the waste tank. The ability to

How utilities respond to radwaste needs

International Nuclear Information System (INIS)

Strauss, S.D.

1987-01-01

Slow progress is being made toward regionalization of waste disposal, some states working toward regional compacts while others choose to go it alone. More promising is the reduction of radwaste volumes discharged from nuclear stations. More and more utilities are contracting with private companies for LLW processing. While such services are provided predominantly by mobile units at plant sites, one fixed installation already offers processing of dry waste and two others await final regulatory approval. Both developments are detailed. This article also includes an analysis of the design, performances comparison between slagging combustors (SC) and the FBC boiler. Comparisons are also made for SC technology to FBC for 250-MW unit and of utility-unit conversion costs

Radwaste reduction through use of condensate non-precoat filters at Perry Nuclear Power Plant

International Nuclear Information System (INIS)

Hartman, J.L.

1996-01-01

The concept of non-precoat filtration to remove iron oxide without generating traditional resin and fiber precoat material, which is expensive to dispose of as radwaste, is rapidly becoming a trend of the 90's. In 1991, in response to escalating radwaste disposal costs, Perry Nuclear Power Plant was the first BWR to install non-precoat filters (septa) on a full scale basis in a Condensate System. To date, non-precoat septa from three vendors; including Memtec Power Generation have been installed and operated at Perry. It is important that other utilities considering this technology be given as much open-quotes real lifeclose quotes operational data as possible. This paper presents the data from three different companies and provides recommendations for consideration

Safety assessment for radwaste disposal in Korea: Pt. 1

International Nuclear Information System (INIS)

Suh, I.S.; Park, H.H.; Han, K.W.; Hahn, P.S.

1986-01-01

A simplified safety analysis code has been established in order to provide a basic methodology for the preliminary selection of a disposal method. The disposal type selection is prerequisite to meet the requirements of low and intermediate level radwaste management program in Korea. The code covers resaturation and leaching, migration through fracture-porous media transport such that the rock cavern disposal option can be evaluated compared with that of shallow land burial

Survey and evaluation of handling and disposing of solid low-level nuclear fuel cycle wastes

International Nuclear Information System (INIS)

Mullarkey, T.B.; Jentz, T.L.; Connelly, J.M.; Kane, J.P.

1976-10-01

The report identifies the types and quantities of low-level solid radwaste for each portion of the nuclear fuel cycle, based on operating experiences at existing sites and design information for future installations. These facts are used to evaluate reference 1000 MWe reactor plants in terms of solid radwaste generation. The effect of waste volumes on disposal methods and land usage has also been determined, based on projections of nuclear power growth through the year 2000. The relative advantages of volume reduction alternatives are included. Major conclusions are drawn concerning available land burial space, light water reactors and fuel fabrication and reprocessing facilities. Study was conducted under the direction of an industry task force and the National Environmental Studies Project, a technical program of the Atomic Industrial Forum. Data was obtained from questionnaires sent to 8 fuel fabrication facilities, 39 reactor sites and 6 commercial waste disposal sites. Additional data were gathered from interviews with architect engineering firms, site visits, contacts with regulatory agencies and published literature

Solid State NMR Characterization of Complex Metal Hydrides systems for Hydrogen Storage Applications

Directory of Open Access Journals (Sweden)

Son-Jong Hwang

2011-12-01

Full Text Available Solid state NMR is widely applied in studies of solid state chemistries for hydrogen storage reactions. Use of 11B MAS NMR in studies of metal borohydrides (BH4 is mainly focused, revisiting the issue of dodecaborane formation and observation of 11B{1H} Nuclear Overhauser Effect.

High temperature solid oxide regenerative fuel cell for solar photovoltaic energy storage

Science.gov (United States)

Bents, David J.

A hydrogen-oxygen regenerative fuel cell energy storage system based on high temperature solid oxide fuel cell technology is discussed which has application to darkside energy storage for solar photovoltaics. The forward and reverse operating cycles are described, and heat flow, mass, and energy balance data are presented to characterize the system's performance and the variation of performance with changing reactant storage pressure. The present system weighs less than nickel hydrogen battery systems after 0.7 darkside operation, and it maintains a specific weight advantage over radioisotope generators for discharge periods up to 72 hours.

High temperature solid oxide regenerative fuel cell for solar photovoltaic energy storage

Science.gov (United States)

Bents, David J.

1987-01-01

A hydrogen-oxygen regenerative fuel cell energy storage system based on high temperature solid oxide fuel cell technology is discussed which has application to darkside energy storage for solar photovoltaics. The forward and reverse operating cycles are described, and heat flow, mass, and energy balance data are presented to characterize the system's performance and the variation of performance with changing reactant storage pressure. The present system weighs less than nickel hydrogen battery systems after 0.7 darkside operation, and it maintains a specific weight advantage over radioisotope generators for discharge periods up to 72 hours.

Cross flow filtration for radwaste applications reverse osmosis demonstration case studies

International Nuclear Information System (INIS)

Malkmus, D.

1995-01-01

Today's radwaste economic and regulatory scenarios signify the importance in the improvement of operational practices to reduce generator liabilities. This action is largely due to the rising cost dealing with burial sites and the imposed waste volume restriction. To control the economical burdens associated with waste burial and to comply with stricter environmental regulations, NPP's are attempting to modify their radwaste system(s) design and operating philosophy by placing a major emphasis on waste volume reduction and processing techniques. The utilization of reverse osmosis technology as a means for treatment of process and wastewater streams in the nuclear power industry has been investigated for many years. This paper will outline reverse osmosis theory and highlight performance data for process and waste stream purification applications. Case studies performed at 5 nuclear plants have been outlined. The demonstrations were performed on a widely variety of process stream for both a PWR and BWR application. The data provided by the pilot systems, the equipment design, and the economical impact a reverse osmosis unit will have on producing treated (high purity) are as follows

Alternative concepts for spent fuel storage basin expansion at Morris Operation

International Nuclear Information System (INIS)

Graf, W.A. Jr.; King, C.E.; Miller, G.P.; Shadel, F.H.; Sloat, R.J.

1980-08-01

Alternative concepts for increasing basin capabilities for storage of spent fuel at the Morris Operation have been defined in a series of simplified flow diagrams and equipment schematics. Preliminary concepts have been outlined for (1) construction alternatives for an add-on basin, (2) high-density baskets for storage of fuel bundles or possible consolidated fuel rods in the existing or add-on basins, (3) modifications to the existing facility for increasing cask handling and fuel receiving capabilities and (4) accumulation, treatment and disposal of radwastes from storage operations. Preliminary capital and operating costs have been prepared and resource and schedule requirements for implementing the concepts have been estimated. The basin expansion alternatives would readily complement potential dry storage projects at the site in an integrated multi-stage program that could provide a total storage capacity of up to 7000 tonnes of spent fuel

Sampling of charged liquid radwaste stored in large tanks

International Nuclear Information System (INIS)

Tchemitcheff, E.; Domage, M.; Bernard-Bruls, X.

1995-01-01

The final safe disposal of radwaste, in France and elsewhere, entails, for liquid effluents, their conversion to a stable solid form, hence implying their conditioning. The production of conditioned waste with the requisite quality, traceability of the characteristics of the packages produced, and safe operation of the conditioning processes, implies at least the accurate knowledge of the chemical and radiochemical properties of the effluents concerned. The problem in sampling the normally charged effluents is aggravated for effluents that have been stored for several years in very large tanks, without stirring and retrieval systems. In 1992, SGN was asked by Cogema to study the retrieval and conditioning of LL/ML chemical sludge and spent ion-exchange resins produced in the operation of the UP2 400 plant at La Hague, and stored temporarily in rectangular silos and tanks. The sampling aspect was crucial for validating the inventories, identifying the problems liable to arise in the aging of the effluents, dimensioning the retrieval systems and checking the transferability and compatibility with the downstream conditioning process. Two innovative self-contained systems were developed and built for sampling operations, positioned above the tanks concerned. Both systems have been operated in active conditions and have proved totally satisfactory for taking representative samples. Today SGN can propose industrially proven overall solutions, adaptable to the various constraints of many spent fuel cycle operators

The remote methods for radwaste and SNF control

International Nuclear Information System (INIS)

Ivanov, O; Stepanov, V; Danilovich, A; Potapov, V

2017-01-01

With the examples of developments carried out in the Kurchatov Institute and by the world leaders in the field the presentation considers the devices and methods to obtain remotely information on the distribution of radioactivity in radwaste and SNF. It describes the different types of light portable gamma cameras. The application of scanning spectrometric systems is considers also. The methods of recording UV radiation for detection of alpha contamination with the luminescence of air are presented. We discuss the scope and tasks that can be solved using remote and non-destructive methods. (paper)

Experience in ultimate storage of radwaste, illustrated by the information on geomechanics gained in the Asse storage facility

International Nuclear Information System (INIS)

Schmidt, M.W.

1981-01-01

Among the numerous variants of storing radioactive waste in the deep geological underground the storage in appropriate mineral salt formations has a couple of particular advantages. In order to effect research- and development works with regard to a safe secular storage of radioactive wastes, the former mineral salt deposit ASSE was assigned to the GSF in the year 1965. At this test plant storage technologies are developed, tested and the operational efficiency of according technical facilities is demonstrated. As a part of these duties several technical and natural scientific fields like nuclear engineering, mining, geomechanics, geochemistry or hydrogeology are worked in interdisciplinarily. Departing from the existing mine building of the shaft ASSE storage bunkers for low- and intermediate-level radioactive wastes (LAW/MAW) are presented. Accompanying geotechnical investigations are explained. An outlook alludes to an eventually possible development potential of the storage bunker arrangement from the geomechanic view. (orig./HP) [de

Preliminary criteria for shallow-land storage/disposal of low-level radioactive solid waste in an arid environment

International Nuclear Information System (INIS)

Shord, A.L.

1979-09-01

Preliminary criteria for shallow land storage/disposal of low level radioactive solid waste in an arid environment were developed. Criteria which address the establishment and operation of a storage/disposal facility for low-level radioactive solid wastes are discussed. These were developed from the following sources: (1) a literature review of solid waste burial; (2) a review of the regulations, standards, and codes pertinent to the burial of radioactive wastes; (3) on site experience; and (4) evaluation of existing burial grounds and practices

Radioactive solid waste inventories at United States Department of Energy burial and storage sites

International Nuclear Information System (INIS)

Watanabe, T.

1987-06-01

Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1986. 4 figs., 7 tabs

The design, construction, and operation of the Integrated Radwaste Treatment System (IRTS) Drum Cell

International Nuclear Information System (INIS)

Landau, B.; Russillo, A.; Frank, D.; Garland, D.

1989-12-01

This report describes the design, construction, and the operation of the Integrated Radwaste Treatment Systems (IRTS) Drum Cell at the West Valley Demonstration Project (WVDP), West Valley, New York. The IRTS Drum Cell was designed to provide a shielded, secure storage area for the remote handling and placement of low-level Class C radioactive waste produced in the IRTS. The Drum Cell was designed to contain up to approximately 8,804 drums from decontaminated supernatant processing. This waste is to be poured into 0.27m 3 in a temperature controlled environment to ensure the cement will not be subjected to freezing and thawing cycles. A Temporary Weather Structure (TWS), a pre-engineered building, now encloses the Drum Cell and associated equipment so that remote waste-handling and placement operations can continue without regard to weather conditions. The Drum Cell was designed so that this TWS could be removed and the low-level waste entombed in place. Final disposition of this low-level waste is currently being evaluated in an Environmental Impact Statement (EIS). 10 refs., 11 figs., 1 tab

Long-term storage of radioactive solid waste within disposal facilities

International Nuclear Information System (INIS)

Wakerley, M.W.; Edmunds, J.

1986-05-01

A study of the feasibility and implications of operating potential disposal facilities for low and intermediate level solid radioactive waste in a retrievable storage mode for extended periods of up to 200 years has been carried out. The arisings of conditioned UK radioactive waste up to the year 2030 have been examined. Assignments of these wastes to different types of underground disposal facilities have been made on the basis of their present activity and that which they will have in 200 years time. Five illustrative disposal concepts proposed both in the UK and overseas have been examined with a view to their suitability for adaption for storage/disposal duty. Two concepts have been judged unsuitable because either the waste form or the repository structure were considered unlikely to last the storage phase. Three of the concepts would be feasible from a construction and operational viewpoint. This suggests that with appropriate allowance for geological aspects and good repository and waste form design that storage/disposal within the same facility is achievable. The overall cost of the storage/disposal concepts is in general less than that for separate surface storage followed by land disposal, but more than that for direct disposal. (author)

Design, construction and commissioning of the new solid waste management and storage facilities of Ignalina NPP, Lithuania

Energy Technology Data Exchange (ETDEWEB)

Goehring, R.; Wenninger, K. [RWE NUKEM GmbH, Alzenau (Germany)

2006-04-15

The contract for the design, construction and commissioning (turn-key) of the New Solid Waste Management and Storage Facilities (SWMSF) has been awarded to RWE NUKEM GmbH. The contract was signed on the 30.11.2005. The New Solid Waste Management and Storage Facilities (SWMSF) are financed by the Ignalina Decommissioning Support Fund which is managed by European Bank for Reconstruction and Development (EBRD). The new facilities are required on the Ignalina Nuclear Power Plant (INPP) in order to support ongoing decomissioning work, including removal of waste from existing waste storage buildings. (orig.)

Repacking of Cobalt 60 spent sources in the central interim storage

International Nuclear Information System (INIS)

Zeleznik, N.

2003-01-01

After the transfer of the responsibility for the management of the Central interim storage for waste from small producers, located at the reactor centre in Brinje near Ljubljana, Slovenia, the national Agency for radwaste management (ARAO) started with most urgent activities to improve the utilization of the storage facility. One of the main tasks has also been the rearrangement of the already stored radioactive waste in order to reduce volume of the waste and to collect same radioisotopes in the containers. The latest campaign, performed in 2002/2003, was repacking of all Co-60 spent sealed sources in the storage facility and also at the producer's premises which were after conditioning put into two drums with concrete matrix and stored back to the Central interim storage. The preparation works together with the implementation are described in the paper. (author)

Viscoelastic response of HTPB based solid fuel to horizontal and vertical storage slumping conditions and it's affect on service life

International Nuclear Information System (INIS)

Nawaz, Q.; Nizam, F.

2011-01-01

Frequent use of solid fuels as thrust generating energy source in modern day space vehicle systems has created a need to assess their serviceability for long term storage under various conditions. Solid fuel grain, the most important part of any solid fuel system, responds visco elastically to any loading condition. For the assessment of the service life of any solid fuel system, the solid fuel grain has to be structurally evaluated in applied storage conditions. Structural integrity of the grain is exceptionally significant to guarantee the successful operation of the solid fuel system. In this work, numerical simulations have been performed to assess the mechanical stresses and strains induced in an HTPB based solid fuel grain during service life employing ABAQUS standard FEA software using 4-node bilinear quadrilateral elements. For finite element analysis (FEA), typical 2-D and p/nth axisymmetric section of 5-point (n) star grain geometry is considered. Mechanical loads include the horizontal or vertical 1-g (solid fuel weight) storage condition. The simulation results are compared with the analytical results for the same grain geometry. Analytically measured slump deflections in grain segment at various storage times have been found in good relation with the FEA based simulation results. This proves the validity of the procedure adopted and is helpful in assessment of the service life of solid fuel systems. (author)

Study of storage capacity in various carbon/graphene-based solid-state supercapacitors

Science.gov (United States)

Subramaniam, C. K.; Boopalan, G.

2014-09-01

Solid-state electrochemical double-layer capacitor (SEDLC) forms excellent energy storage device for high-power applications. They are highly reliable, with no electrolyte leaks, and can be packaged to suit various applications. The electrode material can be activated carbon to graphene. These can have a range of particle size, surface area, pore size and pore distribution for charge storage. The emphasis will be to optimize the graphene to carbon blend in the electrodes which would provide appreciable storage density of the SEDLC. We can use perfluorosulfonic acid polymer as the solid electrolyte in the SEDLC assembly. They have high ionic conductivity, good thermal stability, and mechanical strength. They also have excellent long-term chemical stability. Carbon is widely used for many practical applications, especially for the adsorption of ions and molecules, as it is possible to synthesize one-, two- or three-dimensional (1-, 2-, or 3-D) carbons. Some of the problems in activated carbon like varying micro or mesopores, poor ion mobility due to varying pore distribution, low electrical conductivity, can be overcome using graphene and blends of graphene with carbon of the right pore dimension and distribution. Graphene in various structural nomenclatures have been used by various groups for charge storage. Graphene nanoplates (GNP), with narrow mesopore distributions have been effectively used for SEDLCs. SEDLCs assembled with GNP and blends of GNP with Vulcan XC and solid polymer electrolyte like Nafion show exceptional performance. The cyclic voltammetric studies show that they support high scan rates with substantial smaller capacitance drop as we increase scan rates. Optimization of the electrode structure in terms of blend percentage, binder content and interface character in the frequency and time domain provides excellent insight into the double-layer interface.

Impact of LWR decontamination on radwaste systems

International Nuclear Information System (INIS)

Perrigo, L.D.; Divine, J.R.

1979-01-01

Increased radiation levels around certain reactors in the United States and accompanying increases in personnel exposures are causing a reexamination of options available to utilities to continue operation. One of the options is decontamination of the primary system to reduce radiation levels. The Battelle-Northwest study of decontamination and its impact on radwaste systems has been directed towards existing reactors and allied systems as they are employed during their operational lifetimes. Decommissioning and cleanup during such work are not within the scope of this project although certain processes and waste systems might be similar. Rupture debris cleanup represents a special situation that requires different design features and concepts and it is not a part of this study

The application of polyelectrolytes to improve liquid radwaste treatment system radionuclide removal efficiency

International Nuclear Information System (INIS)

Homyk, W.A.; Spall, M.J.; Vance, J.N.

1990-01-01

At nuclear plants, miscellaneous waste water treated in the liquid radwaste processing system contains a significant fraction of suspended particulate materials ranging in size from a few microns down to the submicron region. The fewer particles that typically exist as colloids are generally negatively charged by virtue of inorganic and organic anions absorbed onto the particle surfaces. Because many of the radionuclides exist as colloids and resist agglomeration and settling they are not easily removed by mechanical filtration or ion exchange processes. The colloidal materials will easily pass through most filters with conventional pore size ratings and through most ion exchange media. This leads to poor decontamination Factors (dFs) and higher radionuclide releases to the environment. A laboratory-scale testing program was conducted at Indian Point Unit No. 2 to determine the effectiveness of the use of organic polyelectrolytes to destabilize colloidal suspensions in liquid radwaste. Destabilizing colloidal suspensions will improve the removal efficiencies of the suspended material by typical filtration and ion exchange processes. The increased removal efficiencies will provide increased dFs in the liquid radwaste treatment system. The testing focused on identifying the specific organic polyelectrolytes and the associated dosages which would be effective in destabilizing the colloidal suspensions on actual waste water samples. The testing also examined the filtration characteristics of the water source to determine filter parameters such as: body feed material, body feed dosages, specific flow rates, etc., which would provide the basis for the design of filtration systems for these applications. The testing effort and the major conclusions from this investigation are given. 4 refs., 8 figs., 2 tabs

The necessity for complex long-term predictions while designing systems for disposal of radwaste and role of those predictions in development of programs for environment protection

International Nuclear Information System (INIS)

Kedrovsky, O.L.; Schishitz, I.Y.

1993-01-01

Development of nuclear power in the future depends on solving two problems: creation of safe reactors; and reliable isolation of radwaste formed during all stages of the nuclear-fuel-cycle. The peculiarity of the second problem consists of the fact that considerable financial expenses are necessary for its decision. The range of the problem is characterized by the predictions of waste accumulation according to which summary activity of those materials (by the year 2000) will come up to 6 x 10 10 mCu. To successfully solve the radwaste isolation problem on the governmental level, it is necessary to formulate the corresponding regulation system. The main task of development of geological aspects of radwaste isolation consists of elimination of dangerous situations, reaching minimum damage effect, and development of a system for hydromonitoring, which includes blocks for search and standard prediction. The paper discusses the activities being carried out in Russia to solve the problems of radwaste disposal

Evaluation of the processes used for the treatment of the hospitable radwastes containing Cs-137

International Nuclear Information System (INIS)

Peres, S.S.; Silva, J.J.G.

1988-01-01

This work presents a resume of results obtained in the treatment of radwastes containing Cs-137 from HNMD (Hospital Naval Marcilio Dias) and IRD (Instituto de Radioprotecao e Dosimetria), due to the radiological accident of Goiania. (author) [pt

Preliminary site investigation for LL and IL radwaste disposal for Qinshan NPP

International Nuclear Information System (INIS)

Huang Yawen; Chen Zhangru

1993-01-01

With the purpose of selecting a disposal site for the low- and intermediate-level radwastes arising from Qinshan NPP, site investigations were carried out in several districts of Zhejiang Province. Investigation objectives included the circumstances of geology, hydrogeology, environmental ecology, and social economy. On the basis of collected data, five possible sites were recommended for policy-making reference and further investigation

Estimation of the conditioning and storage costs of low- and intermediate-level solid radioactive wastes

International Nuclear Information System (INIS)

Lo Moro, A.; Panciatici, G.

1977-01-01

The conditioning and storage costs of low- and intermediate-level solid radioactive wastes are analyzed. The cost of direct labour is assumed as the reference cost for their computation and the storage cost is considered as resulting from the contract cost ''una tantum'' and from the leasing cost. As an example, the cost trends are reported, relevant to the solution adopted at CAMEN (conditioning in concrete containers and storage on concrete open-air bed)

Evaluation and standardisation of fast analytical techniques for destructive radwaste control

International Nuclear Information System (INIS)

De Simone, A.; Troiani, F.

2001-01-01

The document describes the work programme carried out by the Laboratorio Nazionale per la 'Caratterizzazione dei Refit Radioattivi', in the frame of the European research project Destructive Radwaste Control. The main tasks of the research work were the evaluation of fast sample pre-treatment procedures and the development of chromatographic methods coupled to fast nuclide detection by Liquid Scintillation Counting. In order to test the High Performance Ion Chromatograph (HPIC) coupled to the Liquid Scintillation Counter (LSC) on high salt content solutions, synthetic cement solutions have been prepared and spiked with several β-emitters hard to be measured with non-destructive analyses, along with other radionuclides important for the determination of the radiological inventory in radwastes. As the validation tests for the new analytical methods involved the manipulation of radioactive solutions, a remote area for HPIC-LSC apparatus has been designed and performed, in order to operate in safe conditions. According to the research programme, fast analytical methods for the chemical separation and radionuclide detection of the radioactive elements of interest, have been developed and qualified. From the results of the work, some protocols of analysis have been defined: they contain all information about operative conditions for HPIC-LSC apparatus, field of applicability, chemical and radioactive detection limits [it

Complex Metal Hydrides for hydrogen storage and solid-state ion conductors

DEFF Research Database (Denmark)

Payandeh GharibDoust, SeyedHosein

and electricity in batteries. However, both hydrogen and electricity must be stored in a very dense way to be useful, e.g. for mobile applications. Complex metal hydrides have high hydrogen density and have been studied during the past twenty years in hydrogen storage systems. Moreover, they have shown high ionic...... conductivities which promote their application as solid electrolytes in batteries. This dissertation presents the synthesis and characterization of a variety of complex metal hydrides and explores their hydrogen storage properties and ionic conductivity. Five halide free rare earth borohydrides RE(BH4)3, (RE...... = La, Ce, Pr, Nd, Er) have been synthesized, which pave the way for studying the polymorphic transition in these compounds, obtaining new bimetallic borohydrides and designing new reactive hydride composites with improved hydrogen storage capacities. Two novel polymorphs of Pr(BH4)3 are identified...

Strategy for the disposal of low- and intermediate-level radwastes in Canada

International Nuclear Information System (INIS)

Dixon, D.F.

The intent of the strategy described is to optimize both safety and cost of disposal by classifying waste segments according to hazardous lifetime and to match these to two or more selected disposl concepts graded according to containment and isolation capabilities. The bulk of low- and intermediate-level radwastes arising in Canada are a relatively short-lived hazard requiring isolation for no more than a few hundred years. Burial of this segment at tens-of-metres in quatenary deposits has been proposed as a concept worth evaluating. It is expected that part of the low- and intermediate-level radwastes will be potentially hazardous for geological time periods. Once methods of isolation for long-lived fuel wastes have been identified, these could be utilized for wastes requiring isolation for longer than a few hundred years. Disposal of a hard-rock vault is being evaluated as a reference concept and costs are presented. It is proposed that waste classification may consider more than two categories to further reduce costs and to better accommodate the radiological character of wastes. The overall disposal strategy should be flexible enough to account for present waste management practices and anticipated future needs

Gas storage materials, including hydrogen storage materials

Science.gov (United States)

Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

2013-02-19

A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

Simulation of Thermal, Neutronic and Radiation Characteristics in Spent Nuclear Fuel and Radwaste Facilities

International Nuclear Information System (INIS)

Poskas, P.; Bartkus, G.

1999-01-01

The overview of the activities in the Division of Thermo hydro-mechanics related with the assessment of thermal, neutronic and radiation characteristics in spent nuclear fuel and radwaste facilities are performed. Also some new data about radiation characteristics of the RBMK-1500 spent nuclear fuel are presented. (author)

The Engineering Design of Man-Machine Interface for RTS

International Nuclear Information System (INIS)

Yenn, T.-C.

2002-01-01

The purpose of this paper is to present the engineering design of the advanced Man-Machine Interface (MMI) of the Integrated system for Radwaste Treatment and Storage (RTS) facility in Institute of Nuclear Energy Research (INER) Taiwan, ROC. To build the RTS, a multi-function radwaste facility with a total storage of about 10,000 drums, is a five-year project starting in 2000 including intermediate activity waste treatment and combustible waste storage. The completed engineering design of the MMI is based on proven technologies and digital control systems, enhancing the radwaste management efficiency and reliability of operator's performance as well as assuring the dose exposure of personnel meeting the regulation standard. Over past few years, INER has accumulated extensive experience in the area of radwaste treatment and storage. Therefore, we are confident that we will complete this project with fulfillment of the requirements of RTS

Dissolution of britholites and monazite / brabantite solid solutions doped with actinides

International Nuclear Information System (INIS)

Du Fou De Kerdaniel, E.

2007-12-01

In the field of the radwaste storage in underground repository, several matrices were considered as promising ceramics for the specific immobilization of actinides. Two of them, britholites and monazite/ brabantite solid solution, have been considered during this work. In order to examine the dissolution mechanisms occurring at the solid liquid interface, several leaching experiments have been conducted on (Ln III PO 4 ), brabantite (Ca II An IV (PO 4 ) 2 : An = Th, U) and britholites (Ca 9 Nd 0.5 An 0.5 IV (PO 4 ) 4.5 (SiO 4 ) 1.5 F 2 : An = Th, U). Some steady experiments, performed in under saturation conditions for various pH and temperature conditions allowed to evaluate the long term behaviour of such matrices through their chemical durability. On the contrary, the thermodynamic equilibria were examined through the leaching experiments performed near the saturation conditions. By the way, various secondary phases, precipitated onto the surface of altered samples have been identified and characterized. Among them, the (Nd, Ca, Th) - rhabdophane, novelly prepared in over- saturation experiments for a thorium weight loading lower than 11 % appeared to be metastable. Indeed, it turns into TPHPH (Th 2 (PO 4 ) 2 HPO 4 .H 2 O) and Nd - rhabdophane (NdPO 4 .1/2H 2 O) when increasing leaching time. (author)

Melting decontamination and free release of metal waste at Studsvik RadWaste Co. in Sweden

International Nuclear Information System (INIS)

Kawatsuma, Shinji; Ishikawa, Keiji; Matsubara, Tatsuo; Donomae, Yasushi; Imagawa, Yasuhiro

2006-01-01

The Studsvik RadWaste Co. in Sweden was visited on August 29, 2005 by members of radioactive waste and decommissioning subgroup of central safety task force in old Japan Nuclear Cycle Development Institute as 'Overseas investigation'. The visit afforded us the chance to survey melting and decontaminating of metallic waste in this company and the status of free release. Domestic and foreign radioactive metallic waste is accepted in this company after 1987, and the majority of the decontaminated waste have been released freely. In the background of the big effort of this company and the strong leadership of the regulator (SSI: Swedish radiation protection Authority), prosperous operation was able to have been achieved. This survey was done based on 'Free release of radioactive metallic waste in Europe: the free release experience for 17 years at Studsvik RadWaste Co. in Sweden' by Dr. J. Lorenzen. (author)

Immobilization and leaching mechanisms of radwaste in cement-based matrices

International Nuclear Information System (INIS)

Glasser, F.P.; Rahman, A.A.; Crawford, R.W.; McCullough, C.E.; Angus, M.J.

1983-01-01

The effect of potential sorbers including silicas, titania, calcined kaolin, zirconium phosphate and two crystalline calcium silicates, tobermorite and xonotlite, have been used to improve the Cs-retention capacity of cement-based systems. The analysis of the pore fluid compositions of equilibrated cement-radwaste composites provides evidence concerning the leach mechanisms whereby Cs is removed. The reactions occurring between cement and clinoptilolite are elucidated and results of kinetic studies presented. Simulate Magnox waste is shown to react with cement, leading to a carbonate exchange. (author)

Solid state phase change materials for thermal energy storage in passive solar heated buildings

Science.gov (United States)

Benson, D. K.; Christensen, C.

1983-11-01

A set of solid state phase change materials was evaluated for possible use in passive solar thermal energy storage systems. The most promising materials are organic solid solutions of pentaerythritol, pentaglycerine and neopentyl glycol. Solid solution mixtures of these compounds can be tailored so that they exhibit solid-to-solid phase transformations at any desired temperature within the range from less than 25 deg to 188 deg. Thermophysical properties such as thermal conductivity, density and volumetric expansion were measured. Computer simulations were used to predict the performance of various Trombe wall designs incorporating solid state phase change materials. Optimum performance was found to be sensitive to the choice of phase change temperatures and to the thermal conductivity of the phase change material. A molecular mechanism of the solid state phase transition is proposed and supported by infrared spectroscopic evidence.

Phenomenological rate process theory for the storage of atomic H in solid Hsub(2)sup(*)

International Nuclear Information System (INIS)

Rosen, G.

1976-01-01

A phenomenological rate process theory is developed for the storage and rapid recombination of atomic hydrogen fuel radical in a crystalline molecular hydrogen solid at temperatures in the range o.1K(<=)T(<=K. It is shown that such a theory can account quantitatively for the recently observed dependence of the storage time on the storage temperature, for the maximum concentration of trapped H atom, and for the time duration of the energy release in the tritium decay experiments of Webeler

Volume reduction, a safer and cheaper way of radwaste management

International Nuclear Information System (INIS)

Mergan, L.M.; Cordier, J.P.; Storrer, J.A.

1979-01-01

Development of 'Volume Reduction' has demonstrated that it is a safer and cheaper radwaste management method. Safer, because of several advantages: decrease of solidified product volume, satisfactory product properties, absence of free water, better control of process parameters, increased encapsulation efficiency ... The corresponding impact on the waste management costs, results in important savings on different factors, as well as regards the operational costs as the investment expenses. Economy in the range of BF 35.000 per m 3 of incoming waste is achievable. The main volume reduction techniques readily available are briefly reviewed

Potential of reversible solid oxide cells as electricity storage system

OpenAIRE

Di Giorgio, Paolo; Desideri, Umberto

2016-01-01

Electrical energy storage (EES) systems allow shifting the time of electric power generation from that of consumption, and they are expected to play a major role in future electric grids where the share of intermittent renewable energy systems (RES), and especially solar and wind power plants, is planned to increase. No commercially available technology complies with all the required specifications for an efficient and reliable EES system. Reversible solid oxide cells (ReSOC) working in both ...

Strategic review on management and disposal of low- and intermediate-level solid radwastes

International Nuclear Information System (INIS)

Li Xuequn

1993-01-01

An overview on the actual status of solid low- and intermediate-level wastes (L/ILW) management in China is described. Some of the main problems at present are analysed. The strategies on management and disposal of the wastes are discussed in light of systematology. A large amount of solid L/ILW and distilled residual solution to be solidified have been accumulated during the past 30 years development of nuclear industry in China. These wastes, containing fission products, activated products, and uranium and transuranium elements respectively, mainly come from nuclear reactors, spent fuel reprocessing plants, and nuclear fuel fabrication plants. In the century, solid L/ILW and solidified wastes are produced mainly by nuclear industry; but in the next century, solid wastes will be steadily produced mainly from nuclear power plants

Humid storage conditions increase the dissolution rate of diazepam from solid dispersions prepared by melt agglomeration

DEFF Research Database (Denmark)

Jørgensen, Anna Cecilia; Torstenson, Anette Seo

2008-01-01

The purpose of this study is to investigate the effect of cooling mode and storage conditions on the dissolution rate of a solid dispersion prepared by melt agglomeration. The aim has been to relate this effect to the solid state properties of the agglomerates. The cooling mode had an effect on t...

Nanostructured materials for solid-state hydrogen storage: A review of the achievement of COST Action MP1103

NARCIS (Netherlands)

Callini, Elsa; Aguey-Zinsou, Kondo Francois; Ahuja, Rajeev; Ares, Jos Ramon; Bals, Sara; Biliskov, Nikola; Chakraborty, Sudip; Charalambopoulou, Georgia; Chaudhary, Anna Lisa; Cuevas, Fermin; Dam, Bernard; de Jongh, Petra; Dornheim, Martin; Filinchuk, Yaroslav; Novakovic, Jasmina G.; Hirscher, Michael; Hirscher, M.; Jensen, Torben R.; Jensen, Peter Bjerre; Novakovic, Nikola; Lai, Qiwen; Leardini, Fabrice; Gattia, Daniele Mirabile; Pasquini, Luca; Steriotis, Theodore; Turner, Stuart; Vegge, Tejs; Zuttel, Andreas; Montone, Amelia

2016-01-01

In the framework of the European Cooperation in Science and Technology (COST) Action MP1103 Nanostructured Materials for Solid-State Hydrogen Storage were synthesized, characterized and modeled. This Action dealt with the state of the art of energy storage and set up a competitive and coordinated

Nanostructured materials for solid-state hydrogen storage: A review of the achievement of COST Action MP1103

DEFF Research Database (Denmark)

Callini, Elsa; Aguey-Zinsou, Kondo-Francois; Ahuja, Rajeev

2016-01-01

In the framework of the European Cooperation in Science and Technology (COST) Action MP1103 Nanostructured Materials for Solid-State Hydrogen Storage were synthesized, characterized and modeled. This Action dealt with the state of the art of energy storage and set up a competitive and coordinated...

Effect of storage conditions on the calorific value of municipal solid waste.

Science.gov (United States)

Nzioka, Antony Mutua; Hwang, Hyeon-Uk; Kim, Myung-Gyun; Yan, Cao Zheng; Lee, Chang-Soo; Kim, Young-Ju

2017-08-01

Storage conditions are considered to be an important factor as far as waste material characteristics are concerned. This experimental investigation was conducted using municipal solid waste (MSW) with a high moisture content and varying composition of organic waste. The objective of this study was to understand the effect of storage conditions and temperature on the moisture content and calorific value of the waste. Samples were subjected to two different storage conditions and investigated at specified temperatures. The composition of sample materials investigated was varied for each storage condition and temperature respectively. Gross calorific value was determined experimentally while net calorific value was calculated using empirical formulas proposed by other researchers. Results showed minimal changes in moisture content as well as in gross and net calorific values when the samples were subjected to sealed storage conditions. Moisture content reduced due to the ventilation process and the rate of moisture removal increased with a rise in storage temperature. As expected, rate of moisture removal had a positive effect on gross and net calorific values. Net calorific values also increased at varying rates with a simultaneous decrease in moisture content. Experimental investigation showed the effectiveness of ventilation in improving the combustion characteristics of the waste.

Tank designs for combined high pressure gas and solid state hydrogen storage

DEFF Research Database (Denmark)

Mazzucco, Andrea

Many challenges have still to be overcome in order to establish a solid ground for significant market penetration of fuel cell hydrogen vehicles. The development of an effective solution for on-board hydrogen storage is one of the main technical tasks that need to be tackled. The present thesis...... deals with the development of a simulation tool to design and compare different vehicular storage options with respect to targets based upon storage and fueling efficiencies. The set targets represent performance improvements with regard to the state-of-the-art technology and are separately defined...... volume. Heat transfer augmentation techniques (e.g. encapsulation) are found to be the reward strategy to achieve the same stored mass and fueling time of the standard technology, while enabling ambient temperature fueling and save the energy cooling demand (4.2 MJ per fueling) at the refueling station....

Experimental investigation of factors affecting the control of redox conditions within a radwaste repository

International Nuclear Information System (INIS)

Guppy, R.M.; Atkinson, A.

1991-04-01

The maximum aqueous concentration of multivalent radioelements in a radwaste repository can be estimated from the expected Eh (the oxidising or reducing tendency of the solution) and pH of the aqueous phase in the repository so long as equilibrium between all oxidising and reducing species can be guaranteed. The objective of the work reported here was to ascertain whether any significant departures from redox equilibrium are likely to arise. Technetium (VII) species were exposed under anaerobic conditions to concentrations of ferrous, hydrogen sulphide and thiosulphate species likely to be present in a repository environment to establish which species are capable of reducing aqueous Tc(VII) to a less soluble Tc(IV) solid compound. Potential catalytic solid phases and phases capable of electron exchange were also exposed to Tc(VII) species under anaerobic, aerobic and hydrogen atmospheres. We have not been able to demonstrate conclusively that mutual equilibrium was attained between technetium and iron redox couples, nor that the apparent solubility of technetium was that expected from the resulting Eh and pH of the solution, although some technetium was removed from solution. Hydrogen did not reduce Tc(VII) within the timescale of the experiments and no catalytic effects by haematite or a cementitious backfill grout for reductions involving hydrogen were observable. Magnetite removed some technetium from solution, apparently by surface reaction, under inert (argon) and reducing (hydrogen) atmospheres. Sulphides, and to a lesser extent thiosulphates, will reduce the solubility of technetium to a very low level. (author)

Storage of solid and liquid radioactive material

International Nuclear Information System (INIS)

Matijasic, A.; Gacinovic, O.

1961-01-01

Solid radioactive waste collected during 1961 from the laboratories of the Institute amounted to 22.5 m 3 . This report contains data about activity of the waste collected from january to November 1961. About 70% of the waste are short lived radioactive material. Material was packed in metal barrels and stored in the radioactive storage in the Institute. There was no contamination of the personnel involved in these actions. Liquid radioactive wastes come from the Isotope production laboratory, laboratories using tracer techniques, reactor cooling; decontamination of the equipment. Liquid wastes from isotope production were collected in plastic bottles and stored. Waste water from the RA reactor were collected in special containers. After activity measurements this water was released into the sewage system since no activity was found. Table containing data on quantities and activity of radioactive effluents is included in this report

Radioactive waste management in Romania

International Nuclear Information System (INIS)

Barariu, Gheorghe; Radu, Maria; Dobos, Ion; Glodeanu, Florin; Popescu, V. Ion; Rotarescu, Gheorghe; Turcanu, Cornel

1998-01-01

The paper presents the main aspects of management of radwastes generated within the frame of Nuclear Fuel Cycle (NFC) and out of Nuclear Fuel Cycle in Romania. There are mentioned the Romanian legislative and regulatory framework concerning nuclear activities which include provisions for radwaste management generated in Romania. The paper lists the radwaste producers, mentions waste inventory and gives future estimates for radwaste generation, all determining development of the radwaste management strategy. Choosing selected strategy for radwaste management, the main responsible organizations have been established as well as the planned facilities for treatment conditioning, storage and disposal of radwastes generated within the frame of both NFC and out of NFC fields of peaceful nuclear activity. (authors)

Radioactive solid waste inventories at United States Department of Energy burial and storage sites

International Nuclear Information System (INIS)

Watanabe, T.

1986-06-01

Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1985. This report differs from previous issues in that the data cutoff date is December 31, 1985, rather than the fiscal year end. Another difference from previous issues is that data for the TRU categories 1 and 6 have been omitted

300 GPM Solids Removal System A True Replacement for Back Flushable Powdered Filter Systems - 13607

Energy Technology Data Exchange (ETDEWEB)

Ping, Mark R.; Lewis, Mark [EnergySolutions, Suite 100, Center Point II, 100 Center Point Circle, Columbia, SC 29210 (United States)

2013-07-01

The EnergySolutions Solids Removal System (SRS) utilizes stainless steel cross-flow ultra-filtration (XUF) technology which allows it to reliably remove suspended solids greater than one (1) micron from liquid radwaste streams. The SRS is designed as a pre-treatment step for solids separation prior to processing through other technologies such as Ion Exchange Resin (IER) and/or Reverse Osmosis (RO), etc. Utilizing this pre-treatment approach ensures successful production of reactor grade water while 1) decreasing the amount of radioactive water being discharged to the environment; and 2) decreasing the amount of radioactive waste that must ultimately be disposed of due to the elimination of spent powdered filter media. (authors)

300 GPM Solids Removal System A True Replacement for Back Flushable Powdered Filter Systems - 13607

International Nuclear Information System (INIS)

Ping, Mark R.; Lewis, Mark

2013-01-01

The EnergySolutions Solids Removal System (SRS) utilizes stainless steel cross-flow ultra-filtration (XUF) technology which allows it to reliably remove suspended solids greater than one (1) micron from liquid radwaste streams. The SRS is designed as a pre-treatment step for solids separation prior to processing through other technologies such as Ion Exchange Resin (IER) and/or Reverse Osmosis (RO), etc. Utilizing this pre-treatment approach ensures successful production of reactor grade water while 1) decreasing the amount of radioactive water being discharged to the environment; and 2) decreasing the amount of radioactive waste that must ultimately be disposed of due to the elimination of spent powdered filter media. (authors)

Sorption data base for performance assessment of radwaste repository

International Nuclear Information System (INIS)

Cho, Y.H.; Jung, J.; Lee, J.K.; Hahn, P.S.

2001-01-01

Sorption data base (SDB) provides readily available data for the performance assessment of radwaste repository when site-specific data are not available and/or more reference data are needed. The software developed in the Korea Atomic Energy Research Institute (KAERI), SDB-21C, is a graphic user interface (GUI) program that provides efficient and user friendly tools for evaluating the large amount of sorption data. The data base of distribution coefficients compiled in the program contains about 11,000 Nuclear Energy Agency (NEA) data and 2,000 KAERI data up to now while the addition of new data is under progress. Furthermore, the parametric model and its compiled data sets are also included in SDB-21C. (author)

DWPF waste glass Product Composition Control System

International Nuclear Information System (INIS)

Brown, K.G.; Postles, R.L.

1992-01-01

The Defense Waste Processing Facility (DWPF) will be used to blend aqueous radwaste (PHA) with solid radwaste (Sludge) in a waste receipt vessel (the SRAT). The resulting SRAT material is transferred to the SME an there blended with ground glass (Frit) to produce a batch of melter feed slurry. The SME material is passed to a hold tank (the MFT) which is used to continuously feed the DWPF melter. The melter. The melter produces a molten glass wasteform which is poured into stainless steel canisters for cooling and, ultimately, shipment to and storage in a geologic repository. The Product Composition Control System (PCCS) is the system intended to ensure that the melt will be processible and that the glass wasteform will be acceptable. This document provides a description of this system

Dissolution of britholites and monazite / brabantite solid solutions doped with actinides; Etude de la dissolution de britholites et de solutions solides monazite / brabantite dopees avec des actinides

Energy Technology Data Exchange (ETDEWEB)

Du Fou De Kerdaniel, E

2007-12-15

In the field of the radwaste storage in underground repository, several matrices were considered as promising ceramics for the specific immobilization of actinides. Two of them, britholites and monazite/ brabantite solid solution, have been considered during this work. In order to examine the dissolution mechanisms occurring at the solid liquid interface, several leaching experiments have been conducted on (Ln{sup III}PO{sub 4} ), brabantite (Ca{sup II}An{sup IV}(PO{sub 4}){sub 2}: An = Th, U) and britholites (Ca{sub 9}Nd{sub 0.5}An{sub 0.5}{sup IV} (PO{sub 4}){sub 4.5}(SiO{sub 4}){sub 1.5}F{sub 2}: An = Th, U). Some steady experiments, performed in under saturation conditions for various pH and temperature conditions allowed to evaluate the long term behaviour of such matrices through their chemical durability. On the contrary, the thermodynamic equilibria were examined through the leaching experiments performed near the saturation conditions. By the way, various secondary phases, precipitated onto the surface of altered samples have been identified and characterized. Among them, the (Nd, Ca, Th) - rhabdophane, novelly prepared in over- saturation experiments for a thorium weight loading lower than 11 % appeared to be metastable. Indeed, it turns into TPHPH (Th{sub 2}(PO{sub 4}){sub 2}HPO{sub 4}.H{sub 2}O) and Nd - rhabdophane (NdPO{sub 4}.1/2H{sub 2}O) when increasing leaching time. (author)

Radioactive waste on-site storage alternative

International Nuclear Information System (INIS)

Dufrane, K.H.

1983-01-01

The first, most frequently evaluated approach for the large producer is the construction of a relatively expensive storage building. However, with the likely possibility that at least one disposal site will remain available and the building never used, such expenditures are difficult to justify. A low cost, but effective alternative, is the use of ''On-Site Storage Containers'' (OSSC) when and if required. Radwaste is only stored in the OSSC if a disposal site is not available. A small number of OSSC's would be purchased initially just to assure immediate access to storage. Only in the unlikely event of total disposal sites closure would additional OSSC's have to be obtained and even this is cost effective. With two or three months of storage available on site, production lead time is sufficient for the delivery of additional units at a rate faster than the waste can be produced. The recommended OSSC design would be sized and shielding optimized to meet the needs of the waste generator. Normally, this would duplicate the shipping containers (casks or vans) currently in use. The reinforced concrete design presented is suitable for outside storage, contains a leakproof polyethylene liner and has remote sampling capability. Licensing would be under 10CFR50.59 for interim storage with long-term storage under 10CFR30 not an impossibility. Cost comparisons of this approach vs. building construction show that for a typical reactor plant installation, the OSSC offers direct savings even under the worst case assumption that no disposal sites are available and the time value of money is zero

Impact of decontamination on LWR radioactive waste treatment systems

International Nuclear Information System (INIS)

Hoenes, G.R.; Perrigo, L.D.; Divine, J.R.; Faust, L.G.

1979-01-01

Only at N-Reactor is there a means to accommodate radwaste produced during decontamination. The Dresden system is expected to be ready to accommodate such solutions by the summer of 1979. Solidification of the processed decontamination waste may be a significant problem. There is doubt that the materials in current radwaste treatment systems can handle chemicals from a concentrated process. The total storage volume, for concentrated decontamination, is not sufficient in existing radwaste treatment systems. Greater attention should be placed on designing reactors and radwaste treatment systems for decontamination. A means of handling waste material resulting from leaks in the primary system during the decontamination must be developed. On-site storage of solidified decontamination wastes may be a viable option, but license amendments will be necessary

Mathematical simulation of gas pressure in fibre-reinforced concrete container at radiation and biological decomposition of cellulose, bituminized and concrete radwastes

International Nuclear Information System (INIS)

Kuruc, J.; Kvito, P.

2005-01-01

Fibre-reinforced concrete container (FRCC) are used for long-time repository of radioactive wastes. Low- and middle-active radwastes from operation of the NPPs V-1, V-2 Jaslovske Bohunice, Mochovce NPP and from decommissioned NPP A-1 (Jaslovske Bohunice) are treated in the plant SE-VYZ in Jaslovske Bohunice and after immobilisation are deposited in National Radwaste Repository Mochovce (RU RAO). After filling of the RU RAO, FRCC will be stored during 300 years. During this time the integrity of the FRCC must be guaranteed. By the influence of autoradiolysis of the cellulose and bituminized radwastes as well as in cement grout the gases are formed, mainly the hydrogen, methane and carbon dioxide. In the case of presence of available water (a w ≥ 0.63) and in presence of microbes and moulds at appropriate conditions the biological decomposition of cellulose materials may proceed with formation of H 2 , CH 4 a CO 2 . With increasing of developed gases may increase pressure in FRCC, that may initiate the loss of integrity of the FRCC with following endangering of radiation safety of the RU RAO, respectively of the territory over the repository.Authors developed the new mathematical model of pressure of gases in FRCC and in deposited barrels with cellulose and bituminized radwastes. The mathematical model is based on biological decomposition of cellulose materials as well as on radiation decomposition of cellulose, bitumen and concrete. In this mathematical model the diffusion through the walls of FRCC is the main process responsible for decreasing of the pressure. This model was developed in two basic variants: (1) Mathematical model of gas pressure in FRCC as function of dose; (2) Mathematical model of gas pressure in FRCC as function of mass of cellulose

Radiochemical Separation and Quantification of Tritium in Metallic Radwastes Generated from CANDU Type NPP - 13279

Energy Technology Data Exchange (ETDEWEB)

Ahn, H.J.; Choi, K.C.; Choi, K.S.; Park, T.H.; Park, Y.J.; Song, K. [Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-330 (Korea, Republic of)

2013-07-01

As a destructive quantification method of {sup 3}H in low and intermediate level radwastes, bomb oxidation, sample oxidation, and wet oxidation methods have been introduced. These methods have some merits and demerits in the radiochemical separation of {sup 3}H radionuclides. That is, since the bomb oxidation and sample oxidation methods are techniques using heating at high temperature, the separation methods of the radionuclides are relatively simple. However, since {sup 3}H radionuclide has a property of being diffused deeply into the inside of metals, {sup 3}H which is distributed on the surface of the metals can only be extracted if the methods are applied. As an another separation method, the wet oxidation method makes {sup 3}H oxidized with an acidic solution, and extracted completely to an oxidized HTO compound. However, incomplete oxidized {sup 3}H compounds, which are produced by reactions of acidic solutions and metallic radwastes, can be released into the air. Thus, in this study, a wet oxidation method to extract and quantify the {sup 3}H radionuclide from metallic radwastes was established. In particular, a complete extraction method and complete oxidation method of incomplete chemical compounds of {sup 3}H using a Pt catalyst were studied. The radioactivity of {sup 3}H in metallic radwastes is extracted and measured using a wet oxidation method and liquid scintillation counter. Considering the surface dose rate of the sample, the appropriate size of the sample was determined and weighed, and a mixture of oxidants was added to a 200 ml round flask with 3 tubes. The flask was quickly connected to the distilling apparatus. 20 mL of 16 wt% H{sub 2}SO{sub 4} was given into the 200-ml round flask through a dropping funnel while under stirring and refluxing. After dropping, the temperature of the mixture was raised to 96 deg. C and the sample was leached and oxidized by refluxing for 3 hours. At that time, the incomplete oxidized {sup 3}H compounds were

Radioactive waste management in the Federal Republic of Germany: Industrial practices and results

International Nuclear Information System (INIS)

Grabener, K.H.

1987-01-01

In the Federal Republic of Germany (FRG), the production and use of nuclear-generated electricity expanded steadily despite the fact that opposition from the environmentalists led to the impression of an upcoming moratorium for nuclear energy. With this increase in capacity--by the year 1990, nearly 25 000 MW will be on the line--there will be an increase in the volume of low-level (non-heat-generating) radwaste originating from nuclear power plants. Radwaste management has been influenced to a considerable extent by the requirements of the final repository. Following a period of trial storage in the Asse repository, preparations are now being made for storage in the Konrad ore mine. It is intended to begin storage in 1991. Requirements for the packages specify containers with a volume from 3.9 to 10.9 m/sup 3/ or cast iron safety drums. These drums are suitable for radioactive materials in powder form (resins, dried concentrates) without the need for embedding materials. Storage in standard 55-gal drums is no longer permitted. The costs for final storage will be very high so that volume reduction is of prime importance. Kraftwerk Union (KWU) as a supplier of nuclear power plants (NPPs) examined the radwaste market and decided to combine delivery of radwaste treatment systems to NPPs with service jobs including radwaste handling and conditioning in its own service and maintenance plant at Karlstein

Performance assessment for continuing and future operations at solid waste storage area 6. Appendices

International Nuclear Information System (INIS)

1997-09-01

This appendix provides the radionuclide inventory data used for the Solid Waste Storage Area (SWSA) 6 Performance Assessment (PA). The uncertainties in the radionuclide inventory data are also provided, along with the descriptions of the methods used to estimate the uncertainties. of the methods used to estimate the uncertainties

The no-cost radwaste resource: Utilizing the system engineer to help achieve optimum radwaste system performance

International Nuclear Information System (INIS)

Green, R.; Michalski, M.

1995-01-01

All of us in the nuclear power business today know and often use words like - de-regulation, downsize, manpower reduction, cost savings, budget cuts, cost per kilowatt and probably 25 other terms, all relating to you doing a better job with less money and fewer resources. Maybe I have a suggestion that will help you find a resource that can help you - a no-cost resource that you may already have and may not be using. I don't know what you believe, but I believe that a nuclear power station can only be as good as the people who work there, and I believe that system performance and reliability can be improved on virtually any system by merely directing focus and attention to that system. In other words, systems are like children, if you neglect them, they go bad... And they go bad when you're not expecting it. This paper looks at what a system engineer can do for you toward a goal of optimum Radwaste system performance and reviews some of the tools we are using at Grand Gulf to reach our goals

Liquid radwaste processing, operational experience utilizing Duratek Mobile Process System (MPS)

International Nuclear Information System (INIS)

Hunkele, W.; Jensen, C.E.; Duratek Corp., Beltsville, MD)

1985-01-01

The use of Duratek's Mobile Process System (MPS) employing sluiceable pressure vessels and improved operational techniques generates operational efficiencies including volume reduction (VR), reduced personnel labor and exposure and higher flowrates for cleanup of liquid radwaste streams in an operating nuclear power plant (Salem Generating Station). Significant additional VR is achievable based on laboratory and on-site experience utilizing Durasil 70. Under high conductivity, actual waste stream conditions, this proprietary media has demonstrated through-puts of a magnitude 15 times higher than organic cation resin. A long-term problem, cobalt species removal, is mitigated by this media

On selection of geological medium for disposal of high-level radwaste

International Nuclear Information System (INIS)

Min Maozhong

1991-01-01

The present paper briefly reviews the suitability of some rocks as geological disposal repositories of high-level radwaste (HLW). The suitable rocks for geological ogi disposal of HLW are rock salt (salt diapir, bedded salt), granite, argillaceous rocks, tuff, basalt, gabbro, diabase, anhydrite, marine sedimentary rocks etc., especially, rock salt, granite, and argillaceous rocks. The data of principal hydraulic properties, mechanical-physical properties for various rocks in typical environment which might be considered for disposal purposes are also given in this paper. These data give a reference to China's geological disposal of HLW in the future

Preparation of Radwaste Disposal Site in Jawa Island and Its Surrounding Areas

International Nuclear Information System (INIS)

Budi Setiawan; Teddy Sumantry; Heru Sriwahyuni; Hendra A Pratama; Nurul Efri E; Achmad Sjarmufni; Pratomo Budiman; Dadang Suganda; Soegeng Waluyo; Ari Pudyo; Dewi Susilowati; Marwoto

2008-01-01

The task continuation and national needs indicate the important of starting for radioactive waste disposal preparation. As the IAEA procedures for the first step are to accomplished the conceptual and planning stage of radwaste disposal siting in Jawa island. Within the plan, the Milestone, the site important factors, the potential host rock, the possible areas, the aims and the investigation programs have been defined. From the procedures which are followed hopefully in the end of the activities, suitable site(s) to be able selected for radioactive waste disposal facility in near future. (author)

New plant improves radwaste processing at the Tokai-2 BWR

International Nuclear Information System (INIS)

Anon.

1988-01-01

New plant for radiowaste processing at the Tokaj-2 NPP, put in operation in September, 1986, is described. The plant includes five systems providing processing of drianage water, solid waste combustion, decrease of volume and solidification of concentrated wastes, waste storage and flushing water processing. Pressed tablets represent the final product of the waste processing. New plant enables to reduce sufficiently the volume of radioactive wastes

Enhanced reversibility and durability of a solid oxide Fe-air redox battery by carbothermic reaction derived energy storage materials.

Science.gov (United States)

Zhao, Xuan; Li, Xue; Gong, Yunhui; Huang, Kevin

2014-01-18

The recently developed solid oxide metal-air redox battery is a new technology capable of high-rate chemistry. Here we report that the performance, reversibility and stability of a solid oxide iron-air redox battery can be significantly improved by nanostructuring energy storage materials from a carbothermic reaction.

Scattering-layer-induced energy storage function in polymer-based quasi-solid-state dye-sensitized solar cells.

Science.gov (United States)

Zhang, Xi; Jiang, Hongrui

2015-03-09

Photo-self-charging cells (PSCs) are compact devices with dual functions of photoelectric conversion and energy storage. By introducing a scattering layer in polymer-based quasi-solid-state dye-sensitized solar cells, two-electrode PSCs with highly compact structure were obtained. The charge storage function stems from the formed ion channel network in the scattering layer/polymer electrolyte system. Both the photoelectric conversion and the energy storage functions are integrated in only the photoelectrode of such PSCs. This design of PSC could continuously output power as a solar cell with considerable efficiency after being photo-charged. Such PSCs could be applied in highly-compact mini power devices.

McPhy-Energy’s proposal for solid state hydrogen storage materials and systems

Energy Technology Data Exchange (ETDEWEB)

Jehan, Michel, E-mail: michel.jehan@mcphy.com [McPhy Energy SA, ZA Retière, 26190 La Motte-Fanjas (France); Fruchart, Daniel, E-mail: daniel.fruchart@grenoble.cnrs.fr [McPhy Energy SA, ZA Retière, 26190 La Motte-Fanjas (France); Institut Néel and CRETA, CNRS, 25 Avenue des Martyrs, BP 166, 38042 Grenoble Cedex 9 (France)

2013-12-15

Highlights: •Mechanical alloying with nano-structurizing highly reactive magnesium metal hydrides particles. •Solid reversible hydrogen storage at scale of kg to tons of hydrogen using MgH{sub 2} composite discs. •Natural Expanded Graphite draining heat of reaction during sorption. •Change Phase Material storing reversibly heat of reaction within tank storage as adiabatic system. •Technology fully adapted for renewable energy storage and network energy peak shavings through H{sub 2}. -- Abstract: The renewable resources related, for instance, to solar energies exhibit two main characteristics. They have no practical limits in regards to the efficiency and their various capture methods. However, their intermittence prevents any direct and immediate use of the resulting power. McPhy-Energy proposes solutions based on water electrolysis for hydrogen generation and storage on reversible metal hydrides to efficiently cover various energy generation ranges from MW h to GW h. Large stationary storage units, based on MgH{sub 2}, are presently developed, including both the advanced materials and systems for a total energy storage from ∼70 to more than 90% efficient. Various designs of MgH{sub 2}-based tanks are proposed, allowing the optional storage of the heat of the Mg–MgH{sub 2} reaction in an adjacent phase changing material. The combination of these operations leads to the storage of huge amounts of hydrogen and heat in our so-called adiabatic-tanks. Adapted to intermittent energy production and consumption from renewable sources (wind, sun, tide, etc.), nuclear over-production at night, or others, tanks distribute energy on demand for local applications (on-site domestic needs, refueling stations, etc.) via turbine or fuel cell electricity production.

Effect of storage conditions on losses and crop utilization of nitrogen from solid cattle manure

NARCIS (Netherlands)

Shah, G.M.; Shah, G.A.; Groot, J.C.J.; Oenema, O.; Raza, A.S.; Lantinga, E.A.

2016-01-01

The objectives of the present study were to quantify the effects of contrasting methods for storing solid cattle manure on: (i) total carbon (C) and nitrogen (N) balances during storage, and (ii) crop apparent N recovery (ANR) following manure application to arable land, with maize as a test

Kola peninsula radwaste management in the framework of THE Italian-Russian cooperation agreement for global partnership - 59392

International Nuclear Information System (INIS)

Nobile, Massimiliano; Izmailov, Dmitry; Spadoni, Antonino; Uryvskiy, Oleg

2012-01-01

In 2003 a Cooperation Agreement, envisaging a grant of 360 Meuro in 10 years, was signed between Italy and Russia in the framework of the 'so-called' Global Partnership Program. So far, in five years of concrete work, a total of 146 Meuro have been engaged through 33 contracts and 121 Meuro have been already paid. Together with other significant lines of activities the management of waste, presently located at Andreeva Bay site, is surely the most important one, not only for the amount of allocated funds (about the half of available ones) but also for the urgency to solve serious environmental problems linked to the actual unsafe conditions of these waste, both as regards possible incidents or malicious attacks from outside. Volume of Low Level and Intermediate Level (LL/IL) waste at Andreeva Bay site are 17000 tons and 3000 tons, respectively for solid and liquid; moreover is expected, during the next 15 years, the production of additional 33000 tons of liquid and 8000 tons of solid, due to the need of demolishing existing facilities and final closing of the site. As regards radwaste management facilities, the solution defined in OBIN (justification of investment) has been analyzed and critically reviewed. After the completion of a conceptual study, the construction of three facilities (solid and liquid treatment ones and a protective structure for storing on site temporarily conditioned waste) was decided and a contract was assigned in 2010 to Ansaldo Nucleare/AtomStroyExport for the detailed design of the above mentioned facilities, which is expected to be completed in 2012. Some important modifications to the initial time schedule have been taken into account and now the operation of the facilities is expected by 2015, two years before the previous estimate. (authors)

Assessment of tritiated activities in the radwaste generated from ITER Chinese helium cooled ceramic breeding test blanket module system

Energy Technology Data Exchange (ETDEWEB)

Chen, Chang An, E-mail: chenchangan@caep.cn; Liu, Lingbo; Wang, Bo; Xiang, Xin; Yao, Yong; Song, Jiangfeng

2016-11-15

Highlights: • Approaches were developed for calculation/evaluation of tritium activities in the materials and components of a TBM system, with tritium permeation being considered for the first time. • Almost all tritiated materials and components were considered in CNHCCB TBM system including the TBM set, connection pipes, and the ancillary tritium handling systems. • Tritium activity data in HCCB TBM system were updated. Some of which in directly tritium contacted components are to be 2 or 4 magnitudes higher than the original neutron transmutation calculations. • The radwaste amount from both operation and decommission of HCCB TBM system was evaluated. - Abstract: Chinese Helium Cooled Ceramic Breeding Test blanket Module (CNHCCB TBM) will be tested in the ITER machine for the feasibility of in pile tritium production for a future magnetic confinement fusion reactor. The tritium inventories/retentions in the material/components were evaluated and updated mainly based on the tritium diffusion/permeation theory and the analysis of some reported data. Tritiated activities rank from less than 10 Bq g{sup −1} to 10{sup 9} Bq g{sup −1} for the different materials or components, which are generally higher than those from the previous neutron transmutation calculation. The amounts of tritiated radwaste were also estimated according to the operation, decommission, maintenance and replacement strategies, which vary from several tens of kilograms to tons in the different operation phases. The data can be used both for the tritium radiological safety evaluation and radwaste management of CNHCCB TBM set and its ancillary systems.

Performance assessment for continuing and future operations at solid waste storage area 6

International Nuclear Information System (INIS)

1997-09-01

This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility

Performance assessment for continuing and future operations at solid waste storage area 6

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility.

Introduction to seminar on organics in radwaste held at Harwell on 22nd September 1987

International Nuclear Information System (INIS)

Bradbury, D.

1988-01-01

The introduction to the Seminar on Organics in Radwaste stresses the necessity for the efficiency of natural and engineered barriers designed for the management of radioactive wastes to satisfy public scrutiny. The preparation of wastes prior to encapsulation is discussed. The negative effects of introduced organic material in waste sites on safety and the mechanism of organic degradation prior to the removal of organics from wastes is discussed. (U.K.)

Of creation of up-to-date system for liquid radwaste management at Ukraine's NPPs. Problem statement

International Nuclear Information System (INIS)

Andronov, O.B.

2015-01-01

The main aspects are addressed of problems in the field of liquid radwaste (LRW) management for Ukrainian NPPs; approaches for its decision, and offers of NNEGC Energoatom SE STC specialists concerning the above issue. Conceptual principle of creation of up-to-date hi-tech complex for LRW management is considered

Solid NMR characterization of hydrogen solid storage matrices

International Nuclear Information System (INIS)

Pilette, M.A.; Charpentier, T.; Berthault, P.

2007-01-01

The aim of this work is to develop and validate characterization tools by NMR imagery and spectroscopy of the structure of materials for hydrogen storage, and of their evolution during load/unload cycles. The two main topics of this work are in one hand the analysis of the local structure of the materials and the understanding of their eventual modifications, and in another hand, the in-situ analysis of the distribution and diffusion of hydrogen inside the storage material. (O.M.)

Immobilization and leaching mechanisms of radwaste in cement-based matrices

International Nuclear Information System (INIS)

Glasser, F.P.; Rahman, A.A.; Crawford, R.W.; McCullough, C.E.; Angus, M.J.

1982-03-01

The components of anhydrous cement clinkers and their adsorptive properties for Cs has been determined. The efficiency of different analytical methods are compared, and it is shown that only radiochemical methods afford a true picture of the quantitative extent of adsorption. Hydrothermal studies have been undertaken to assess the interactions between the Ca(OH) 2 component of cement and radioactive waste constituents. In most cases, chemical reaction occurs due to the strongly alkaline nature of the medium: the potential of hydrothermal methods for predicting the behaviour and performance of cement-radwaste systems is assessed and the relevant solution chemistry described. Cement-zeolite interactions have been studied: these interactions are revealed by a variety of physical techniques, and begin to afford some insight into the reaction mechanism. (author)

Performance assessment for Nuclear Power Plant Krsko intermediate and low-level rad-waste repository; Provjera sigurnosnih performansi odlagalishta radioaktivnog otpada niske i srednje aktivnosti nuklearne elektrane Krsko

Energy Technology Data Exchange (ETDEWEB)

Jelavic, V [Inst. za Elektroprivredu, Zagreb. (Yugoslavia).; Tankosic, Dj [Bechtel Inc., San Francisco (United States); Skanata, D [Nuklearna elektrana Krshko, Krshko (Yugoslavia); Plecjas, I [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

1990-07-01

Performance safety Assessment for NPP Krsko radwaste repository was performed (LLW/ILW). Shallow land and tunnel type concept were analyzed. Because it was based on two unknown referent sites, one for the shallow land concept and the other for the tunnel type, analysis was generic in nature. Scenario selecting process and consequence analysis were performed by using deterministic approach. Results for both concepts of disposal suggests that proposed NPP Krsko radwaste repository reference site and disposal technology will fully meet radiation limits imposed by the Yugoslav regulations and ICRP guidelines. (author)

Tritium storage

International Nuclear Information System (INIS)

Hircq, B.

1990-01-01

This document represents a synthesis relative to tritium storage. After indicating the main storage particularities as regards tritium, storages under gaseous and solid form are after examined before establishing choices as a function of the main criteria. Finally, tritium storage is discussed regarding tritium devices associated to Fusion Reactors and regarding smaller devices [fr

Robotic cleaning of radwaste tank nozzles

International Nuclear Information System (INIS)

Boughman, G.; Jones, S.L.

1992-01-01

The Susquehanna radwaste processing system includes two reactor water cleanup phase separator tanks and one waste sludge phase separator tank. A system of educator nozzles and associated piping is used to provide mixing in the tanks. The mixture pumped through the nozzles is a dense resin-and-water slurry, and the nozzles tend to plug up during processing. The previous method for clearing the nozzles had been for a worker to enter the tanks and manually insert a hydrolaser into each nozzle, one at a time. The significant radiation exposure and concern for worker safety in the tank led the utility to investigate alternate means for completing this task. The typical tank configuration is shown in a figure. The initial approach investigated was to insert a manipulator arm in the tank. This arm would be installed by workers and then teleoperated from a remote control station. This approach was abandoned because of several considerations including educator location and orientation, excessive installation time, and cost. The next approach was to use a mobile platform that would operate on the tank floor. This approach was selected as being the most feasible solution. After a competitive selection process, REMOTEC was selected to provide the mobile platform. Their proposal was based on the commercial ANDROS Mark 5 platform

Decommissioning of NPP A1 - HWGCR type

International Nuclear Information System (INIS)

Burclova, J.

1998-01-01

support) in 1997 as well as preparation for bituminization of organic spent fuel coolant. The new equipment for spent fuel handling including new storage (semi dry) for spent fuel was projected and should be built up in 1997. The decontamination and dismantling of auxiliary equipment (radwaste tanks, evaporation plant and original solid storage) should start after the commissioning of conditioning centre and bituminization plant with new evaporation plant in 1998 and finish at 2000. The decontamination and dismantling of original spent fuel storage should finish at 2007/8. Supporting activities to these works started at 1994/95. (author)

Development of high integrity containers for rad-waste treatment

Energy Technology Data Exchange (ETDEWEB)

Song, Yung Chul; Cho, Myung Sug; Jung, Yun Sub [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

1995-12-31

Nuclear power plants are generating rad waste such as solid wastes, concentrated liquid wastes, spent resins and spent filters, and various types of imported containers which have different specifications and material properties are employed to handle the rad wastes according to facility characteristics of the plants or the type of wastes. These containers are stored at the intermediate storage facilities at the plant site due to the construction delay of permanent disposal site, and the additional construction of storage and disposal sites become more difficult with increase of the numbers and the operation time of the plants. In order to solve these difficulties, rad wastes volume reduction facilities such as High Pressure Compression Facility or Drying Facility are being installed and use of High Integrity Containers(HIC) are increasing. Therefore, we decide quality and technology standards required for the HIC, and then develop the HIC which satisfies the standards with new composite material called Steel Fiber Polymer Impregnated Concrete(SFPIC) (author). 84 refs., 118 figs.

Development of high integrity containers for rad-waste treatment

Energy Technology Data Exchange (ETDEWEB)

Song, Yung Chul; Cho, Myung Sug; Jung, Yun Sub [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

1996-12-31

Nuclear power plants are generating rad waste such as solid wastes, concentrated liquid wastes, spent resins and spent filters, and various types of imported containers which have different specifications and material properties are employed to handle the rad wastes according to facility characteristics of the plants or the type of wastes. These containers are stored at the intermediate storage facilities at the plant site due to the construction delay of permanent disposal site, and the additional construction of storage and disposal sites become more difficult with increase of the numbers and the operation time of the plants. In order to solve these difficulties, rad wastes volume reduction facilities such as High Pressure Compression Facility or Drying Facility are being installed and use of High Integrity Containers(HIC) are increasing. Therefore, we decide quality and technology standards required for the HIC, and then develop the HIC which satisfies the standards with new composite material called Steel Fiber Polymer Impregnated Concrete(SFPIC) (author). 84 refs., 118 figs.

Solid-State Hydrogen Storage

Data.gov (United States)

National Aeronautics and Space Administration — This project will develop a method for converting metals to metal hydrides at low pressures for hydrogen storage systems with high efficiency with respect to volume...

Geophysical investigations at ORNL solid waste storage area 3

International Nuclear Information System (INIS)

Rothschild, E.R.; Switek, J.; Llopis, J.L.; Farmer, C.D.

1985-07-01

Geophysical investigations at ORNL solid waste storage area 3 have been carried out. The investigations included very-low-frequency-electromagnetic resistivity (VLF-EM), electrical resistivity, and seismic refraction surveys. The surveys resulted in the measurement of basic geophysical rock properties, as well as information on the depth of weathering and the configuration of the bedrock surface beneath the study area. Survey results also indicate that a number of geophysical anomalies occur in the shallow subsurface at the site. In particular, a linear feature running across the geologic strike in the western half of the waste disposal facility has been identified. This feature may conduct water in the subsurface. The geophysical investigations are part of an ongoing effort to characterize the site's hydrogeology, and the data presented will be valuable in directing future drilling and investigations at the site. 10 refs., 6 figs

Key study on the potential of hydrazine bisborane for solid- and liquid-state chemical hydrogen storage.

Science.gov (United States)

Pylypko, Sergii; Petit, Eddy; Yot, Pascal G; Salles, Fabrice; Cretin, Marc; Miele, Philippe; Demirci, Umit B

2015-05-04

Hydrazine bisborane N2H4(BH3)2 (HBB; 16.8 wt %) recently re-emerged as a potential hydrogen storage material. However, such potential is controversial: HBB was seen as a hazardous compound up to 2010, but now it would be suitable for hydrogen storage. In this context, we focused on fundamentals of HBB because they are missing in the literature and should help to shed light on its effective potential while taking into consideration any risk. Experimental/computational methods were used to get a complete characterization data sheet, including, e.g., XRD, NMR, FTIR, Raman, TGA, and DSC. From the reported results and discussion, it is concluded that HBB has potential in the field of chemical hydrogen storage given that both thermolytic and hydrolytic dehydrogenations were analyzed. In solid-state chemical hydrogen storage, it cannot be used in the pristine state (risk of explosion during dehydrogenation) but can be used for the synthesis of derivatives with improved dehydrogenation properties. In liquid-state chemical hydrogen storage, it can be studied for room-temperature dehydrogenation, but this requires the development of an active and selective metal-based catalyst. HBB is a thus a candidate for chemical hydrogen storage.

Status of radioactive waste management in Taiwan

International Nuclear Information System (INIS)

Huang, C.C.

1993-01-01

Taiwan started to generate nuclear power in 1977. The peaceful uses of nuclear energy generated radwaste. The major radwaste generators are nuclear power plants of Taiwan Power Company (Taipower). The other generators are the Institute of Nuclear Energy Research (INER), industry, medicine, agriculture, and education. Radwaste Administration (RWA), a subsidiary of Atomic Energy Council (AEC), is the regulatory body of radwaste in Taiwan. Radwaste management projects in Taiwan include: (1) construction of a Volume Reduction Center (VRC); (2) construction of a low-level radwaste transport ship; (3) construction of low-level waste final disposal facility; (4) construction of a spent fuel interim storage facility; (5) construction of spent fuel disposal facility. In the near future, final disposal of low-level waste is the most important work of both Taipower and RWA. Both organizations will put much more effort into this work

The development of radwaste policy and the Nirex programme

International Nuclear Information System (INIS)

Folger, M.

1993-01-01

Radwaste policy has had a chequered past in this country and although some of the blame has occasionally been laid at our door, three things sound be borne in mind, the context within which Nirex has worked and must continue to work, many of the ''myths'' about Nirex, and assurance that there is a well structured programme for stepwise investigation, and potential development, at Sellafield. Through that solution the waste producers will be paying real money to meet the requirement in the present generation. I aim to demonstrate that the United Kingdom (UK) programme for deep disposal is on track and compares well with the programmes which other nuclear nations have in place. Whatever the future investment decisions on nuclear power, government strategy does properly require safe disposal of the wastes we already have and the wastes which will come forward from the present nuclear programme. (Author)

Record of discussions in full wording: Hearing on the Ahaus storage facility for spent-fuel transport containers, June 21-29, 1983. Hearing concerning a project of the Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, Hannover, and STEAG Kernenergie GmbH, Essen, to establish a long-term storage facility for spent-fuel transport containers in Ahaus, Landkreis Borken, Nordrhein-Westfalen. Pt. 3

International Nuclear Information System (INIS)

1984-01-01

This third part of the record of the Ahaus Hearing presents the full wording of the discussions and statements concerning the topics of radiation protection and protection of the environment during operation of the planned facility. The problems considered can be summarized under the following keynotes: Wastes, effluents, environmental monitoring, radiological protection of workers, micro-climate, accidents and their impacts on the environment, site selection, development trends, physical protection, emergency service. The final debates are concerned with the radwaste disposal and management concept of the Federal German Government, with alternative methods or techniques for waste storage, and with the transport of radwaste. The hearing was organized by the PTB in its capacity as a licensing authority under atomic energy law, and this organisation will be responsible of examining and evaluating the objections stated with a view to the requirements set by section 6 of the Atomic Energy Act. (HSCH) [de

In situ evaluation of radwaste gamma activities

International Nuclear Information System (INIS)

Dulama, Cristian; Toma, Al.; Dobrin, R.; Pavelescu, Margarit

2003-01-01

There are certain limitations concerning the usage of standard source method for efficiency calibration of gamma-ray spectrometers measuring in extended geometry conditions. These limitations arise from the great diversity of forms and sizes of the objects which are to be measured during decommissioning and radioactive waste management activities. The INR - Pitesti operates a radioactive waste management facilities for both its own necessities and for providing external services. This facility is able to perform conditioning of liquid and solid wastes for interim storage disposal. During the conditioning operations there are certain stages when the radioactive measurement of the storage drums is demanded. We developed a gamma ray spectrometry equipment using a portable MCA Canberra INSPECTOR, a HPGe detector and an INR manufactured collimator. We are using a semiempirical method to calibrate the gamma ray spectrometer for such measurements. A program was written in Visual Basic language and includes a graphical interface for parameters input and data output. The input parameters are stored in text files, which can be loaded, modified or saved on disk as desired. The program was tested to establish the stability of MC simulation and the sensitivity to the input parameters. During the programming process it was possible to verify some code sequences and the results obtained showed that the model used was appropriate. To find out the optimal number of MC histories, which have to be modelled to obtain results of sufficient accuracy, the program was repeatedly run by changing only the number of histories. The relative deviation to the mean of the effective solid angle was calculated. The density of the source material as well as its composition can be changed by input. For comparison the efficiency calibration curves for sources materials having the same elemental composition but different densities ranging from 10 to 1000 kg/m 3 are drawn. The activities of the

Radwaste disposal strategy in Bangladesh: Present status and future trends

International Nuclear Information System (INIS)

Jalil, A.; Rabbani, G.

2002-01-01

Significant amounts of radioactive solid liquid and mixed wastes are generated in Bangladesh from peaceful uses of atomic energy including disused sealed sources and spent fuel from the research reactor and other hot laboratories in the country. At present these wastes are being collected, segregated, labeled and stored in an interim safe storage. A Central Waste Processing and Storage Facility (CWPSF) is fast nearing completion in the Atomic Energy Research Establishment (AERE), Savar campus where the TRIGA Research Reactor, Isotope Production Laboratory, 14 MeV Neutron Generator, 37 x 10 2 TBq commercial irradiator and other hot facilities are situated. A national strategy exists for the management and disposal of various types of radioactive wastes. Gaseous and liquid wastes are discharged in the environment in a controlled manner following delay decay procedure. Short-lived low and intermediate level wastes (SL-LILW) and disused/spent sealed radioactive sources are being stored in an interim storage before storage in the CWPSF following short treatment and conditioning. As regards their disposal, the currently preferred option is engineered near surface repository. Site investigation work has progressed far enough toward the goal of establishing a demonstration repository at AERE, Savar by the year 2010. For small amount of long-lived highly active problem wastes including spent radium needles and disused radioactive sources, the safe management option is a long-term storage in the CWPSF after conditioning and treatment. But this is not considered as a sustainable solution. The real emphasis is placed on the development of inexpensive disposal methods and availing regional/international repositories. (author)

Improvement of Radwaste Management System at Bilibinskaya NPP in the Far North Conditions - 13456

Energy Technology Data Exchange (ETDEWEB)

Fedorov, Denis; Adamovich, Dmitry; Savkin, Alexander [SUE SIA Radon, 2/14, 7th Rostovsky lane, Moscow, 119121 (Russian Federation)

2013-07-01

Since 2009 Bilibinskaya NPP is getting started to prepare to the decommissioning in the Far North conditions. Bilibinskaya NPP is located in the Far North of Russian Federation in Chukotka region. Since 1974 it operates 4 units EGP-6 with the capacity of 48 MW each. According to the contract, SIA Radon has performed the following works: - LLRW disposal safety analysis, - The technology of spent ion-exchanger and salt residue solidification is proposed, - Expected radwaste (till 2027) management economical analysis, - Technical proposals for LLRW and IRW management. (authors)

Handling of bulk solids theory and practice

CERN Document Server

Shamlou, P A

1990-01-01

Handling of Bulk Solids provides a comprehensive discussion of the field of solids flow and handling in the process industries. Presentation of the subject follows classical lines of separate discussions for each topic, so each chapter is self-contained and can be read on its own. Topics discussed include bulk solids flow and handling properties; pressure profiles in bulk solids storage vessels; the design of storage silos for reliable discharge of bulk materials; gravity flow of particulate materials from storage vessels; pneumatic transportation of bulk solids; and the hazards of solid-mater

Composite analysis for solid waste storage area 6

International Nuclear Information System (INIS)

Lee, D.W.

1997-09-01

The composite analysis (CA) provides an estimate of the potential cumulative impacts to a hypothetical future member of the public from the Solid Waste Storage Area 6 (SWSA 6) disposal operations and all of the other sources of radioactive material in the ground on the ORR that may interact with contamination originating in SWSA 6.The projected annual dose to hypothetical future member of the public from all contributing sources is compared to the primary dose limit of 100 mrem per year and a dose constraint of 30 mrem per year. Consistent with the CA guidance, dose estimates for the first 1000 years after disposal are emphasized for comparison with the primary dose limit and dose constraint.The current land use plan for the ORR is being revised, and may include a reduction in the land currently controlled by DOE on the ORR. The possibility of changes in the land use boundary is considered in the CA as part of the sensitivity and uncertainty analysis of the results, the interpretation of results, and the conclusions

Operation of radiation monitoring system in radwaste form test facility

International Nuclear Information System (INIS)

Ryu, Young Gerl; Kim, Ki Hong; Lee, Jae Won; Kwac, Koung Kil

1998-08-01

RWFTF (RadWaste Form Test Facility) must have a secure radiation monitoring system (RMS) because of having a hot-cell capable of handling high radioactive materials. And then in controlled radiation zone, which is hot-cell and its maintenance and operation / control room, area dose rate, radioactivities in air-bone particulates and stack, and surface contamination are monitored continuously. For the effective management such as higher utilization, maintenance and repair, the status of this radiation monitoring system, the operation and characteristics of all kinds of detectors and other parts of composing this system, and signal treatment and its evaluation were described in this technical report. And to obtain the accuracy detection results and its higher confidence level, the procedure such as maintenance, functional check and system calibration were established and appended to help the operation of RMS. (author). 6 tabs., 30 figs

Approach for Assessing Human Intrusion into a Radwaste Repository

International Nuclear Information System (INIS)

Cho, Dong Keun; Kim, Jung Woo; Jeong, Jong Tae; Baik, Min Hoon

2016-01-01

An approach to assess human intrusion into radwaste repository resulting from future human actions was proposed based on the common principals, requirements, and recommendations from IAEA, ICRP, and OECD/NEA, with the assumption that the intrusion occurs after loss of knowledge of the hazardous nature of the disposal facility. At first, the essential boundary conditions were derived on the basis of international recommendations, followed by overall approach to deal with inadvertent human intrusion. The essential premises were derived on the basis of international recommendations, followed by overall approach to deal with inadvertent human intrusion. The procedure to derive protective measures was also explained with four steps regarding how to derive safety framework, general measures, potential measures, and eventual protective measures on the basis of stylized scenarios. It is expected that the approach proposed in this study will be effectively used to reduce the potential for and/or consequence of human intrusion during entire processes of realization of disposal facility.

Liquid radwaste processing history at Fort Calhoun Nuclear Station

International Nuclear Information System (INIS)

Bilau, A.; Rutar, F.

1989-01-01

This report presents a historical perspective of liquid radwaste processing at the Fort Calhoun Unit 1 Nuclear Power Station, located in east central Nebraska. Of particular interest is the textual and graphical comparison of the operational implications of the various waste processing methods employed in the last ten years at the Fort Calhoun Station. Fort Calhoun's waste collection and processing systems are described in detail. These process systems include evaporation and solidification employing an in-plant drum solidification system. This solidification system was later replaced with vendor solidification services which solidified wastes in large liners. Ultimately, the plant converted its processing operation to ion exchange cleanup using ion selective media. The operational and economic impact of each of these process systems is discussed including overall costs, personnel exposure, capital expenditure requirements, burial volumes generated, maintenance and reliability assessments. Operational goals and performance criteria employed in the decision-making process for selection of the optimal technology are discussed, including the impact of various influent and effluent requirements

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Willis, N.P.; Triner, G.C.

1991-09-01

Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

Prediction of battery storage ageing and solid electrolyte interphase property estimation using an electrochemical model

Science.gov (United States)

Ashwin, T. R.; Barai, A.; Uddin, K.; Somerville, L.; McGordon, A.; Marco, J.

2018-05-01

Ageing prediction is often complicated due to the interdependency of ageing mechanisms. Research has highlighted that storage ageing is not linear with time. Capacity loss due to storing the battery at constant temperature can shed more light on parametrising the properties of the Solid Electrolyte Interphase (SEI); the identification of which, using an electrochemical model, is systematically addressed in this work. A new methodology is proposed where any one of the available storage ageing datasets can be used to find the property of the SEI layer. A sensitivity study is performed with different molecular mass and densities which are key parameters in modelling the thickness of the SEI deposit. The conductivity is adjusted to fine tune the rate of capacity fade to match experimental results. A correlation is fitted for the side reaction variation to capture the storage ageing in the 0%-100% SoC range. The methodology presented in this paper can be used to predict the unknown properties of the SEI layer which is difficult to measure experimentally. The simulation and experimental results show that the storage ageing model shows good accuracy for the cases at 50% and 90% and an acceptable agreement at 20% SoC.

Treatment of solid radioactive waste: Volume reduction of non-combustible waste

International Nuclear Information System (INIS)

Boehme, G.

1982-01-01

Press compaction is very common as for volume reduction of low level radioactive solid waste. In most cases a sorting step and if necessary a fragmenting step are desirable prior to the compaction process. Besides contamination-free loading and unloading techniques are important. Typical technical solutions for mixed solid waste handling and compacting equipment are shown and discussed by means of the lay-out drawings for a medium size radwaste compaction facility. A special technique can be applied if one has to compact active exhaust air filters in a hot cell. KfK has developed a remotely operated mobile equipment for this purpose. As for the nuclear fuel cycle considerable interest is existing in compacting spent fuel halls after fuel dissolution. In various European countries mechanical compaction and high temperature processes are therefore under development. These processes are described and the related equipment is discussed. (orig./RW)

The Assured Storage Integrated Management System: What is it and what will it cost?

International Nuclear Information System (INIS)

Kerr, T.A.; Newberry, W.F.

1996-01-01

The Assured Storage Integrated Management System for low-level radioactive waste as an alternative to traditional disposal is attracting favorable attention from many states, regulators, processors, and low-level radioactive waste generators. open-quotes Assured storageclose quotes is defined as a management system for safely isolating waste, while preserving options for its long-term management, through: robust, accessible facilities; planned preventive maintenance; and sureties adequate to address contingencies or implement future alternatives. Following introduction of the concept in RADWASTE Magazine, the Connecticut Hazardous Waste Management Service (among several others) requested a briefing on the idea. The Connecticut Hazardous Waste Management Service then requested that the National Low-Level Waste Management Program at the Idaho National Engineering Laboratory evaluate the life cycle costs of the Assured Storage Integrated Management System versus traditional disposal. Building on some of that work, this paper discusses the concept of an Assured Storage Integrated Management System for low-level radioactive waste as well as examines cost elements of the Assured Storage Integrated Management System in comparison to traditional disposal facilities. Further analyses conducted for the Connecticut study will more clearly define and quantify potential differences in life-cycle costs between the Assured Storage Integrated Management System and traditional disposal

Management of solid waste

Science.gov (United States)

Thompson, W. T.; Stinton, L. H.

1980-04-01

Compliance with the latest regulatory requirements addressing disposal of radioactive, hazardous, and sanitary solid waste criteria in the selection, design, and operation of solid waste management facilities. Due to the state of flux of these regulatory requirements from EPA and NRC, several waste management options were of solid waste. The current regulatory constraints and the design and operational requirements for construction of both storage and disposal facilities for use in management of DOE-ORO solid waste are highlighted. Capital operational costs are included for both disposal and storage options.

10CFR61 waste form conformance program for asphalted radwaste

International Nuclear Information System (INIS)

Kobran, M.J.; Guarini, W.J.

1987-01-01

With the enactment of Title 10, Code of Federal Regulation, Part 61, ''Licensing Requirements for Land Disposal of Radioactive Waste'' came the imposition of new requirements on licensees who dispose of radioactive waste via shallow land burial. Specifically, 10CFR61 both imposed a waste classification system requiring segregation of waste according to hazard and established waste performance characteristics required to enhance stability of the burial site. In order to provide licensees with guidance regarding implementation of applicable requirements of 10CFR61, the NRC low level Waste Licensing Branch issued two Technical Positions. To demonstrate compliance of asphalted radwaste produced with oxidized asphalt with 10CFR61 criteria and the NRC's Technical Position, five utilities combined resources. The five utilities sponsoring the program were Public Service Electric and Gas Company, Niagara Mohawk Power Company, Detroit Edison Company, New Hampshire Yankee, and Consumers Power Comany

Performance of a solid oxide fuel cell CHP system coupled with a hot water storage tank for single household

DEFF Research Database (Denmark)

Liso, Vincenzo; Zhao, Yingru; Yang, Wenyuan

2014-01-01

In this paper a solid oxide fuel cell (SOFC) system for cogeneration of heat and power integrated with a stratified heat storage tank is studied. Thermal stratification in the tank increases the heat recovery performance as it allows existence of a temperature gradient with the benefit of deliver......In this paper a solid oxide fuel cell (SOFC) system for cogeneration of heat and power integrated with a stratified heat storage tank is studied. Thermal stratification in the tank increases the heat recovery performance as it allows existence of a temperature gradient with the benefit...... of delivering hot water for the household and returning the coldest fluid back to SOFC heat recovery heat-exchanger. A model of the SOFC system is developed to determine the energy required to meet the hourly average electric load of the residence. The model evaluates the amount of heat generated and the amount...... of heat used for thermal loads of the residence. Two fuels are considered, namely syngas and natural gas. The tank model considers the temperature gradients over the tank height. The results of the numerical simulation is used to size the SOFC system and storage heat tank to provide energy for a small...

Tritium storage

International Nuclear Information System (INIS)

Hircq, B.

1989-01-01

A general synthesis about tritium storage is achieved in this paper and a particular attention is given to practical application in the Fusion Technology Program. Tritium, storage under gaseous form and solid form are discussed (characteristics, advantages, disadvantages and equipments). The way of tritium storage is then discussed and a choice established as a function of a logic which takes into account the main working parameters

Integrated Treatment and Storage Solutions for Solid Radioactive Waste at the Russian Shipyard Near Polyarny

International Nuclear Information System (INIS)

Griffith, A.; Engoy, T.; Endregard, M.; Busmundrud, O.; Schwab, P.; Nazarian, A.; Krumrine, P.; Backe, S.; Gorin, S.; Evans, B.

2002-01-01

Russian Navy Yard No. 10 (Shkval), near the city of Murmansk, has been designated as the recipient for Solid Radioactive Waste (SRW) pretreatment and storage facilities under the Arctic Military Environmental Cooperation (AMEC) Program. This shipyard serves the Northern Fleet by servicing, repairing, and dismantling naval vessels. Specifically, seven nuclear submarines of the first and second generation and Victor class are laid up at this shipyard, awaiting defueling and dismantlement. One first generation nuclear submarine has already been dismantled there, but recently progress on dismantlement has slowed because all the available storage space is full. SRW has been placed in metal storage containers, which have been moved outside of the actual storage site, which increases the environmental risks. AMEC is a cooperative effort between the Russian Federation, Kingdom of Norway and the United States. AMEC Projects 1.3 and 1.4 specifically address waste treatment and storage issues. Various waste treatment options have been assessed, technologies selected, and now integrated facilities are being designed and constructed to address these problems. Treatment technologies that are being designed and constructed include a mobile pretreatment facility comprising waste assay, segregation, size reduction, compaction and repackaging operations. Waste storage technologies include metal and concrete containers, and lightweight modular storage buildings. This paper focuses on the problems and challenges that are and will be faced at the Polyarninsky Shipyard. Specifically, discussion of the waste quantities, types, and conditions and various site considerations versus the various technologies that are to be employed will be provided. A systems approach at the site is being proposed by the Russian partners, therefore integration with other ongoing and planned operations at the site will also be discussed

Reduction of radioactive waste volumes by using supercompaction technique

International Nuclear Information System (INIS)

Santos, John Wagner A.; Lima, Sandro Leonardo N. de

2007-01-01

The Radioactive Waste Management Program from ELETRONUCLEAR comprises the use of techniques and technologies to reduce the volumes of processed radwaste, which aims to improve the storage capacity and also assure the protection for the environment, as part of ELETRONUCLEAR's business strategy. The Angra site stores radwaste in temporary storage facilities, named Store number 1 and Store number 2, which are routinely managed and surveyed periodically by the ELETRONUCLEAR's Radiological Protection Division and submitted to frequent CNEN inspections. Medium level and low level radwastes are stored on those storage facilities. In January 2005, ELETRONUCLEAR decided to realize the Supercompaction of drums with compacted radwaste, mostly from Angra 1 and a little from Angra 2. By that time, the Store 1 was near to achieve its nominal capacity; this situation demanded a prompt response, and the chosen option was to proceed the supercompaction by using a mobile supercompactor unit. In April, 2006, two thousand and twenty seven drums of 200 liters were supercompacted at the plant site, and as a result, the initial storage area became sufficient to store drums for about five more years of operation. The supercompaction process is achieved by using a hydraulic press with extra high force. The pellets (crashed drums) were placed inside a special metallic box with 2500 liters of capacity (the overpack). This operation produced 128 full boxes, varying from 12 to 19 pellets inside each box, and the boxes were stored inside the Store 1. (author)

Solid-state supercapacitors with ionic liquid gel polymer electrolyte based on poly (3, 4-ethylenedioxythiophene), carbon nanotubes, and metal oxides nanocomposites for electrical energy storage

Science.gov (United States)

Obeidat, Amr M.

Clean and renewable energy systems have emerged as an important area of research having diverse and significant new applications. These systems utilize different energy storage methods such as the batteries and supercapacitors. Supercapacitors are electrochemical energy storage devices that are designed to bridge the gap between batteries and conventional capacitors. Supercapacitors which store electrical energy by electrical double layer capacitance are based on large surface area structured carbons. The materials systems in which the Faradaic reversible redox reactions store electrical energy are the transition metal oxides and electronically conducting polymers. Among the different types of conducting polymers, poly (3, 4- ethylenedioxythiophene) (PEDOT) is extensively investigated owing to its chemical and mechanical stability. Due to instability of aqueous electrolytes at high voltages and toxicity of organic electrolytes, potential of supercapacitors has not been fully exploited. A novel aspect of this work is in utilizing the ionic liquid gel polymer electrolyte to design solid-state supercapacitors for energy storage. Various electrochemical systems were investigated including graphene, PEDOT, PEDOT-carbon nanotubes, PEDOT-manganese oxide, and PEDOT-iron oxide nanocomposites. The electrochemical performance of solid-state supercapacitor devices was evaluated based on cyclic voltammetry (CV), charge-discharge (CD), prolonged cyclic tests, and electrochemical impedance spectroscopy (EIS) techniques. Raman spectroscopy technique was also utilized to analyze the bonding structure of the electrode materials. The graphene solid-state supercapacitor system displayed areal capacitance density of 141.83 mF cm-2 based on high potential window up to 4V. The PEDOT solid-state supercapacitor system was synthesized in acetonitrile and aqueous mediums achieving areal capacitance density of 219.17 mF cm-2. The hybrid structure of solid-state supercapacitors was also

Liquid radwaste treatment by microfiltration, ultrafiltration and reverse osmosis

International Nuclear Information System (INIS)

Dulama, M.; Deneanu, N.; Popescu, I.V.

2001-01-01

Radioactive liquid waste processing is an integral part of any facility involved in nuclear power generation, radioisotope production, research and development, decontamination or other aspects of nuclear energy. The aqueous liquid radwastes from the decontamination center are currently treated by the membrane plant. Generally, the liquid waste streams are effectively volume-reduced by a combination of continuous crossflow microfiltration (MF), spiral wound reverse osmosis (SWRO) and tubular reverse osmosis membrane technologies. Backwash chemical cleaning wastes from the membrane plant are further volume-reduced by evaporation. The concentrate from the membrane plant is ultimately immobilized with bitumen. We performed experiments using two simulated waste solution; secondary waste from the decontamination process with POD (Permanganate Oxidation Decontamination) solution and secondary waste from decontamination with CAN-DECON solution. The experimental tests have been done with cellulose acetate (CA) membrane and polysulfonate (PSF) membrane manufactured at Research Center for Macromolecular Materials and Membranes Bucharest and with Millipore membrane type VS 0.025 μm. A schematic of the laboratory-scale test facility is presented

Potential of Reversible Solid Oxide Cells as Electricity Storage System

Directory of Open Access Journals (Sweden)

Paolo Di Giorgio

2016-08-01

Full Text Available Electrical energy storage (EES systems allow shifting the time of electric power generation from that of consumption, and they are expected to play a major role in future electric grids where the share of intermittent renewable energy systems (RES, and especially solar and wind power plants, is planned to increase. No commercially available technology complies with all the required specifications for an efficient and reliable EES system. Reversible solid oxide cells (ReSOC working in both fuel cell and electrolysis modes could be a cost effective and highly efficient EES, but are not yet ready for the market. In fact, using the system in fuel cell mode produces high temperature heat that can be recovered during electrolysis, when a heat source is necessary. Before ReSOCs can be used as EES systems, many problems have to be solved. This paper presents a new ReSOC concept, where the thermal energy produced during fuel cell mode is stored as sensible or latent heat, respectively, in a high density and high specific heat material and in a phase change material (PCM and used during electrolysis operation. The study of two different storage concepts is performed using a lumped parameters ReSOC stack model coupled with a suitable balance of plant. The optimal roundtrip efficiency calculated for both of the configurations studied is not far from 70% and results from a trade-off between the stack roundtrip efficiency and the energy consumed by the auxiliary power systems.

Radioactive Solid Waste Storage and Disposal at Oak Ridge National Laboratory, Description and Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Bates, L.D.

2001-01-30

Oak Ridge National Laboratory (ORNL) is a principle Department of Energy (DOE) Research Institution operated by the Union Carbide Corporation - Nuclear Division (UCC-ND) under direction of the DOE Oak Ridge Operations Office (DOE-ORO). The Laboratory was established in east Tennessee, near what is now the city of Oak Ridge, in the mid 1940s as a part of the World War II effort to develop a nuclear weapon. Since its inception, disposal of radioactively contaminated materials, both solid and liquid, has been an integral part of Laboratory operations. The purpose of this document is to provide a detailed description of the ORNL Solid Waste Storage Areas, to describe the practice and procedure of their operation, and to address the health and safety impacts and concerns of that operation.

Design and construction of engineering test device of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author describes designs of main un-standard devices, monitoring system and safety system, as well as construction of the engineering system devices for a multi-purpose radwaste incineration system. Un-standard devices include waste crusher, pyrolysis furnace, incinerator furnace, cool stream dilution device and bag filter, etc. The monitoring system mainly includes industrial controlled computer, supported by conventional electrical equipment and instruments. Designs of system safety takes account of containment of radioactive materials fire-prevention, explosion prevention, anti-corrosion, redundance and reservation, emergency system, controlling and electric safety system, etc. Results show that main technological system remains good airtight with leakage ratio at 0.67%

WasteChem Corporation's Volume Reduction and Solidification (VRS) system for low-level radwaste treatment: Final report

International Nuclear Information System (INIS)

1988-01-01

Since 1965, low and medium level radwastes from nuclear power stations, reprocessing plants and nuclear research centers have been stabilized using the Volume Reduction and Solidification (VRS) system. The VRS system uses an extruder/evaporator to evaporate the liquids from waste influents, while simultaneously incorporating the remaining radioactive solids in an asphalt binder. In the period 1965 to 1986 a minimum of 700,000 cubic feet of wastes have been processed with the VRS system. This report provides current operating data from various systems including the volume reduction factors achieved, and the progress of start-ups in the US. The report also provides previously unpublished experience with mixed wastes including uranium raffinate and nitrate-bearing sludges from surface impoundments. VRS systems in the US are currently operating at the Palisades and Hope Creek nuclear stations. These systems produce a variety of waste types including boric acid, bead resin, sodium sulfate and powdered resins. There are three start-ups of VRS systems scheduled in the US in 1987. These systems are at Fermi 2, Seabrook, and Nine Mile Point 2. Overseas, the startup of new systems continues with three VRS process lines coming on-line at the LaHague Reprocessing Center in France in 1986 and a start-up scheduled for 1987 at the Laguna Verde plant in Mexico. The US systems are operating continuously and with little required maintenance. Data on maintenance and the operator exposure are provided in this report. 6 refs., 11 figs., 13 tabs

Description of INR-Pitesti own strategy for on site radioactive solid waste storage concepts

International Nuclear Information System (INIS)

Tuturici, I.L.; Toma, V.; Bujoreanu, D.; Prava, M.

1993-01-01

The Post Irradiation Examination Laboratory (PIEL) produces and will produce the majority of institute's alpha-contaminated solid radioactive waste, generated by the process of examination of irradiated CANDU-600 type nuclear fuel. The wastes will be divided into three categories: low-level, medium-level, and high-level general process trash (LLGPT, MLGPT, and HLGPT). The paper describes the strategy adopted for immobilization, conditioning and on-site long-term storage of these wastes. The proposed strategy is based on the best experience acquired by other nuclear centers, confronted with same problems. (Author)

Solid solution barium–strontium chlorides with tunable ammonia desorption properties and superior storage capacity

DEFF Research Database (Denmark)

Bialy, Agata; Jensen, Peter Bjerre; Blanchard, Didier

2015-01-01

with spray drying and in situ thermogravimetric and structural characterization, we synthesize a range of new, stable barium-strontium chloride solid solutions with superior ammonia storage densities. By tuning the barium/strontium ratio, different crystallographic phases and compositions can be obtained...... with different ammonia ab- and desorption properties. In particular it is shown, that in the molar range of 35–50% barium and 65–50% strontium, stable materials can be produced with a practically usable ammonia density (both volumetric and gravimetric) that is higher than any of the pure metal halides...

Management of solid waste

International Nuclear Information System (INIS)

Thompson, W.T.; Stinton, L.H.

1980-01-01

Compliance with the latest regulatory requirements addressing disposal of radioactive, hazardous, and sanitary solid waste requires the application of numerous qualitative and quantitative criteria in the selection, design, and operation of solid waste management facilities. Due to the state of flux of these regulatory requirements from EPA and NRC, several waste management options were identified as being applicable to the management of the various types of solid waste. This paper highlights the current regulatory constraints and the design and operational requirements for construction of both storage and disposal facilities for use in management of DOE-ORO solid waste. Capital and operational costs are included for both disposal and storage options

Management of solid waste

International Nuclear Information System (INIS)

Thompson, W.T.; Stinton, L.H.

1980-01-01

Compliance with the latest regulatory requirements addressing disposal of radioactive, hazardous, and sanitary solid waste requires the application of numerous qualitative and quantitative criteria in the selection, design, and operation of solid waste management facilities. Due to the state of flux of these regulatory requirements from EPA and NRC several waste management options were identified as being applicable to the management of the various types of solid waste. This paper highlights the current regulatory constraints and the design and operational requirements for construction of both storage and disposal facilities for use in management of DOE-ORO solid waste. Capital and operational costs are included for both disposal and storage options

Combustion/absorption process for the separation of {sup 14}C and {sup 3}H in radwastes released from nuclear power plants and their analysis

Energy Technology Data Exchange (ETDEWEB)

Ko, Young Gun, E-mail: ygko@kaeri.re.kr; Kim, Chang-Jong; Cho, Young Hyun; Chung, Kun Ho; Kang, Mun Ja

2017-06-05

Highlights: • {sup 14}CO{sub 2} and THO were produced by the combustion of radwaste samples. • The radioactivity of {sup 14}CO{sub 2} and THO absorbed sorbents were measured by LSC. • The CO{sub 2} absorption in the {sup 14}C sorbent was analyzed using by FT-IR and a rheometer. • The temperature and viscosity of the CO{sub 2} absorbed {sup 14}C sorbent was investigated. - Abstract: Radioactivities of {sup 3}H and {sup 14}C in spent radioactive ion exchange resins and spent radioactive lubricant oils released from nuclear power plants, has been determined using a combustion and sorption method (combustion method). The liquid scintillation counting (LSC) spectra showed that the interference of other radionuclides has not significantly affected the determination of radioactivities of {sup 3}H and {sup 14}C in the radwaste samples. The chemical structure of {sup 14}CO{sub 2}, which originated from the combustion of radwastes, trapped {sup 14}C sorbent has been investigated using Fourier transform infrared spectroscopy (FT-IR). FT-IR study showed interesting results that peaks for uncoupled CO{sub 2} and carbonic amide appeared at FT-IR spectra of CO{sub 2} high-absorbed {sup 14}C sorbents, while the peak for carbamate was only observed at the spectra of CO{sub 2} low-absorbed sorbents. During the CO{sub 2} sorption in {sup 14}C sorbent, temperature and viscosity of the sorbent increased owing to decrease of enthalpy and increase of apparent molecular weight of the sorbent caused by the bonding formation between sorbent molecules.

Continuous solid-state phase transitions in energy storage materials with orientational disorder – Computational and experimental approach

International Nuclear Information System (INIS)

Singh, Harpreet; Talekar, Anjali; Chien, Wen-Ming; Shi, Renhai; Chandra, Dhanesh; Mishra, Amrita; Tirumala, Muralidhar; Nelson, Daryl J.

2015-01-01

We report on TES (thermal energy storage) in new CT (continuous phase transitions) in multicomponent tetrahederally configured (orientationally disordered) crystals of NPG-neopentylglycol-C 5 H 12 O 2 , PG-pentaglycerine-C 5 H 12 O 3 , and PE-pentaerythritol-C 5 H 12 O 4 . This discovery is applicable in thermal energy storage in many systems which do not require conventional isothermal first-order phase transition energy storage. The above compounds exhibit polymorphs of orientationally disordered phases in which O–H…O bond rotation around the C–C bond stores significant amount of energy; for example, in PE 41.26 kJ/mol are absorbed isothermally during solid–solid transitions. In this paper we show, anisothermal continuous phase transitions (CT), due to compositional changes with changes in temperature, associated with a measurable amount of energy, not reported earlier. The correlation of phase stability regions in pseudo-binaries, calculated from ternary NPG–PG–PE phase diagrams, is validated by experimental ternary DSC (differential scanning calorimetry) and in-situ x-ray diffraction data. We established equations for determining the CT in a temperature range, and their respective enthalpies of transitions for any composition of the ternaries. Thermodynamic calculations of the Gibbs energies of the solution phases are modeled as substitutional solid solutions, in which the excess Gibbs energies are expressed by the Redlich–Kister–Muggianu polynomial. There is excellent agreement between the experimental and CALPHAD calculated data. - Highlights: • Continuous phase transition (CT) thermal energy storage in organic ternary system. • Anisothermal temperature ramping leads to CT transitions as per lever rule. • Orientationally disordered phases store energy in O–H…O bond rotation/oscillation. • Validated calculated data with measured thermodynamic properties in ternary system. • Used CALPHAD methodology to calculate Gibbs energies of

Enhanced electrocaloric analysis and energy-storage performance of lanthanum modified lead titanate ceramics for potential solid-state refrigeration applications.

Science.gov (United States)

Zhang, Tian-Fu; Huang, Xian-Xiong; Tang, Xin-Gui; Jiang, Yan-Ping; Liu, Qiu-Xiang; Lu, Biao; Lu, Sheng-Guo

2018-01-10

The unique properties and great variety of relaxer ferroelectrics make them highly attractive in energy-storage and solid-state refrigeration technologies. In this work, lanthanum modified lead titanate ceramics are prepared and studied. The giant electrocaloric effect in lanthanum modified lead titanate ceramics is revealed for the first time. Large refrigeration efficiency (27.4) and high adiabatic temperature change (1.67 K) are achieved by indirect analysis. Direct measurements of electrocaloric effect show that reversible adiabatic temperature change is also about 1.67 K, which exceeds many electrocaloric effect values in current direct measured electrocaloric studies. Both theoretical calculated and direct measured electrocaloric effects are in good agreements in high temperatures. Temperature and electric field related energy storage properties are also analyzed, maximum energy-storage density and energy-storage efficiency are about 0.31 J/cm 3 and 91.2%, respectively.

Vandellos 1 NPP. Dismantling at the level 1

International Nuclear Information System (INIS)

Pla, E.; Perez Pallares, J.

1998-01-01

Because of the fire in a main turbogenerator in October 1989, the Spanish Ministry of Industry ordered the definitive shutdown of Vandellos 1 NPP. The tasks allowed to the owner in the Ministerial Order were: the reactor defueling, the operation radwaste conditioning. The size of the reactor core needed to prepare an adequate defueling plan in order to prevent the potential reactivity oscillations and ensure the refrigeration of the nuclear fuel remaining in the core. The operation radwastes were divided in four types, according to the conditioning method: the low level solid radwaste, the irradiated metallic materials, the resins and zeolites used for decontaminating the liquid effluents, the radwaste stored in three graphite silos. The low level solid radwastes were stored during operation in drums of 220 litres. Recently they were compacted at a pressure of 40 tones before to be shipped to en ENRESA disposal. The irradiated metallic materials are, essentially, some parts of the refuelling machine. For deactivating the liquid effluents, Vandellos 1 used both organic resins and zeolites. The presence of zeolites helps the cementation, but its rough surface makes difficult to flow in the pipes of the cementation plant. 35 m 3 of this mixture have been conditioned into 670 drums of 220 liters. Vandellos 1 has three silos designed to store the graphite sleeves (reactor fuel support). In the silo number 1 some other radwastes were stored, as low level solid radwastes and two fuel elements. An international request for tenders was made in order to undertake the extraction and conditioning all these radwastes. The project was awarded to the Spanish/French Consortium EQUIPOS NUCLEARES-FRAMATOME. The achievement of the graphite silos project needed to design specific devices for separating irradiated wires from graphite, and searching and extracting two fuel elements jumbled up with the graphite sleeves. The spent fuel ponds have been emptied and its internals confined

Disposal of low-level radioactive wastes. Plasma furnace for the treatment of low-level radwastes in Switzerland. Plasma furnace for the treatment of low-level radwastes in Switzerland

International Nuclear Information System (INIS)

Hoffelner, W.; Mueller, T.; Fuenfschilling, M.R.; Jacobi, A.; Eschenbach, R.; Lutz, H.R.; Vuilleumier, C.

1994-01-01

The treatment method to be applied consists of thermal decomposition and vitrification. The facility to be constructed at the Zwilag is a plasma-arc furnace, and planning activities are heading towards the final phase. There will be only this one facility for treating in only one process step solid, mixed wastes, liquid wastes, sludges, metals, and inorganic wastes, producing vitrified waste packages ready for ultimate storage as 200-l waste drums. The main features of the plasma-arc furnace are explained. (orig./HP) [de

Safety device and machine system of nuclear power plant

International Nuclear Information System (INIS)

1978-10-01

It introduces principle and kinds of heat power including heat balance and nuclear power. It explains a lot of technical terms about the nuclear power system, which are primary loop, reactor, steam generator, primary coolant pump and pressurizer in PWR, chemical and volume control system, component cooling system, safety injection system, and spent fuel cooling and storage system in auxiliary system, liquid solid and gaseous waste disposal system in radwaste disposal, gland sealing system, turbine instrumentation, turning gear, hydrogen cooling system, condenser, feedwater heater, degenerate heater, auxiliary heat exchanger, centrifugal pump, rotary reciprocating and tank and pressure vessel.

Localized corrosion of metallic materials and γ radiation effects in passive layers under simulated radwaste repository conditions. Final report

International Nuclear Information System (INIS)

Schultze, J.W.; Kudelka, S.; Michaelis, A.; Schweinsberg, M.; Thies, A.

1996-02-01

The task of the project was to simulate the conditions in a radwaste repository and to perform local analyses in order to detect the critical conditions and material susceptibilities leading to localized corrosion of materials. The information thus obtained was to yield more precise data on the long-term stability of materials for the intended purpose, in order to be able to appropriately select or optimize the materials (Ti, TiO.2Pd, Hastelloy C4, fine-grained structural steel). A major aspect to be examined was natural inhomogeneities of the electrode surfaces, as determined by the grain structure of the selected materials. Thus a laterally inhomogeneous composition in the welded zone induces an inhomogeneous current distribution, and hence strong susceptibility to localized corrosion. This effect was to be quantified, and the localized corrosion processes had to be identified by means of novel, electrochemical methods with a resolution power of μm. The investigations were to be made under conditions as near to practice as possible, for instance by simulating radwaste repository conditions and performing measurements at elevated temperatures (170 C) in an autoclave. Another task was to examine the radiation effects of γ radiation on passive layers, and describe the possible modifications induced by recrystallisation, photocorrosion, or oxide formation. (orig./MM) [de

Solid solution barium–strontium chlorides with tunable ammonia desorption properties and superior storage capacity

Energy Technology Data Exchange (ETDEWEB)

Bialy, Agata [Amminex Emissions Technology A/S, Gladsaxevej 363, 2860 Soeborg (Denmark); Jensen, Peter B. [Department of Energy Conversion and Storage, Technical University of Denmark, Frederiksborgvej 399, DK-4000 Roskilde (Denmark); Center for Atomic-scale Materials Design, Department of Physics, Technical University of Denmark, Fysikvej 311, DK-2800 Kgs. Lyngby (Denmark); Blanchard, Didier [Department of Energy Conversion and Storage, Technical University of Denmark, Frederiksborgvej 399, DK-4000 Roskilde (Denmark); Vegge, Tejs, E-mail: teve@dtu.dk [Department of Energy Conversion and Storage, Technical University of Denmark, Frederiksborgvej 399, DK-4000 Roskilde (Denmark); Quaade, Ulrich J., E-mail: ujq@amminex.com [Amminex Emissions Technology A/S, Gladsaxevej 363, 2860 Soeborg (Denmark)

2015-01-15

Metal halide ammines are very attractive materials for ammonia absorption and storage—applications where the practically accessible or usable gravimetric and volumetric storage densities are of critical importance. Here we present, that by combining advanced computational materials prediction with spray drying and in situ thermogravimetric and structural characterization, we synthesize a range of new, stable barium-strontium chloride solid solutions with superior ammonia storage densities. By tuning the barium/strontium ratio, different crystallographic phases and compositions can be obtained with different ammonia ab- and desorption properties. In particular it is shown, that in the molar range of 35–50% barium and 65–50% strontium, stable materials can be produced with a practically usable ammonia density (both volumetric and gravimetric) that is higher than any of the pure metal halides, and with a practically accessible volumetric ammonia densities in excess of 99% of liquid ammonia. - Graphical abstract: Thermal desorption curves of ammonia from Ba{sub x}Sr{sub (1−x)}Cl{sub 2} mixtures with x equal to 0.125, 0.25 and 0.5 and atomic structure of Sr(NH{sub 3}){sub 8}Cl{sub 2}. - Highlights: • Solid solutions of strontium and barium chloride were synthesized by spray drying. • Adjusting molar ratios led to different crystallographic phases and compositions. • Different molar ratios led to different ammonia ab-/desorption properties. • 35–50 mol% BaCl{sub 2} in SrCl{sub 2} yields higher ammonia density than any other metal halide. • DFT calculations can be used to predict properties of the mixtures.

Contact expert group for international radwaste projects. Fourth meeting

International Nuclear Information System (INIS)

1997-06-01

The Contact Expert Group for International Radwaste Projects is the result of an IAEA seminar on ''International Co-operation on Nuclear Waste Management in the Russian Federation'', 15-17 May 1995, that was requested and sponsored by the Nordic countries. In two working groups at the Seminar, participants from the Russian Federation and 17 countries and international organizations co-operating with the Russian Federation in waste management projects recognized the need for setting up a contact group of experts to assist in co-ordinating their efforts. Such co-ordination would help avoid redundancy and duplication of effort, assure that priority needs were made known to the international community, and provide points of contact to facilitate co-operation. This report is a compilation of the 4. CEG meeting materials, both prepared by the CEG Secretariat and presented by meeting's participants. The materials discussed by the CEG and subsequently modified are presented in the finally approved version. As in the case of previous similar reports, the documentation presented was just compiled without any editing and thus should be considered only as ''working proceedings'' of the meeting

Low level radwaste packaging: why not cement

International Nuclear Information System (INIS)

Wilson, R.B.

1978-01-01

Over the past several years many words have been expended in a quest to define a variety of competing radioactive waste immobilization technologies. With the more recent recognition of the technical pitfalls of urea-formaldehyde (UF) a liquid chemical binder considered as optimum less than two years ago, utilities, architect-engineers and systems vendors find themselves in a technology void, awaiting the inevitable breakthrough which will identify the perfect immobilization agent. The culmination of these pressures has brought about the introduction of new immobilization technologies including: one which offers both volume reduction and immobilization in yet another new binder agent; the costly development of highly sophisticated volume reduction systems, the highly-concentrated products from which may pose as-yet unknown immobilization problems; and, the marketing of several new more expensive liquid chemical binders which are reputed to have eliminated the kinds of problems associated with urea-formaldehyde. This paper addresses these issues by coming full circle and arriving back at the initial approach employed for low level radwaste immobilization, the use of cement. Based on an evaluation of the three principal competing immobilization approaches, liquid chemical, bitumen and cement, the merits and drawbacks of each is examined. As will be described, an objective assessment of these competing technologies has resulted in a somewhat surprising conclusion that, while none of the approaches is without disadvantages, cement can be shown to offer the most reliable, versatile long-term solution to today's needs

Radiochemical approaches to the migration of elements from a radwaste repository

International Nuclear Information System (INIS)

Guillaumont, R.

1993-01-01

Underground high-level or intermediary-level alpha radwaste repositories will contain tons to hundreds of tons of anthropogenic elements. It is predicted that the release of the elements into the far field will be mainly dependent upon the 'solubilities', sums of the concentrations of soluble species and colloidal/pseudo colloidal forms, of expected near field compounds. On the other hand, safety assessments, based on computation models of migration, show that elements in the discharged water into the biosphere will be at tracer level, or at least, at trace levels. Kinetic and thermodynamic aspects of the processes in which elements will be involved during their migration are discussed together with the change in their concentrations, over several orders of magnitude. It is shown that special attention must be given to predict the behaviour of the elements in the far field from what we know from classical chemistry, and that more experimental data must be obtained to improve the models. (author). 31 refs., 5 figs., 4 tabs

Radiological impact of the storage of solid wastes from coal-fored power plants

International Nuclear Information System (INIS)

Hugon, J.; Caries, J.C.; Patellis, A.; Roussel, S.

1983-01-01

Solid wastes from the coal-fired power plant of GARDANNE are stared in piles, outside near the unit. The coal contains a high proportion of sulfur, so the storage pile is a very reducing middle. The radium coming from the ore, which is mostly retained in the bottom ashes, could then be solubilized again, by physicochemical processes, leached by the rain and reach the nearest population through the food-chain pathways. Leaching-tests where made with three sampling series. The measurement datas show that only 15% of the 226 Ra can be solved and that the Ra 226 observed concentrations in vegetal samples come mostly from transportation of dust by the wind [fr

Combined Solid State and High Pressure Hydrogen Storage

DEFF Research Database (Denmark)

Grube, Elisabeth; Jensen, Torben René

Presented at The First European Early Stage Researcher's Conference on Hydrogen Storage in Belgrade, Serbia.......Presented at The First European Early Stage Researcher's Conference on Hydrogen Storage in Belgrade, Serbia....

A new class of solid oxide metal-air redox batteries for advanced stationary energy storage

Science.gov (United States)

Zhao, Xuan

Cost-effective and large-scale energy storage technologies are a key enabler of grid modernization. Among energy storage technologies currently being researched, developed and deployed, rechargeable batteries are unique and important that can offer a myriad of advantages over the conventional large scale siting- and geography- constrained pumped-hydro and compressed-air energy storage systems. However, current rechargeable batteries still need many breakthroughs in material optimization and system design to become commercially viable for stationary energy storage. This PhD research project investigates the energy storage characteristics of a new class of rechargeable solid oxide metal-air redox batteries (SOMARBs) that combines a regenerative solid oxide fuel cell (RSOFC) and hydrogen chemical-looping component. The RSOFC serves as the "electrical functioning unit", alternating between the fuel cell and electrolysis mode to realize discharge and charge cycles, respectively, while the hydrogen chemical-looping component functions as an energy storage unit (ESU), performing electrical-chemical energy conversion in situ via a H2/H2O-mediated metal/metal oxide redox reaction. One of the distinctive features of the new battery from conventional storage batteries is the ESU that is physically separated from the electrodes of RSOFC, allowing it to freely expand and contract without impacting the mechanical integrity of the entire battery structure. This feature also allows an easy switch in the chemistry of this battery. The materials selection for ESU is critical to energy capacity, round-trip efficiency and cost effectiveness of the new battery. Me-MeOx redox couples with favorable thermodynamics and kinetics are highly preferable. The preliminary theoretical analysis suggests that Fe-based redox couples can be a promising candidate for operating at both high and low temperatures. Therefore, the Fe-based redox-couple systems have been selected as the baseline for this

Facility for low-level solid waste treatment

International Nuclear Information System (INIS)

Vicente, R.; Miyamoto, H.

1987-01-01

A facility for low-level solid waste compaction, encapsulation and storage is described. Solid wastes are compacted in 200 l drums and stored over concrete platforms covered with canvas, for decay or for interim storage before transport to the final disposal site. (Author) [pt

Performance Improvement of V-Fe-Cr-Ti Solid State Hydrogen Storage Materials in Impure Hydrogen Gas.

Science.gov (United States)

Ulmer, Ulrich; Oertel, Daria; Diemant, Thomas; Bonatto Minella, Christian; Bergfeldt, Thomas; Dittmeyer, Roland; Behm, R Jürgen; Fichtner, Maximilian

2018-01-17

Two approaches of engineering surface structures of V-Ti-based solid solution hydrogen storage alloys are presented, which enable improved tolerance toward gaseous oxygen (O 2 ) impurities in hydrogen (H 2 ) gas. Surface modification is achieved through engineering lanthanum (La)- or nickel (Ni)-rich surface layers with enhanced cyclic stability in an H 2 /O 2 mixture. The formation of a Ni-rich surface layer does not improve the cycling stability in H 2 /O 2 mixtures. Mischmetal (Mm, a mixture of La and Ce) agglomerates are observed within the bulk and surface of the alloy when small amounts of this material are added during arc melting synthesis. These agglomerates provide hydrogen-transparent diffusion pathways into the bulk of the V-Ti-Cr-Fe hydrogen storage alloy when the remaining oxidized surface is already nontransparent for hydrogen. Thus, the cycling stability of the alloy is improved in an O 2 -containing hydrogen environment as compared to the same alloy without addition of Mm. The obtained surface-engineered storage material still absorbs hydrogen after 20 cycles in a hydrogen-oxygen mixture, while the original material is already deactivated after 4 cycles.

Thermal energy storage for solar power generation - State of the art

Science.gov (United States)

Shukla, K. N.

1981-12-01

High temperature storage for applications in solar-thermal electric systems is considered. Noting that thermal storage is in either the form of latent, sensible or chemically stored heat, sensible heat storage is stressed as the most developed of the thermal storage technologies, spanning direct heating of a storage medium from 120-1250 C. Current methods involve solids, packed beds, fluidized beds, liquids, hot water, organic liquids, and inorganic liquids and molten salts. Latent heat storage comprises phase-change materials that move from solid to liquid with addition of heat and liquid to solid with the removal of heat. Metals or inorganic salts are candidates, and the energy balances are outlined. Finally, chemical heat storage is examined, showing possible high energy densities through catalytic, thermal dissociation reactions.

Preparation, characterization and thermal properties of PMMA/n-heptadecane microcapsules as novel solid-liquid microPCM for thermal energy storage

International Nuclear Information System (INIS)

Sari, Ahmet; Alkan, Cemil; Karaipekli, Ali

2010-01-01

This study is focused on the preparation, characterization and thermal properties of microencapsulated n-heptadecane with polymethylmethacrylate shell. The PMMA/heptadecane microcapsules were synthesized as novel solid-liquid microencapsulated phase change material (microPCMs) by emulsion polymerization method. The chemical and thermal characterization of the microPCMs were investigated using scanning electron microscopy (SEM), differential scanning calorimetry (DSC) and thermogravimetry analysis (TGA). The diameters of microPCMs were found in the narrow range (0.14-0.40 μm) under the stirring speed of 2000 rpm. The spherical surfaces of microPCMs were smooth and compact. The DSC results show that microPCMs have good energy storage capacity. Thermal cycling test showed that the microPCMs have good thermal reliability with respect to the changes in their thermal properties after repeated 5000 thermal cycling. TGA analyses also indicated that the microPCMs degraded in three steps and have good thermal stability. Based on all results, it can be considered that the PMMA/heptadecane microcapsules as novel solid-liquid microPCMs have good energy storage potential.

In situ grouting of low-level burial trenches with a cement-based grout

International Nuclear Information System (INIS)

Francis, C.W.; Spalding, B.P.

1991-01-01

A restoration technology being evaluated for use in the closure of one of the low-level radwaste burial grounds at Oak Ridge National Laboratory (ORNL) is trench stabilization using a cement-based grout. To demonstrate the applicability and effectiveness of this technology, two interconnecting trenches in Solid Waste Storage Area 6 (SWSA 6) were selected as candidates for in situ grouting with a particulate grout. The primary objective was to demonstrate the increased trench stability and decreased potential for leachate migration following in situ injection of a particulate grout into the waste trenches. Stability against trench subsidence is a critical issue. 7 refs., 3 figs., 5 tabs

Storage of multiple single-photon pulses emitted from a quantum dot in a solid-state quantum memory

Science.gov (United States)

Tang, Jian-Shun; Zhou, Zong-Quan; Wang, Yi-Tao; Li, Yu-Long; Liu, Xiao; Hua, Yi-Lin; Zou, Yang; Wang, Shuang; He, De-Yong; Chen, Geng; Sun, Yong-Nan; Yu, Ying; Li, Mi-Feng; Zha, Guo-Wei; Ni, Hai-Qiao; Niu, Zhi-Chuan; Li, Chuan-Feng; Guo, Guang-Can

2015-01-01

Quantum repeaters are critical components for distributing entanglement over long distances in presence of unavoidable optical losses during transmission. Stimulated by the Duan–Lukin–Cirac–Zoller protocol, many improved quantum repeater protocols based on quantum memories have been proposed, which commonly focus on the entanglement-distribution rate. Among these protocols, the elimination of multiple photons (or multiple photon-pairs) and the use of multimode quantum memory are demonstrated to have the ability to greatly improve the entanglement-distribution rate. Here, we demonstrate the storage of deterministic single photons emitted from a quantum dot in a polarization-maintaining solid-state quantum memory; in addition, multi-temporal-mode memory with 1, 20 and 100 narrow single-photon pulses is also demonstrated. Multi-photons are eliminated, and only one photon at most is contained in each pulse. Moreover, the solid-state properties of both sub-systems make this configuration more stable and easier to be scalable. Our work will be helpful in the construction of efficient quantum repeaters based on all-solid-state devices. PMID:26468996

High energy storage efficiency with fatigue resistance and thermal stability in lead-free Na{sub 0.5}K{sub 0.5}NbO{sub 3}/BiMnO{sub 3} solid-solution films

Energy Technology Data Exchange (ETDEWEB)

Sun, Yizhu; Zhou, Yunpeng; Lu, Qingshan; Zhao, Shifeng [Inner Mongolia Key Lab of Nanoscience and Nanotechnology and School of Physical Science and Technology, Inner Mongolia University, Hohhot (China)

2018-02-15

The ferroelectric, leakage, dielectric, and energy storage properties of lead-free Na{sub 0.5}K{sub 0.5}NbO{sub 3}/BiMnO{sub 3} (KNN/BMO) solid-solution films are investigated. The strong ferroelectric relaxation behaviors of slim ferroelectricity with small remanent polarization and coercive field induce a high energy-storage density and efficiency at room temperature. The energy density reaches 14.8 J cm{sup -3}, even the efficiency is up to 79.79% under the applied electric field of 985.66 kV cm{sup -1}. Moreover, the energy storage performances of KNN/BMO solid-solution films exhibit good thermal stability over a wide temperature range and high ferroelectric fatigue endurance after switching 10{sup 6} bipole electrical cycles. KNN/BMO solid-solution films can replace lead-based films and other outstanding lead-free systems in the energy storage performance. (copyright 2017 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Characterization plan for Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Boegly, W.J. Jr.; Dreier, R.B.; Huff, D.D.; Kelmers, A.D.; Kocher, D.C.; Lee, S.Y.; O'Donnell, F.R.; Pin, F.G.; Smith, E.D.

1985-12-01

Solid Waste Storage Area 6 (SWSA-6) is the only currently operating low-level radioactive waste (LLW) shallow land burial facility at the Oak Ridge National Laboratory. The US Department of Energy (DOE) recently issued DOE Order 5820.2, which provides new policy and guidelines for the management of radioactive wastes. To ensure that SWSA-6 complies with this Order it will be necessary to establish whether sufficient data on the geology, hydrology, soils, and climatology of SWSA-6 exist, and to develop plans to obtain any additional information required. It will also be necessary to establish a source term from the buried waste and provide geochemical information for hydrologic and dosimetric calculations. Where data gaps exist, methodology for obtaining this information must be developed. The purpose of this Plan is to review existing information on SWSA-6 and develop cost estimates and schedules for obtaining any required additional information. Routine operation of SWSA-6 was initiated in 1973, and it is estimated that about 29,100 m 3 (1,000,000 ft 3 ) of LLW containing about 250,000 Ci of radioactivity have been buried through 1984. Since SWSA-6 was sited prior to enactment of current disposal regulations, a detailed site survey of the geologic and hydrologic properties of the site was not performed before wastes were buried. However, during the operation of SWSA-6 some information on site characteristics has been collected

Radioactive waste management and disposal scenario for fusion power reactors

Energy Technology Data Exchange (ETDEWEB)

Tabara, Takashi; Yamano, Naoki [Sumitomo Atomic Energy Industries Ltd., Tokyo (Japan); Seki, Yasushi; Aoki, Isao

1997-10-01

The environmental and economic impact of radioactive waste (radwaste) generated from fusion power reactors using five types of structural materials and a light water reactor (LWR) have been evaluated and compared. At first, the amount and the radioactive level of the radwaste generated in five fusion reactors ware evaluated by an activation calculation code. Next, a possible radwaste disposal scenario applicable to fusion radwaste in Japan is considered and the disposal cost evaluated under certain assumptions. The exposure doses are evaluated for the skyshine of gamma-rays during the disposal operation, groundwater migration scenario during the institutional control period of 300 years and future site use scenario after the institutional period. The radwaste generated from a typical LWR was estimated based on a literature survey and the disposal cost was evaluated using the same assumptions as for the fusion reactors. It is found that the relative cost of disposal is strongly dependent on the cost for interim storage of medium level waste of fusion reactors and the cost of high level waste for the LWR. (author)

The methods of hydrogen storage

International Nuclear Information System (INIS)

Joubert, J.M.; Cuevas, F.; Latroche, M.; Percheron-Guegan, A.

2005-01-01

Hydrogen may be an excellent energy vector owing to its high specific energy. Its low density is however a serious drawback for its storage. Three techniques exist to store hydrogen. Storage under pressure is now performed in composite tanks under pressures around 700 bar. Liquid storage is achieved at cryogenic temperatures. Solid storage is possible in reversible metal hydrides or on high surface area materials. The three storage means are compared in terms of performance, energetic losses and risk. (authors)

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

Energy Technology Data Exchange (ETDEWEB)

M. D. Staiger

1999-06-01

A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

Combining plasma gasification and solid oxide cell technologies in advanced power plants for waste to energy and electric energy storage applications.

Science.gov (United States)

Perna, Alessandra; Minutillo, Mariagiovanna; Lubrano Lavadera, Antonio; Jannelli, Elio

2018-03-01

The waste to energy (WtE) facilities and the renewable energy storage systems have a strategic role in the promotion of the "eco-innovation", an emerging priority in the European Union. This paper aims to propose advanced plant configurations in which waste to energy plants and electric energy storage systems from intermittent renewable sources are combined for obtaining more efficient and clean energy solutions in accordance with the "eco-innovation" approach. The advanced plant configurations consist of an electric energy storage (EES) section based on a solid oxide electrolyzer (SOEC), a waste gasification section based on the plasma technology and a power generation section based on a solid oxide fuel cell (SOFC). The plant configurations differ for the utilization of electrolytic hydrogen and oxygen in the plasma gasification section and in the power generation section. In the first plant configuration IAPGFC (Integrated Air Plasma Gasification Fuel Cell), the renewable oxygen enriches the air stream, that is used as plasma gas in the gasification section, and the renewable hydrogen is used to enrich the anodic stream of the SOFC in the power generation section. In the second plant configuration IHPGFC (Integrated Hydrogen Plasma Gasification Fuel Cell) the renewable hydrogen is used as plasma gas in the plasma gasification section, and the renewable oxygen is used to enrich the cathodic stream of the SOFC in the power generation section. The analysis has been carried out by using numerical models for predicting and comparing the systems performances in terms of electric efficiency and capability in realizing the waste to energy and the electric energy storage of renewable sources. Results have highlighted that the electric efficiency is very high for all configurations (35-45%) and, thanks to the combination with the waste to energy technology, the storage efficiencies are very attractive (in the range 72-92%). Copyright © 2017 Elsevier Ltd. All rights

Use of some industrial waste as energy storage media

International Nuclear Information System (INIS)

Tayeb, A.M.

1996-01-01

Solar energy is stored using different solid storage materials, both chemical and metallic industrial wastes. The materials tested in the present study are paraffin wax, copper slag, aluminium slag, iron slag, cast iron slag and copper chips. Solar energy is stored in these materials and energy ia then recovered with water stream at different flow rates and the storage capacity and period for different materials were compared. The same set of experiments is run on solid metallic materials mixed with wax. The results indicated that iron slag has the highest storage capacity followed by cast iron slag then aluminium slag and copper chips and copper slag. It is also noted that addition of paraffin wax to the solid metallic material improves its storage capacity and duration greatly. The storage efficiency of different units is calculated and compared. 5 figs

Radwaste management aspects of the test blanket systems in ITER

Energy Technology Data Exchange (ETDEWEB)

Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, F-13067 Saint Paul Lez Durance (France); Canas, D. [CEA, DEN/DADN, centre de Saclay, F-91191 Gif-sur-Yvette cedex (France); Chaudhari, V. [Institute for Plasma Research, Bhat, Gandhinagar 382428 (India); Iseli, M. [ITER Organization, Route de Vinon sur Verdon, F-13067 Saint Paul Lez Durance (France); Kawamura, Y. [Japan Atomic Energy Agency, Naka-shi, Ibaraki-ken 311-0193 (Japan); Lee, D.W. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Petit, P. [European Commission, DG ENER, Brussels (Belgium); Pitcher, C.S.; Torcy, D. [ITER Organization, Route de Vinon sur Verdon, F-13067 Saint Paul Lez Durance (France); Ugolini, D. [Fusion for Energy, Barcelona (Spain); Zhang, H. [China Nuclear Energy Industry Corporation, Beijing 100032 (China)

2016-11-01

Highlights: • Test Blanket Systems are operated in ITER to test tritium breeding technologies. • The in-vessel parts of TBS become radio-active during the ITER nuclear phase. • For each TBM campaign the TBM, its shield and the Pipe Forests are removed. • High tritium contents and novel materials are specific TBS radwaste features. • A preliminary assessment confirmed RW routing, provided its proper conditioning. - Abstract: Test Blanket Systems (TBS) will be operated in ITER in order to prepare the next steps towards fusion power generation. After the initial operation in H/He plasmas, the introduction of D and T in ITER will mark the transition to nuclear operation. The significant fusion neutron production will give rise to nuclear heating and tritium breeding in the in-vessel part of the TBS. The management of the activated and tritiated structures of the TBS from operation in ITER is described. The TBS specific features like tritium breeding and power conversion at elevated temperatures, and the use of novel materials require a dedicated approach, which could be different to that needed for the other ITER equipment.

Remediation of radioactively contaminated facilities and the site of Russian Research Center Kurchatov Institute

International Nuclear Information System (INIS)

Velikhov, E.P.; Ponomarev-Stepnoj, N.N.; Volkov, V.G.

2007-01-01

One discusses the efforts to rehabilitate the radiation hazard installations and to remediate the contaminated territory of the Kurchatov Institute RSC undertaken in 2006-2007 in terms of the Remediation Project. The old radwaste storage facilities constructed at the site when the Institute was involved in activities to elaborate both war and civil nuclear technologies were the basic objects of the rehabilitation efforts. Paper describes the structure of the storage facilities covering the volume and the characteristics of the stored radwaste. Paper discusses the storage facility site layout parameters taken into consideration in the course of the remediation efforts. Paper describes the procedures, the sequence of the remediation efforts and the peculiar features of the planning and engineering approaches. Paper dwells upon the results of the rehabilitation and the remediation efforts [ru

Predicting protein aggregation during storage in lyophilized solids using solid state amide hydrogen/deuterium exchange with mass spectrometric analysis (ssHDX-MS).

Science.gov (United States)

Moorthy, Balakrishnan S; Schultz, Steven G; Kim, Sherry G; Topp, Elizabeth M

2014-06-02

Solid state amide hydrogen/deuterium exchange with mass spectrometric analysis (ssHDX-MS) was used to assess the conformation of myoglobin (Mb) in lyophilized formulations, and the results correlated with the extent of aggregation during storage. Mb was colyophilized with sucrose (1:1 or 1:8 w/w), mannitol (1:1 w/w), or NaCl (1:1 w/w) or in the absence of excipients. Immediately after lyophilization, samples of each formulation were analyzed by ssHDX-MS and Fourier transform infrared spectroscopy (FTIR) to assess Mb conformation, and by dynamic light scattering (DLS) and size exclusion chromatography (SEC) to determine the extent of aggregation. The remaining samples were then placed on stability at 25 °C and 60% RH or 40 °C and 75% RH for up to 1 year, withdrawn at intervals, and analyzed for aggregate content by SEC and DLS. In ssHDX-MS of samples immediately after lyophilization (t = 0), Mb was less deuterated in solids containing sucrose (1:1 and 1:8 w/w) than in those containing mannitol (1:1 w/w), NaCl (1:1 w/w), or Mb alone. Deuterium uptake kinetics and peptide mass envelopes also indicated greater Mb structural perturbation in mannitol, NaCl, or Mb-alone samples at t = 0. The extent of deuterium incorporation and kinetic parameters related to rapidly and slowly exchanging amide pools (Nfast, Nslow), measured at t = 0, were highly correlated with the extent of aggregation on storage as measured by SEC. In contrast, the extent of aggregation was weakly correlated with FTIR band intensity and peak position measured at t = 0. The results support the use of ssHDX-MS as a formulation screening tool in developing lyophilized protein drug products.

A study of reverse osmosis applicability to light water reactor radwaste processing. Technical report

International Nuclear Information System (INIS)

Markind, J.; Van Tran, T.

1979-04-01

The use of membrane technology has demonstrated significant process potential in nuclear radioactive waste applications. Reverse osmosis and ultrafiltration can provide filtration capability without the need of filter aids, minimize the requirements of chemical regeneration and/or disposal of expensive resins and can preconcentrate wastes without requiring major process equipment with large auxiliary heat supplies. Because of these capabilities, a study was undertaken to review, evaluate and document the existing experience, both nuclear and appropriate non-nuclear, of the membrane industry as it applies to the processing of reactor radwaste by membrane technology and, in particular, reverse osmosis and ultrafiltration. Relevant information was collected from both the literature and extensive communications with users and suppliers of membrane equipment. The systems reviewed ranged from experimental laboratory units to full scale process units

Pocket Size Solid State FLASH and iPOD Drives for gigabyte storage, display and transfer of digital medical images: an introduction

International Nuclear Information System (INIS)

Sankaran, A.

2008-01-01

The transition of radiological imaging from analog to digital was closely followed by the development of the Picture Archiving and Communication (PACS) system. Concomitantly, multidimensional imaging ( 4D and 5D, for motion and functional studies on 3D images) have presented new challenges, particularly in handling gigabyte size images from CT, MRI and PET scanners, which generate thousands of images. The storage and analysis of these images necessitate expensive image workstations. This paper highlights the recent innovations in mass storage, display and transfer of images, using miniature/pocket size solid state FLASH and iPOD drives

The development of radwaste in cineration technology (1)

International Nuclear Information System (INIS)

Park, Hun Hwee; Kim, Joon Hyung; Seo, Yong Chil; Kim, In Tae; Ahn, Byung Gil; Yang, Hee Chul; Won, Dong Yeon; Lee, Jae Chun; Kim, Chan Joong

1988-04-01

In order to establish a schedule to develope the incineration technology with feasibility, we summarized the recently published reports of the state of the arts and feasibility studies on it. After comparison study between incineration and compaction, we suggested that the combustible wastes should be incinerated and the incombustible wastes should be compacted by a supercompactor. The status of utilization of incineration for industrial and municipal wastes in Korea was surveyed and the applicability of these techniques to incineration of radwastes were evaluated and resulted to be good. Finally, a long-term plan to utilize the incineration technology up to the commercialization was established on the basis of the above data and feasibility. An experimental incineration process with a capacity of 5 kg plastic wastes per hour was designed by the research team and constructed by several machinery industries of the country to study the incineration characteristics and test the performance of each filter unit in the off-gas system. This process consists of waste pretreatment system, incinerator, off-gas treatment system, and measurement and control system. This process was constructed and performed test-operation with feeding some shredded wastes. The actual experiments will be done in 1988. Under the final goal of developing a SiC filter tube which could be used in the incineration process, a SiC sample with a proper binder was fabricated. The attempts to fabricate a bigger tube and to find out the best fabricating condition will be continued. (Author)

Safety assessment for the above ground storage of Cadmium Safety and Control Rods at the Solid Waste Management Facility

International Nuclear Information System (INIS)

Shaw, K.W.

1993-11-01

The mission of the Savannah River Site is changing from radioisotope production to waste management and environmental restoration. As such, Reactor Engineering has recently developed a plan to transfer the safety and control rods from the C, K, L, and P reactor disassembly basin areas to the Transuranic (TRU) Waste Storage Pads for long-term, retrievable storage. The TRU pads are located within the Solid Waste Management Facilities at the Savannah River Site. An Unreviewed Safety Question (USQ) Safety Evaluation has been performed for the proposed disassembly basin operations phase of the Cadmium Safety and Control Rod Project. The USQ screening identified a required change to the authorization basis; however, the Proposed Activity does not involve a positive USQ Safety Evaluation. A Hazard Assessment for the Cadmium Safety and Control Rod Project determined that the above-ground storage of the cadmium rods results in no change in hazard level at the TRU pads. A Safety Assessment that specifically addresses the storage (at the TRU pads) phase of the Cadmium Safety and Control Rod Project has been performed. Results of the Safety Assessment support the conclusion that a positive USQ is not involved as a result of the Proposed Activity

Wrong low level radioactive waste management in hospitals and improvement steps

International Nuclear Information System (INIS)

Keren, M.

2000-01-01

Hospitals are producers of great amounts of all kind of waste, including dangerous waste. The dangerous waste can be toxic, biological, radioactive, or a mixture of several kinds. There are clear procedures how to store and treat every kind of waste separately, according to its characteristics. Radioactive waste should be disposed only to a central radwaste disposal site. If the radioactive waste is mixed with biological waste, and contains long half-life isotopes, it should be neutralized from biological hazards before disposal to radwaste storage site. If the waste contains short half-life isotopes, it should be stored in a proper intermediate storage facility till a complete decay of the radioactive elements, and then treated as not radioactive. The existing procedures are old and a new proposal for radwaste procedures was prepared but not implemented. After several repetitive violations of the old regulations by some hospitals, it was decided to advance the implementation of the new proposal. This proposal consists of a detailed procedures for segregation, storage, decay and disposal of radwaste. It is based on the new recommendations of the IAEA. The responsibility for implementing the regulations is on the producers of the waste. This paper summarizes the violations and describes the main recommendations for improving procedures. The competent authority used moderate enforcement steps because of the delay in the implementation of the new procedures. As a matter of fact, the competent authority concluded that it's own investigation procedures should improve, but we shall not discuss it in this paper. (author)

Estimation of doses to individuals from radionuclides disposed of in Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Fields, D.E.; Boegly, W.J. Jr.; Huff, D.D.

1986-01-01

A simple methodology has been applied to estimate maximum possible doses to individuals from exposure to radionuclides released from Solid Waste Storage Area No. 6. This is the only operating shallow-land disposal site for radioactive waste at the Oak Ridge National Laboratory. The methodology is based upon simple, conservative assumptions. A data base of radionuclides disposed of in trenches and auger holes was prepared, and several radionuclide transport and ingestion scenarios were considered. The results of these simulations demonstrate the potential for adverse health effects associated with this waste disposal area, and support the need for further calculations using more complete and realistic assumptions

All-MXene (2D titanium carbide) solid-state microsupercapacitors for on-chip energy storage

KAUST Repository

Peng, You-Yu

2016-08-01

On-chip energy storage is a rapidly evolving research topic, opening doors for integration of batteries and supercapacitors at microscales on rigid and flexible platforms. Recently, a new class of two-dimensional (2D) transition metal carbides and nitrides (so-called MXenes) has shown great promise in electrochemical energy storage applications. Here, we report the fabrication of all-MXene (Ti3C2Tx) solid-state interdigital microsupercapacitors by employing a solution spray-coating, followed by a photoresist-free direct laser cutting method. Our prototype devices consisted of two layers of Ti3C2Tx with two different flake sizes. The bottom layer was stacked large-size MXene flakes (typical lateral dimensions of 3-6 μm) serving mainly as current collectors. The top layer was made of small-size MXene flakes (~1 μm) with a large number of defects and edges as the electroactive layer responsible for energy storage. Compared to Ti3C2Tx micro-supercapacitors with platinum current collectors, the all-MXene devices exhibited much lower contact resistance, higher capacitances and better rate-capabilities. The areal and volumetric capacitances of ~27 mF cm-2 and ~337 F cm-3, respectively, at a scan rate of 20 mV s-1 were achieved. The devices also demonstrated their excellent cyclic stability, with 100% capacitance retention after 10,000 cycles at a scan rate of 50 mV s-1. This study opens up a plethora of possible designs for high-performance on-chip devices employing different chemistries, flake sizes and morphologies of MXenes and their heterostructures.

All-MXene (2D titanium carbide) solid-state microsupercapacitors for on-chip energy storage

KAUST Repository

Peng, You-Yu; Akuzum, Bilen; Kurra, Narendra; Zhao, Meng-Qiang; Alhabeb, Mohamed; Anasori, Babak; Kumbur, Emin Caglan; Alshareef, Husam N.; Ger, Ming-Der; Gogotsi, Yury

2016-01-01

On-chip energy storage is a rapidly evolving research topic, opening doors for integration of batteries and supercapacitors at microscales on rigid and flexible platforms. Recently, a new class of two-dimensional (2D) transition metal carbides and nitrides (so-called MXenes) has shown great promise in electrochemical energy storage applications. Here, we report the fabrication of all-MXene (Ti3C2Tx) solid-state interdigital microsupercapacitors by employing a solution spray-coating, followed by a photoresist-free direct laser cutting method. Our prototype devices consisted of two layers of Ti3C2Tx with two different flake sizes. The bottom layer was stacked large-size MXene flakes (typical lateral dimensions of 3-6 μm) serving mainly as current collectors. The top layer was made of small-size MXene flakes (~1 μm) with a large number of defects and edges as the electroactive layer responsible for energy storage. Compared to Ti3C2Tx micro-supercapacitors with platinum current collectors, the all-MXene devices exhibited much lower contact resistance, higher capacitances and better rate-capabilities. The areal and volumetric capacitances of ~27 mF cm-2 and ~337 F cm-3, respectively, at a scan rate of 20 mV s-1 were achieved. The devices also demonstrated their excellent cyclic stability, with 100% capacitance retention after 10,000 cycles at a scan rate of 50 mV s-1. This study opens up a plethora of possible designs for high-performance on-chip devices employing different chemistries, flake sizes and morphologies of MXenes and their heterostructures.

Tribology of magnetic storage systems

Science.gov (United States)

Bhushan, Bharat

1992-01-01

The construction and the materials used in different magnetic storage devices are defined. The theories of friction and adhesion, interface temperatures, wear, and solid-liquid lubrication relevant to magnetic storage systems are presented. Experimental data are presented wherever possible to support the relevant theories advanced.

Learn interactively about radwaste management

International Nuclear Information System (INIS)

Stritar, Andrej; Gortnar, Oton; Mele, Irena; Zeleznik, Nadja

2001-01-01

The main purpose of this multimedia, developed by Nuclear Training Centre for the Agency for Radwaste Management is to present the topic to general public, especially schoolchildren. This is a short report about our first experience with the development of multimedia presentations. The whole process was relatively long, almost two years, but the main reason for that was availability of funds. The basic messages, the CD is supposed to deliver to the user, are: Radioactive waste is produced as a by-product of several beneficial human activities. Radioactive waste is dangerous, but we can safely handle and store it. Target audience is younger population that is very familiar with that type of multimedia technology. Therefore the design must be simple, attractive and easily understandable. The way how our messages are delivered must be close to the emotional level of the user, while at the same time factual data must be accurate and up to date. We have decided to use a combination of graphical animations, spoken messages, music, pictures and video clips. Main areas covered are the following: 1. Civilisation and waste 2. About radioactivity 3. What is radioactive waste and where is it produced? 4. What do we do with radioactive waste? 5. Radioactive waste in Slovenia 6. Transport of radioactive waste. Each area is at the top of a single branch of the scenario. In the second step for every display of each branch we have carefully prepared the written and spoken text, selected pictures, eventual video clips and designed animations. During the last development phase the feedback from the target audience was analysed. About 40 students and teacher of elementary school were involved. Their feedback was quite positive. Following figures try to give the impression about the final implementation of the CD ROM. Everything is in Slovenian language, however, translation to any other language is possible. CD-ROM is freely distributed to young visitors of the Nuclear Information

Evaluation and standardisation of fast analytical techniques for destructive radwaste control

Energy Technology Data Exchange (ETDEWEB)

De Simone, A.; Troiani, F. [ENEA, Unita' Rifiuti Radioattivi e Disattivazione Impianti, Centro Ricerche Saluggia, Vercelli (Italy)

2001-07-01

The document describes the work programme carried out by the Laboratorio Nazionale per la 'Caratterizzazione dei Rifiuti Radioattivi', in the frame of the European research project Destructive Radwaste Control. The main tasks of the research work were the evaluation of fast sample pre-treatment procedures and the development of chromatographic methods coupled to fast nuclide detection by Liquid Scintillation Counting. In order to test the High Performance Ion Chromatograph (HPIC) coupled to the Liquid Scintillation Counter (LSC) on high salt content solutions, synthetic cement solutions have been prepared and spiked with several {beta}-emitters hard to be measured with non-destructive analyses, along with other radionuclides important for the determination of the radiological inventory in radwastes. As the validation tests for the new analytical methods involved the manipulation of radioactive solutions, a remote area for HPIC-LSC apparatus has been designed and performed, in order to operate in safe conditions. According to the research programme, fast analytical methods for the chemical separation and radionuclide detection of the radioactive elements of interest, have been developed and qualified. From the results of the work, some protocols of analysis have been defined: they contain all information about operative conditions for HPIC-LSC apparatus, field of applicability, chemical and radioactive detection limits. [Italian] Questo documento riporta il lavoro realizzato dal Laboratorio Nazionale per la Caratterizzazione dei Rifiuti Radioattivi, nell'ambito del progetto di ricerca Europeo sulle tecniche di misura distruttive per rifiuti radioattivi. Il lavoro era finalizzato sia alla valutazione di nuove procedure veloci per la preparazione dei campioni da analizzare sia allo sviluppo di metodi Cromatografici accoppiati alla rivelazione di radionuclidi mediante Conteggio a Scintillazione Liquida. La sperimentazione della Cromatografia Ionica ad

Incorporating solid state drives into distributed storage systems

OpenAIRE

Wacha, Rosie

2012-01-01

Big data stores are becoming increasingly important in a variety of domains including scientific computing, internet applications, and business applications. For price and performance reasons, such storage is comprised of magnetic hard drives. To achieve the necessary degree of performance and reliability, the drives are configured into storage subsystems based on RAID (Redundant Array of Independent Disks). Because of their mechanical nature, hard drives are relatively power-hungry and slow ...

Storage and Disposal of Solid Radioactive Waste; Stockage et Evacuation des Dechets Radioactifs Solides; 0425 0420 0414 ; Almacenamiento y Evacuacion de Desechos Radiactivos Solidos

Energy Technology Data Exchange (ETDEWEB)

Pomarola, J. [Chef du Bureau Technique, Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

1960-07-01

This paper deals with solutions for the problem of final disposal of solid radioactive waste. I. It is first essential to organize a proper system of temporary storage. II. Final Storage In order to organize final storage, it is necessary to fix, according to the activity and form of the waste, the site and the modes of transport to be used within and outside the nuclear centre. The choice of solutions follows from the foregoing essentials. The paper then considers, in turn, final storage, on the ground, in the sub-soil and in the sea. Economic considerations are an important factor in determining the choice of solution. (author) [French] La presente communication a pour objet les solutions envisagees pour une destination finale des dechets radioactifs solides. I - Il est tout d'abord necessaire de prevoir un stockage provisoire organise. II - Stockage definitif: La realisation d'un stockage definitif rend necessaire, en fonction de l'activite et du conditionnement des dechets, la definition: - du site et des modes de transports envisages a l'interieur et a l'exterieur des Centres Nucleaires. Le choix des solutions decoule des imperatifs ci-dessus et on examine successivement le stockage definitif: - sur le sol, - dans le sous-sol, - en mer. Les considerations d'ordre economique constituent un facteur important dans le choix de la solution. (author) [Spanish] El autor de la memoria estudia las diferentes soluciones previstas para la evacuacion definitiva de los desechos radiactivos solidos. I - Antes que nada hay que preparar un almacenamiento provisional organizado. II - Evacuacion definitiva : Para organizar la evacuacion definitiva es necesario definir antes, en funcion de la actividad y acondicionamiento de los desechos: - el emplazamiento y la forma de transporte que se piensa utilizar en el interior y en el exterior de los centros nucleares. La eleccion de las diversas soluciones depende de las dos condiciones mencionadas; el autor examina sucesivamente la

Filter Paper-based Nucleic Acid Storage in High-throughput Solid Tumor Genotyping.

Science.gov (United States)

Stachler, Matthew; Jia, Yonghui; Sharaf, Nematullah; Wade, Jacqueline; Longtine, Janina; Garcia, Elizabeth; Sholl, Lynette M

2015-01-01

Molecular testing of tumors from formalin-fixed paraffin-embedded (FFPE) tissue blocks is central to clinical practice; however, it requires histology support and increases test turnaround time. Prospective fresh frozen tissue collection requires special handling, additional storage space, and may not be feasible for small specimens. Filter paper-based collection of tumor DNA reduces the need for histology support, requires little storage space, and preserves high-quality nucleic acid. We investigated the performance of tumor smears on filter paper in solid tumor genotyping, as compared with paired FFPE samples. Whatman FTA Micro Card (FTA preps) smears were prepared from 21 fresh tumor samples. A corresponding cytology smear was used to assess tumor cellularity and necrosis. DNA was isolated from FTA preps and FFPE core samples using automated methods and quantified using SYBR green dsDNA detection. Samples were genotyped for 471 mutations on a mass spectrophotometry-based platform (Sequenom). DNA concentrations from FTA preps and FFPE correlated for untreated carcinomas but not for mesenchymal tumors (Spearman σ=0.39 and σ=-0.1, respectively). Average DNA concentrations were lower from FTA preps as compared with FFPE, but DNA quality was higher with less fragmentation. Seventy-six percent of FTA preps and 86% of FFPE samples generated adequate DNA for genotyping. FTA preps tended to perform poorly for collection of DNA from pretreated carcinomas and mesenchymal neoplasms. Of the 16 paired DNA samples that were genotyped, 15 (94%) gave entirely concordant results. Filter paper-based sample preservation is a feasible alternative to FFPE for use in automated, high-throughput genotyping of carcinomas.

Summary of radioactive solid waste received in the 200 Areas during calendar year 1993

International Nuclear Information System (INIS)

Anderson, J.D.; Hagel, D.L.

1994-09-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1993. This report does not include backlog waste, solid radioactive waste in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, ''Hanford Site Solid Waste Acceptance Criteria,'' (WHC 1988), liquid waste data are not included in this document

Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Ragaisis, Valdas; Poskas, Povilas; Simonis, Vytautas; Adomaitis, Jonas Erdvilas [Lithuanian Energy Institute, Kaunas (Lithuania). Nuclear Engineering Lab.

2011-11-15

New solid radioactive waste management and interim storage facilities will be constructed for the Ignalina Nuclear Power Plant to support ongoing decommissioning activities, including removal and treatment of operational waste from the existing storage buildings. The paper presents approach and methods that have been used to assess radiological impacts to the general public potentially arising under normal operation and accident conditions and to demonstrate compliance with regulations in force. The assessment of impacts from normal operation includes evaluation of exposure arising from release of airborne radioactive material and from facilities and packages containing radioactive material. In addition, radiological impacts from other nearby operating and planned nuclear facilities are taken into consideration. The assessment of impacts under accident conditions includes evaluation of exposure arising from the selected design and beyond design basis accidents. (orig.)

Nickel-based anode with water storage capability to mitigate carbon deposition for direct ethanol solid oxide fuel cells.

Science.gov (United States)

Wang, Wei; Su, Chao; Ran, Ran; Zhao, Bote; Shao, Zongping; Tade, Moses O; Liu, Shaomin

2014-06-01

The potential to use ethanol as a fuel places solid oxide fuel cells (SOFCs) as a sustainable technology for clean energy delivery because of the renewable features of ethanol versus hydrogen. In this work, we developed a new class of anode catalyst exemplified by Ni+BaZr0.4Ce0.4Y0.2O3 (Ni+BZCY) with a water storage capability to overcome the persistent problem of carbon deposition. Ni+BZCY performed very well in catalytic efficiency, water storage capability and coking resistance tests. A stable and high power output was well maintained with a peak power density of 750 mW cm(-2) at 750 °C. The SOFC with the new robust anode performed for seven days without any sign of performance decay, whereas SOFCs with conventional anodes failed in less than 2 h because of significant carbon deposition. Our findings indicate the potential applications of these water storage cermets as catalysts in hydrocarbon reforming and as anodes for SOFCs that operate directly on hydrocarbons. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

A strategic approach to the conceptual design of complex radwaste facilities

International Nuclear Information System (INIS)

Mackay, Stewart; Scott Dam, A.; Holmes, Robert G.G.

1992-01-01

The design of radwaste treatment facilities is often complicated by the variety of waste types being treated. Further uncertainties over their composition and final waste form specifications can make the normal conceptual design phase difficult and unreliable. This paper describes the strategic planning necessary to define the facility functions and the process to prepare a Functional Design Criteria. The paper shows clearly, that for complex waste management problems, it is vital to consider and resolve uncertainties by means of a strategic plan before embarking on conceptual design. The paper shows an approach to preparation of design criteria using functional analysis. The paper provides examples where these methods were and are being used, both in the U.K. and the U.S. Strategic plans and functional criteria can be used as a basis for conceptual design which then provides a more meaningful basis for detailed technology selection during the detailed design process. The paper discusses experiences and lessons learned in the planning process. This process is widely applicable to a number of complex waste treatment facilities being planned and developed to process wastes generated at government facilities. (author)

The estimation and prediction of the inventories for the liquid and gaseous radwaste systems using the linear regression analysis

International Nuclear Information System (INIS)

Kim, J. Y.; Shin, C. H.; Kim, J. K.; Lee, J. K.; Park, Y. J.

2003-01-01

The variation transitions of the inventories for the liquid radwaste system and the radioactive gas have being released in containment, and their predictive values according to the operation histories of Yonggwang(YGN) 3 and 4 were analyzed by linear regression analysis methodology. The results show that the variation transitions of the inventories for those systems are linearly increasing according to the operation histories but the inventories released to the environment are considerably lower than the recommended values based on the FSAR suggestions. It is considered that some conservation were presented in the estimation methodology in preparing stage of FSAR

Treatment and storage of hydrogen isotopes

International Nuclear Information System (INIS)

Jung, H. S.; Lee, H. S.; An, D. H.; Kim, K. R.; Lee, S. H.; Choi, H. J.; Back, S. W.; Kang, H. S.; Eom, K. Y.; Lee, M. S.

2000-01-01

Storage of gaseous hydrogen isotopes in a cylinder is a well-established technology. However, Immobilization in the solid form is preferred for long-term storage of radioactive isotope gas because of the concern for leakage of the gas. The experimental thermodynamic p-c-T data show that Ti and U soak up hydrogen isotope gas at a temperature of a few hundred .deg. C and modest pressures. It was found that more hydrogen is dissolved in the metal than deuterium at constant pressure. Thus, the lighter isotope tends to be enriched in the solid phase

Process modeling of a reversible solid oxide cell (r-SOC) energy storage system utilizing commercially available SOC reactor

International Nuclear Information System (INIS)

Mottaghizadeh, Pegah; Santhanam, Srikanth; Heddrich, Marc P.; Friedrich, K. Andreas; Rinaldi, Fabio

2017-01-01

Highlights: • An electric energy storage system was developed based on a commercially available SOC reactor. • Heat generated in SOFC mode of r-SOC is utilized in SOEC operation of r-SOC using latent heat storage. • A round trip efficiency of 54.3% was reached for the reference system at atmospheric pressure. • An improved process system design achieved a round-trip efficiency of 60.4% at 25 bar. - Abstract: The increase of intermittent renewable energy contribution in power grids has urged us to seek means for temporal decoupling of electricity production and consumption. A reversible solid oxide cell (r-SOC) enables storage of surplus electricity through electrochemical reactions when it is in electrolysis mode. The reserved energy in form of chemical compounds is then converted to electricity when the cell operates as a fuel cell. A process system model was implemented using Aspen Plus® V8.8 based on a commercially available r-SOC reactor experimentally characterized at DLR. In this study a complete self-sustaining system configuration is designed by optimal thermal integration and balance of plant. Under reference conditions a round trip efficiency of 54.3% was achieved. Generated heat in fuel cell mode is exploited by latent heat storage tanks to enable endothermic operation of reactor in its electrolysis mode. In total, out of 100 units of thermal energy stored in heat storage tanks during fuel cell mode, 90% was utilized to offset heat demand of system in its electrolysis mode. Parametric analysis revealed the significance of heat storage tanks in thermal management even when reactor entered its exothermic mode of electrolysis. An improved process system design demonstrates a system round-trip efficiency of 60.4% at 25 bar.

Seven years of experience in storage of solid radioactive wastes of low and medium activity on the surface or in concrete ditches

International Nuclear Information System (INIS)

Bardet, G.

This experience in the transport and storage of radioactive waste leads to several reflections pertinent to large-scale nuclear installations throughout the world. The experience demonstrates that products of this kind can be centralized and confined by relatively simple processes which are safe and of reasonable cost. The necessary liaison between the producer of radioactive wastes and the group which takes charge of storage is emphasized for the choice of the waste conditioning procedure. It is a consistent part of the experience that the initial conditioning determines in large measure the handling and storage techniques. It is certain that the absence of a solution for long-term storage of radioactive wastes will lead the producers to consider and carry out conditioning which, although valuable, does not have all the same advantages for final disposition of the product. In the field of transport, the volumes and weights are important. It is desirable that a permanent storage center be near a railroad. It is stated that storage can be ensured under safe conditions and with acceptable costs of all solid wastes of low and average activity except those having more than a certain amount of alpha activity. For the latter products a solution can be found which is safe

Plutonium storage criteria

Energy Technology Data Exchange (ETDEWEB)

Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

1996-05-01

The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

Summary of radioactive solid waste received in the 200 Areas during calendar year 1990

International Nuclear Information System (INIS)

Anderson, J.D.; McCann, D.C.; Poremba, B.E.

1991-04-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1990. This report does not include solid radioactive wastes in storage or disposal in other areas or facilities such as the underground tank farms. Unless packaged within the scope of Hanford Site radioactive solid waste acceptance criteria, liquid waste data are not included in this document. 10 refs., 1 tab

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992

International Nuclear Information System (INIS)

Anderson, J.D.; Hagel, D.L.

1992-05-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994

International Nuclear Information System (INIS)

Anderson, J.D.; Hagel, D.L.

1995-08-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994

Energy Technology Data Exchange (ETDEWEB)

Anderson, J.D.; Hagel, D.L.

1995-08-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document.

Modeling and experimental performance of an intermediate temperature reversible solid oxide cell for high-efficiency, distributed-scale electrical energy storage

Science.gov (United States)

Wendel, Christopher H.; Gao, Zhan; Barnett, Scott A.; Braun, Robert J.

2015-06-01

Electrical energy storage is expected to be a critical component of the future world energy system, performing load-leveling operations to enable increased penetration of renewable and distributed generation. Reversible solid oxide cells, operating sequentially between power-producing fuel cell mode and fuel-producing electrolysis mode, have the capability to provide highly efficient, scalable electricity storage. However, challenges ranging from cell performance and durability to system integration must be addressed before widespread adoption. One central challenge of the system design is establishing effective thermal management in the two distinct operating modes. This work leverages an operating strategy to use carbonaceous reactant species and operate at intermediate stack temperature (650 °C) to promote exothermic fuel-synthesis reactions that thermally self-sustain the electrolysis process. We present performance of a doped lanthanum-gallate (LSGM) electrolyte solid oxide cell that shows high efficiency in both operating modes at 650 °C. A physically based electrochemical model is calibrated to represent the cell performance and used to simulate roundtrip operation for conditions unique to these reversible systems. Design decisions related to system operation are evaluated using the cell model including current density, fuel and oxidant reactant compositions, and flow configuration. The analysis reveals tradeoffs between electrical efficiency, thermal management, energy density, and durability.

Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

International Nuclear Information System (INIS)

Hladek, K.L.

1996-01-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995

Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

Energy Technology Data Exchange (ETDEWEB)

Hladek, K.L.

1996-06-06

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995.

Solid-state supercapacitors with rationally designed heterogeneous electrodes fabricated by large area spray processing for wearable energy storage applications

Science.gov (United States)

Huang, Chun; Zhang, Jin; Young, Neil P.; Snaith, Henry J.; Grant, Patrick S.

2016-01-01

Supercapacitors are in demand for short-term electrical charge and discharge applications. Unlike conventional supercapacitors, solid-state versions have no liquid electrolyte and do not require robust, rigid packaging for containment. Consequently they can be thinner, lighter and more flexible. However, solid-state supercapacitors suffer from lower power density and where new materials have been developed to improve performance, there remains a gap between promising laboratory results that usually require nano-structured materials and fine-scale processing approaches, and current manufacturing technology that operates at large scale. We demonstrate a new, scalable capability to produce discrete, multi-layered electrodes with a different material and/or morphology in each layer, and where each layer plays a different, critical role in enhancing the dynamics of charge/discharge. This layered structure allows efficient utilisation of each material and enables conservative use of hard-to-obtain materials. The layered electrode shows amongst the highest combinations of energy and power densities for solid-state supercapacitors. Our functional design and spray manufacturing approach to heterogeneous electrodes provide a new way forward for improved energy storage devices. PMID:27161379

Solid-state supercapacitors with rationally designed heterogeneous electrodes fabricated by large area spray processing for wearable energy storage applications.

Science.gov (United States)

Huang, Chun; Zhang, Jin; Young, Neil P; Snaith, Henry J; Grant, Patrick S

2016-05-10

Supercapacitors are in demand for short-term electrical charge and discharge applications. Unlike conventional supercapacitors, solid-state versions have no liquid electrolyte and do not require robust, rigid packaging for containment. Consequently they can be thinner, lighter and more flexible. However, solid-state supercapacitors suffer from lower power density and where new materials have been developed to improve performance, there remains a gap between promising laboratory results that usually require nano-structured materials and fine-scale processing approaches, and current manufacturing technology that operates at large scale. We demonstrate a new, scalable capability to produce discrete, multi-layered electrodes with a different material and/or morphology in each layer, and where each layer plays a different, critical role in enhancing the dynamics of charge/discharge. This layered structure allows efficient utilisation of each material and enables conservative use of hard-to-obtain materials. The layered electrode shows amongst the highest combinations of energy and power densities for solid-state supercapacitors. Our functional design and spray manufacturing approach to heterogeneous electrodes provide a new way forward for improved energy storage devices.

Solving radwaste problems

International Nuclear Information System (INIS)

Oyen, L.C.

1976-01-01

The combination of regulatory changes and increased waste volume has resulted in design changes in waste processing systems. Problems resulting from waste segregation as a basis for design philosophy are considered, and solutions to the problems are suggested. The importance of operator training, maintenance procedures, good housekeeping, water management, and offsite shipment of solids is discussed. Flowsheets for radioactive waste processing systems for boiling water reactors and pressurized water reactors are included

Radwaste '86: Abstracts volume

International Nuclear Information System (INIS)

Ainslie, L.C.

1986-08-01

The conference dealt with the treatment and containment of radioactive wastes and its disposal in arid environments. Papers were delivered on the various aspects of site selection. Waste transportation, and the storage and disposal of wastes at the Vaalputs radioactive waste disposal facility in the Republic of South Africa and in other parts of the world are discussed

Latent heat coldness storage; Stockage du froid par chaleur latente

Energy Technology Data Exchange (ETDEWEB)

Dumas, J.P. [Pau Univ., Lab. de Thermodynamique et Energetique, LTE, 64 (France)

2002-07-01

This article presents the advantages of latent heat storage systems which use the solid-liquid phase transformation of a pure substance or of a solution. The three main methods of latent heat storage of coldness are presented: ice boxes, encapsulated nodules, and ice flows: 1 - definition of the thermal energy storage (sensible heat, latent heat, thermochemical storage); 2 - advantages and drawbacks of latent heat storage; 3 - choice criteria for a phase-change material; 4 - phenomenological aspect of liquid-solid transformations (phase equilibrium, crystallisation and surfusion); 5 - different latent heat storage processes (ice boxes, encapsulated nodules, two-phase refrigerating fluids); 6 - ice boxes (internal and external melting, loop, air injection, measurement of ice thickness); 7 - encapsulated nodules (nodules, tank, drainage, advantage and drawbacks, charge and discharge); 8 - two-phase refrigerating fluids (composition, ice fabrication, flow circulation, flow storage, exchangers). (J.S.)

National report of the Slovak Republic compiled in terms of the Join on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Solid Waste Management Program Plan

Energy Technology Data Exchange (ETDEWEB)

Duncan, D.R.

1990-08-01

The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

ICPP calcined solids storage facility closure study. Volume III: Engineering design files

International Nuclear Information System (INIS)

1998-02-01

The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project's scope of work. Should more accurate numbers be required, a new analysis would be necessary

ICPP calcined solids storage facility closure study. Volume III: Engineering design files

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project`s scope of work. Should more accurate numbers be required, a new analysis would be necessary.

Performance assessment for continuing and future operations at Solid Waste Storage Area 6

International Nuclear Information System (INIS)

1994-02-01

This radiological performance assessment for the continued disposal operations at Solid Waste Storage Area 6 (SWSA 6) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US DOE. The analysis of SWSA 6 required the use of assumptions to supplement the available site data when the available data were incomplete for the purpose of analysis. Results indicate that SWSA 6 does not presently meet the performance objectives of DOE Order 5820.2A. Changes in operations and continued work on the performance assessment are expected to demonstrate compliance with the performance objectives for continuing operations at the Interim Waste Management Facility (IWMF). All other disposal operations in SWSA 6 are to be discontinued as of January 1, 1994. The disposal units at which disposal operations are discontinued will be subject to CERCLA remediation, which will result in acceptable protection of the public health and safety

Performance assessment for continuing and future operations at Solid Waste Storage Area 6

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

This radiological performance assessment for the continued disposal operations at Solid Waste Storage Area 6 (SWSA 6) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US DOE. The analysis of SWSA 6 required the use of assumptions to supplement the available site data when the available data were incomplete for the purpose of analysis. Results indicate that SWSA 6 does not presently meet the performance objectives of DOE Order 5820.2A. Changes in operations and continued work on the performance assessment are expected to demonstrate compliance with the performance objectives for continuing operations at the Interim Waste Management Facility (IWMF). All other disposal operations in SWSA 6 are to be discontinued as of January 1, 1994. The disposal units at which disposal operations are discontinued will be subject to CERCLA remediation, which will result in acceptable protection of the public health and safety.

Soil survey of Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Lietzke, D.A.; Lee, S.Y.

1986-06-01

An intensive soil survey was made of Solid Waste Storage Area (SWSA) 6 (Oak Ridge National Laboratory) at a scale of 1:1200. The amount of chemical weathering, the thickness of upland soils, and the depth to unoxidized rock are dependent on slope gradient, water-flow pathways, degree of rock fracturing, and the extent of soil and rock erosion by late Pleistocene and Holocene geomorphic processes. Foot-slope landforms have generally concave slope shapes where sediment accumulates. Colluvium stratigraphy exhibits at least one lithologic discontinuity, but there may be two discontinuities preserved in some thicker colluvia. One or more paleosols, either complete or partially truncated, are preserved in these concave landforms. Alluvial soils were not examined in detail but were separated from colluvial soils because of their wetness. A small area of ancient alluvium was located on a stable upland summit that formed the highest elevation in SWSA-6. On the nearly level summit, a thin loess cap was preserved on the older alluvial soil. Upland and colluvial soils are all highly leached and strongly acid even though they are formed from a calcareous parent rock. The highly fractured rock, being relatively permeable, has been leached free of carbonates in the upper levels so that there is a wide pH gradient from the surface downward. Most of the soils were classified as Ultisols, with minimal areas of Alfisols, Inceptisols, and Entisols. Based on the soil survey, representative landforms and soils will be selected to study physical, chemical, and mineralogical properties of the soil and weathered rock. Those properties will be used to predict both the amount and duration of leachate filtration and purification in downward migration to the water table or lateral migration through colluvial and alluvial soils to ground-water seeps

Summary of radioactive solid waste received in the 200 areas during calendar year 1997

International Nuclear Information System (INIS)

Hagel, D.L.

1998-01-01

Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document

Summary of radioactive solid waste received in the 200 areas during calendar year 1997

Energy Technology Data Exchange (ETDEWEB)

Hagel, D.L.

1998-06-25

Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document.

Summary of radioactive solid waste received in the 200 areas during calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

Hladek, K.L.

1997-05-21

Rust Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1996. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document.

Light storage via slow-light four-wave mixing

International Nuclear Information System (INIS)

Fan, Yun-Fei; Wang, Hai-Hua; Wei, Xiao-Gang; Li, Ai-Jun; Kang, Zhi-Hui; Wu, Jin-Hui; Zhang, Han-Zhuang; Xu, Huai-Liang; Gao, Jin-Yue

2012-01-01

We experimentally demonstrate a light storage via slow-light four-wave mixing in a solid-state medium with a four-level double lambda scheme. Using slow light based on electromagnetically induced transparency, we obtain a slowed four-wave mixing signal pulse together with the slowed probe pulse. During the propagation of light pulses, the storage and retrieval of both the slowed four-wave mixing pulse and the slowed probe pulse are studied by manipulating the intensities of the control fields. -- Highlights: ► A light storage via slow-light four-wave mixing is observed in a solid. ► The probe pulse is slowed under electromagnetically induced transparency. ► A slowed four-wave mixing pulse is obtained by slow light. ► The storage of slowed double pulses is studied.

Generation, storage, collection and transportation of municipal solid waste - A case study in the city of Kathmandu, capital of Nepal

International Nuclear Information System (INIS)

Alam, R.; Chowdhury, M.A.I.; Hasan, G.M.J.; Karanjit, B.; Shrestha, L.R.

2008-01-01

Solid waste management (SWM) services have consistently failed to keep up with the vast amount of solid waste produced in urban areas. There is not currently an efficient system in place for the management, storage, collection, and transportation of solid waste. Kathmandu City, an important urban center of South Asia, is no exception. In Kathmandu Metropolitan City, solid waste generation is predicted to be 1091 m 3 /d (245 tons/day) and 1155 m 3 /d (260 tons/day) for the years 2005 and 2006, respectively. The majority (89%) of households in Kathmandu Metropolitan City are willing to segregate the organic and non-organic portions of their waste. Overall collection efficiency was 94% in 2003. An increase in waste collection occurred due to private sector involvement, the shutdown of the second transfer station near the airport due to local protest, a lack of funding to maintain trucks/equipment, a huge increase in plastic waste, and the willingness of people to separate their waste into separate bins. Despite a substantial increase in total expenditure, no additional investments were made to the existing development plan to introduce a modern disposal system due to insufficient funding. Due to the lack of a proper lining, raw solid waste from the existing dumping site comes in contact with river water directly, causing severe river contamination and deteriorating the quality of the water

Evaluation of disposal, recycling and clearance scenarios for managing ARIES radwaste after plant decommissioning

International Nuclear Information System (INIS)

El-Guebaly, L.

2007-01-01

The wealth of experience accumulated over the past 30-40 years of fusion power plant studies must be forged into a new strategy to reshape all aspects of handling the continual stream of radioactive materials during operation and after power plant decommissioning. With tighter environmental controls and the political difficulty of building new repositories worldwide, the disposal option could be replaced with more environmentally attractive scenarios, such as recycling and clearance. We applied the three scenarios to the most recent ARIES compact stellarator power plant. All ARIES-CS components qualify as Class A or C low-level waste, according to the US guidelines, and can potentially be recycled using conventional and advanced remote handling equipment. Approximately 80% of the total waste can be cleared for reuse within the nuclear industry or, preferably, released to the commercial market. This paper documents the recent developments in radwaste management of nuclear facilities and highlights the benefits and challenges of disposal, recycling and clearance

Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Ashwood, T.L.; Marsh, J.D. Jr.

1994-04-01

This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L)

Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Ashwood, T.L.; Marsh, J.D. Jr.

1994-04-01

This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L).

Heat Modeling and Material Development of Mg-Based Nanomaterials Combined with Solid Oxide Fuel Cell for Stationary Energy Storage

Directory of Open Access Journals (Sweden)

Huaiyu Shao

2017-11-01

Full Text Available Mg-based materials have been investigated as hydrogen storage materials, especially for possible onboard storage in fuel cell vehicles for decades. Recently, with the development of large-scale fuel cell technologies, the development of Mg-based materials as stationary storage to supply hydrogen to fuel-cell components and provide electricity and heat is becoming increasingly promising. In this work, numerical analysis of heat balance management for stationary solid oxide fuel cell (SOFC systems combined with MgH2 materials based on a carbon-neutral design concept was performed. Waste heat from the SOFC is supplied to hydrogen desorption as endothermic heat for the MgH2 materials. The net efficiency of this model achieves 82% lower heating value (LHV, and the efficiency of electrical power output becomes 68.6% in minimizing heat output per total energy output when all available heat of waste gas and system is supplied to warm up the storage. For the development of Mg-based hydrogen storage materials, various nano-processing techniques have been widely applied to synthesize Mg-based materials with small particle and crystallite sizes, resulting in good hydrogen storage kinetics, but poor thermal conductivity. Here, three kinds of Mg-based materials were investigated and compared: 325 mesh Mg powers, 300 nm Mg nanoparticles synthesized by hydrogen plasma metal reaction, and Mg50Co50 metastable alloy with body-centered cubic structure. Based on the overall performances of hydrogen capacity, absorption kinetics and thermal conductivity of the materials, the Mg nanoparticle sample by plasma synthesis is the most promising material for this potential application. The findings in this paper may shed light on a new energy conversion and utilization technology on MgH2-SOFC combined concept.

Thermal contact resistance in carbon nanotube enhanced heat storage materials

NARCIS (Netherlands)

Zhang, H.; Nedea, S.V.; Rindt, C.C.M.; Smeulders, D.M.J.

2015-01-01

Solid-liquid phase change is one of the most favorable means of compact and economical heat storage in the built environment. In such storage systems, the vast available solar heat is stored as latent heat in the storage materials. Recent studies suggest using sugar alcohols as seasonal heat storage

German conception for ultimate storage of radwaste

International Nuclear Information System (INIS)

Viehl, E.

1981-01-01

Before starting the site exploring program of the salt deposit of Gorleben only the outlines and the depth level of the deposit surface were known, as far as those informations could be obtained by means of reflection-seismic measurements. In total it is about 15 km long and 4 km large and towers from its base in 3 000 m low altitude to about 200 to 300 m below surface. Three older boreholes in the north-eastern part of the salt deposit can not be sufficiently interpreted. One of them caused a shaft sinking through 694 m steep placed mineral salt with included beds of potash salt that are not described in detail. In later times the borehole Gorleben Z1 in the north-west, outside close to the salt deposit has been sunk down to the Zechstein-base. The site exploring program is used for exploring the geological over-all situation of the salt deposit Gorleben and is compared of a hydrogeological investigation program and a drilling program. (orig./HP) [de

Influence of the segregation of the granulate from the radwaste-mortar mixture from on the {sup 137}Cs leach-rate; Uticaj segregacije granulata iz sastava betonske - RAO forme na izluzivanje Cs{sup 137}

Energy Technology Data Exchange (ETDEWEB)

Peric, A; Plecas, I; Pavlovic, R; Pavlovic, S [Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia)

1994-07-01

In this paper. influence of the segregation of the granulate, presented in the radwaste-mortar matrix formulation, on the {sup 137}Cs, immobilized in the waste form, leach-rate is presented. {sup 137}Cs leach-rates of the two inspected groups of the radwaste-mortar mixture samples were compared, where the first group of the orthocylinder shaped samples was treated due to the Standard Hespe's method and the second group was treated using modified Hespe's method. In the prolonged experimental time, both groups have obtained leach-rate values that are nearly the same, striving to the saturation leach-rate values. This fact indicates that the leaching of the radionuclide as a consequence of the granulate segregation process is in same way rebuilt, as a result of the completed hydratation of the mortar matrix, and 'self healing' of the new open pores and cavities (author)

National report of the Slovak Republic compiled in terms of the join convention on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Treatment of radioactive wastes from DOE underground storage tanks

International Nuclear Information System (INIS)

Collins, J.L.; Egan, B.Z.; Spencer, B.B.; Chase, C.W.; Anderson, K.K.; Bell, J.T.

1994-01-01

Bench-scale batch tests have been conducted with sludge and supernate tank waste from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation technology process for use in a comprehensive sludge processing flow sheet as a means of concentrating the radionuclides and reducing the volumes of storage tank waste at national sites for final disposal. This paper discusses the separation of the sludge solids and supernate, the basic washing of the sludge solids, the acidic dissolution of the sludge solids, and the removal of the radionuclides from the supernate

Applications of chemical engineering principles to glassmaking for nuclear waste fixation

International Nuclear Information System (INIS)

Boersma, M.D.

1988-01-01

There are five important differences between radwaste vitrification and normal industrial glassmaking. The hostile (radioactive) environment requires the entire process to be operated and maintained remotely. This is largely a mechanical/architectural engineering problem because radiation has very little direct impact on process chemistry or energy. A second difference is that process plant economics are dominated by safety and reliability considerations, rather than market conditions and energy costs. Third, the product quality criteria are quite different; rather than optical clarity, mechanical strength, functional shape, and esthetic appeal, the important quality for radwaste glass is its chemical durability in final storage. Fourth, the off-gases from a radwaste vitrification process are of greater environmental concern. Equipment must be airtight or under vacuum, and highly efficient gas cleanup systems must be used. Finally, feed to a radwaste glass melter is typically at least 50% water. Liquid slurry melter feed is not unheard of in commercial glassmaking but dry batch feed is normal. Slurry water more than doubles the process energy demand in the melter and causes some very large local temperature gradients. 2 figs

Amorphous solid dispersions of piroxicam and Soluplus(®): Qualitative and quantitative analysis of piroxicam recrystallization during storage.

Science.gov (United States)

Lust, Andres; Strachan, Clare J; Veski, Peep; Aaltonen, Jaakko; Heinämäki, Jyrki; Yliruusi, Jouko; Kogermann, Karin

2015-01-01

The conversion of active pharmaceutical ingredient (API) from amorphous to crystalline form is the primary stability issue in formulating amorphous solid dispersions (SDs). The aim of the present study was to carry out qualitative and quantitative analysis of the physical solid-state stability of the SDs of poorly water-soluble piroxicam (PRX) and polyvinyl caprolactam-polyvinyl acetate-polyethylene-glycol graft copolymer (Soluplus(®)). The SDs were prepared by a solvent evaporation method and stored for six months at 0% RH/6 °C, 0% RH/25 °C, 40% RH/25 °C and 75% RH/25 °C. Fourier transform infrared spectroscopy equipped with attenuated total reflection accessory (ATR-FTIR) and Raman spectroscopy were used for characterizing the physical solid-state changes and drug-polymer interactions. The principal component analysis (PCA) and multivariate curve resolution alternating least squares (MCR-ALS) were used for the qualitative and quantitative analysis of Raman spectra collected during storage. When stored at 0% RH/6 °C and at 0% RH/25 °C, PRX in SDs remained in an amorphous form since no recrystallization was observed by ATR-FTIR and Raman spectroscopy. Raman spectroscopy coupled with PCA and MCR-ALS and ATR-FTIR spectroscopy enabled to detect the recrystallization of amorphous PRX in the samples stored at higher humidity. Copyright © 2015 Elsevier B.V. All rights reserved.

Calculation characterization of spent fuel hazard related to partitioning and transmutation of minor actinides and fission products

International Nuclear Information System (INIS)

Gerasimov, A. S.; Bergelson, B. R.; Tikhomirov, G.V.; Volovik, A.I. . E-mail of corresponding author: geras@itep.ru; Gerasimov, A.S.)

2005-01-01

Radiotoxicity is one of important characteristics of radwaste hazard. Radiotoxicity of actinides and fission products from spent fuel of VVER-1000 reactor for processes of burnup, long-term storage, and transmutation is discussed. (author)

Rad-waste treatment

International Nuclear Information System (INIS)

1996-01-01

The spent fuel coming from Slovak NPPs have partially been transported to the former Soviet Union, and a part of it is stored in an interim spent fuel wet storage. In compliance with the worldwide practices, further medium-term possibilities of storing in dry storages are under preparation. Disposal of a spent fuel and other high-level active wastes in a deep geological formation repository is the final solution. At present, there are geological investigations of possible sites in progress in Slovakia. Mochovce repository is a factory for a final disposal of compacted low and intermediate level radioactive wastes coming from the Slovak NPPs. This is a near-surface facility of a construction similar to the one used for disposal of radioactive wastes in France, Spain, Japan, Czech Republic, U.S.A, etc. Quality of the design, construction and functioning of the Mochovce's repository was assessed by an international team of experts within a special IAEA programme (WATRP). Having familiarized with the final report of the IAEA mission, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) issued its position early in 1995, in which NRA SR required additional adjustment of the repository itself. Based on the NRA SR's position, Mochovce NPP invited experts from a number of institutions in September 1995 to discuss the NRA SR's requirements. Following was recommended by the experts: (1) to perform a complementary engineering-geological investigation on the site, (2) to use geophysical methods to verify existence of geological faults. In the next part a radioactive wastes that were treated at radioactive waste treatment lines in 1995 are listed. In 1995, the Chief Inspector of NRA SR issued an instruction that radioactive waste department should start inspections of radioactive waste treatment right in hospitals, research institutes and industries. Therefore, a total of 14 such workplaces were incorporated into a plan of inspections in 1995

Final storage of radioactive waste in Germany - a 'no-development report'?

International Nuclear Information System (INIS)

Roesel, H.

1994-01-01

The Federal Government is obliged by law to install facilities for safekeeping and ultimate storage of radioactive waste, and it fulfills this duty purposefully, assigning top priority to safety. This is demonstrated by the large number of court cases in which the Federal Government firmly seeks its right vis-a-vis a State Government bent on opting out of nuclear power. Against the backdrop of the failed energy consensus talks there is no need to discontinue the speedy exploration of the Gorleben salt dome to determine its suitability as a repository, about which there can be no doubt. Comment: The Lueneburg Court of Administration recently has set aside the decision of the Ministry of the Environment of the Land Lower Saxony, to stop the exploration at the Gorleben site. The public hearing about the Konrad site has been successfully terminated after a period of 75 days. The Magdeburg Court of Administration confirmed the lawfulness of the operating permit issued for the Morsleben site, which now is allowed to receive radwaste, also from installations in the western part of Germany. (orig./HP) [de

Preparation for tritiated waste management of fusion facilities: Interim storage WAC

Energy Technology Data Exchange (ETDEWEB)

Decanis, C., E-mail: christelle.decanis@cea.fr [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Canas, D. [CEA, DEN/DADN, Centre de Saclay, F-91191 Gif-sur-Yvette cedex (France); Derasse, F. [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Pamela, J. [CEA, Agence ITER-France, F-13108 Saint-Paul-lez-Durance (France)

2016-11-01

Highlights: • Fusion devices including ITER will generate tritiated waste. • Interim storage is the reference solution offering an answer for all types of tritiated radwaste. • Interim storage is a buffer function in the process management and definition of the waste acceptance criteria (WAC) is a key milestone in the facility development cycle. • Defining WAC is a relevant way to identify ahead of time the studies to be launched and the required actions to converge on a detailed design for example material specific studies, required treatment, interfaces management, modelling and monitoring studies. - Abstract: Considering the high mobility of tritium through the package in which it is contained, the new 50-year storage concepts proposed by the French Alternative Energies and Atomic Energy Commission (CEA) currently provide a solution adapted to the management of waste with tritium concentrations higher than the accepted limits in the disposals. The 50-year intermediate storage corresponds to 4 tritium radioactive periods i.e., a tritium reduction by a factor 16. This paper details the approach implemented to define the waste acceptance criteria (WAC) for an interim storage facility that not only takes into account the specificity of tritium provided by the reference scheme for the management of tritiated waste in France, but also the producers’ needs, the safety analysis of the facility and Andra’s disposal requirements. This will lead to define a set of waste specifications that describe the generic criteria such as acceptable waste forms, general principles and specific issues, e.g. conditioning, radioactive content, tritium content, waste tracking system, and quality control. This approach is also a way to check in advance, during the design phase of the waste treatment chain, how the future waste could be integrated into the overall waste management routes and identify possible key points that need further investigations (design changes, selection

Storing solid radioactive wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Horton, J.H.; Corey, J.C.

1976-06-01

The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

Recent advances in energy storage materials and devices

CERN Document Server

Lu, Li

2017-01-01

This book compiles nine comprehensive contributions from the principle of Li-ion batteries, cathode and anode electrode materials to future energy storage systems such as solid electrolyte for all-solid-state batteries and high capacity redox flow battery.

Fundamentally Addressing Bromine Storage through Reversible Solid-State Confinement in Porous Carbon Electrodes: Design of a High-Performance Dual-Redox Electrochemical Capacitor.

Science.gov (United States)

Yoo, Seung Joon; Evanko, Brian; Wang, Xingfeng; Romelczyk, Monica; Taylor, Aidan; Ji, Xiulei; Boettcher, Shannon W; Stucky, Galen D

2017-07-26

Research in electric double-layer capacitors (EDLCs) and rechargeable batteries is converging to target systems that have battery-level energy density and capacitor-level cycling stability and power density. This research direction has been facilitated by the use of redox-active electrolytes that add faradaic charge storage to increase energy density of the EDLCs. Aqueous redox-enhanced electrochemical capacitors (redox ECs) have, however, performed poorly due to cross-diffusion of soluble redox couples, reduced cycle life, and low operating voltages. In this manuscript, we propose that these challenges can be simultaneously met by mechanistically designing a liquid-to-solid phase transition of oxidized catholyte (or reduced anolyte) with confinement in the pores of electrodes. Here we demonstrate the realization of this approach with the use of bromide catholyte and tetrabutylammonium cation that induces reversible solid-state complexation of Br 2 /Br 3 - . This mechanism solves the inherent cross-diffusion issue of redox ECs and has the added benefit of greatly stabilizing the reactive bromine generated during charging. Based on this new mechanistic insight on the utilization of solid-state bromine storage in redox ECs, we developed a dual-redox EC consisting of a bromide catholyte and an ethyl viologen anolyte with the addition of tetrabutylammonium bromide. In comparison to aqueous and organic electric double-layer capacitors, this system enhances energy by factors of ca. 11 and 3.5, respectively, with a specific energy of ∼64 W·h/kg at 1 A/g, a maximum power density >3 kW/kg, and cycling stability over 7000 cycles.

Solid NMR characterization of hydrogen solid storage matrices; Caracterisation par RMN du solide des matrices de stockage solide de l'hydrogene

Energy Technology Data Exchange (ETDEWEB)

Pilette, M.A.; Charpentier, T.; Berthault, P. [CEA Saclay, Dept. de Recherche sur l' Etat Condense, les Atomes et les Molecules, Lab. de Structure et Dynamique par Resonance Magnetique Lab. Claude Frejacques - CEA/CNRS URA 331, DSM/DRECAM/SCM, 91 - Gif sur Yvette (France)

2007-07-01

The aim of this work is to develop and validate characterization tools by NMR imagery and spectroscopy of the structure of materials for hydrogen storage, and of their evolution during load/unload cycles. The two main topics of this work are in one hand the analysis of the local structure of the materials and the understanding of their eventual modifications, and in another hand, the in-situ analysis of the distribution and diffusion of hydrogen inside the storage material. (O.M.)

ICPP calcined solids storage facility closure study. Volume II: Cost estimates, planning schedules, yearly cost flowcharts, and life-cycle cost estimates

International Nuclear Information System (INIS)

1998-02-01

This document contains Volume II of the Closure Study for the Idaho Chemical Processing Plant Calcined Solids Storage Facility. This volume contains draft information on cost estimates, planning schedules, yearly cost flowcharts, and life-cycle costs for the four options described in Volume I: (1) Risk-Based Clean Closure; NRC Class C fill, (2) Risk-Based Clean Closure; Clean fill, (3) Closure to landfill Standards; NRC Class C fill, and (4) Closure to Landfill Standards; Clean fill

ICPP calcined solids storage facility closure study. Volume II: Cost estimates, planning schedules, yearly cost flowcharts, and life-cycle cost estimates

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

This document contains Volume II of the Closure Study for the Idaho Chemical Processing Plant Calcined Solids Storage Facility. This volume contains draft information on cost estimates, planning schedules, yearly cost flowcharts, and life-cycle costs for the four options described in Volume I: (1) Risk-Based Clean Closure; NRC Class C fill, (2) Risk-Based Clean Closure; Clean fill, (3) Closure to landfill Standards; NRC Class C fill, and (4) Closure to Landfill Standards; Clean fill.

Novel electrical energy storage system based on reversible solid oxide cells: System design and operating conditions

Science.gov (United States)

Wendel, C. H.; Kazempoor, P.; Braun, R. J.

2015-02-01

Electrical energy storage (EES) is an important component of the future electric grid. Given that no other widely available technology meets all the EES requirements, reversible (or regenerative) solid oxide cells (ReSOCs) working in both fuel cell (power producing) and electrolysis (fuel producing) modes are envisioned as a technology capable of providing highly efficient and cost-effective EES. However, there are still many challenges and questions from cell materials development to system level operation of ReSOCs that should be addressed before widespread application. This paper presents a novel system based on ReSOCs that employ a thermal management strategy of promoting exothermic methanation within the ReSOC cell-stack to provide thermal energy for the endothermic steam/CO2 electrolysis reactions during charging mode (fuel producing). This approach also serves to enhance the energy density of the stored gases. Modeling and parametric analysis of an energy storage concept is performed using a physically based ReSOC stack model coupled with thermodynamic system component models. Results indicate that roundtrip efficiencies greater than 70% can be achieved at intermediate stack temperature (680 °C) and elevated stack pressure (20 bar). The optimal operating condition arises from a tradeoff between stack efficiency and auxiliary power requirements from balance of plant hardware.

Solid-State Ultracapacitor for Improved Energy Storage

Science.gov (United States)

Nabors, Sammy

2015-01-01

NASA's Marshall Space Flight Center has developed a solid-state ultracapacitor using a novel nanocomposite, dielectric material. The material's design is based on the internal barrier layer capacitance (IBLC) concept, and it uses novel dielectric and metallic conductive ink formulations. Novel processing methods developed by NASA provide for unique dielectric properties at the grain level. Nanoscale raw material powders are tailored using a variety of techniques and then formulated into a special ink. This dielectric ink is used with novel metallic conductive ink to print a capacitor layer structure into any design necessary to meet a range of technical requirements. The innovation is intended to replace current range safety batteries that NASA uses to power the systems that destroy off-course space vehicles. A solid-state design provides the needed robustness and safety for this demanding application.

Hydrogen storage using borohydrides

International Nuclear Information System (INIS)

Bernard BONNETOT; Laetitia LAVERSENNE

2006-01-01

The possibilities of hydrogen storage using borohydrides are presented and discussed specially in regard of the recoverable hydrogen amount and related to the recovering conditions. A rapid analysis of storage possibilities is proposed taking in account the two main ways for hydrogen evolution: the dehydrogenation obtained through thermal decomposition or the hydrolysis of solids or solutions. The recoverable hydrogen is related to the dehydrogenation conditions and the real hydrogen useful percentage is determined for each case of use. The high temperature required for dehydrogenation even when using catalyzed compounds lead to poor outlooks for this storage way. The hydrolysis conditions direct the chemical yield of the water consuming, and this must be related to the experimental conditions which rule the storage capacity of the 'fuel' derived from the borohydride. (authors)

Advanced solid state batteries

Energy Technology Data Exchange (ETDEWEB)

Levasseur, A; Delmas, C; Menetrier, M; Hagenmuller, P

1984-01-01

Direct electrochemical storage of electricity is attractive because of its adaptability to vehicle traction as well as to stationary applications. Important advancements are necessary to improve primary or secondary batteries so far used. The aim of this study was to develop and to characterize materials for the next generation of advanced, rechargeable solid state batteries for vehicle transport and stationary storage applications. One of the best electricity storage systems was the lithium/intercalation compound secondary battery, though up to now the behavior of liquid organic electrolytes did not allow for good recycling in such systems. The research program for these batteries is described.

Instructive for radioactive solid waste management

International Nuclear Information System (INIS)

Mora Rodriguez, Patricia

2014-01-01

An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM [es

Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

International Nuclear Information System (INIS)

1998-01-01

The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

Conditioning of spent fuel assemblies from the Rossendorf RFR research reactor in transport and storage containers of the type CASTOR MTR 2

International Nuclear Information System (INIS)

Schneider, B.; Hofmann, G.

1994-09-01

Most of the spent fuel assemblies are temporarily stored in the flooded fuel ponds AB 1 and AB 2 of the RFR, and some are still in the reactor core. The conditioning task described here is part of the RFR spent fuel management concept and covers the safe emplacement of the spent fuel elements in the CASTOR MTR 2 shipping containers and the sealing of the containers in compliance with the nuclear licence issued for the conditioning task. The transfer of the spent fuel assemblies from the present wet storage conditions to the dry storage conditions in the CASTOR MTR 2 containers is done by a mobile manipulation equipment consisting essentially of the transfer sluice gate and a transfer container. Subsequent to conditioning, the shipping containers are to be transported to a licensed intermediate storage facility to await their transport to a national radwaste repository. The technical handling tools for the transfer and manipulation are briefly described, as well as the process steps involved, putting emphasis on the detailed description of processes and the accompanying time frame, so that the conditioning task can be incorporated into the work plan of the entire project. The report further presents the EDP concept established for the task, including the required data archivation and documentation. (orig.) [de

Maximizing the energy storage performance of phase change thermal storage systems

Energy Technology Data Exchange (ETDEWEB)

Amin, N.A.M.; Bruno, F.; Belusko, M. [South Australia Univ., Mawson Lakes, South Australia (Australia). Inst. for Sustainable Systems and Technologies

2009-07-01

The demand for electricity in South Australia is highly influenced by the need for refrigeration and air-conditioning. An extensive literature review has been conducted on the use of phase change materials (PCMs) in thermal storage systems. PCMs use latent heat at the solid-liquid phase transition point to store thermal energy. They are considered to be useful as a thermal energy storage (TES) material because they can provide much higher energy storage densities compared to conventional sensible thermal storage materials. This paper reviewed the main disadvantages of using PCMs for energy storage, such as low heat transfer, super cooling and system design issues. Other issues with PCMs include incongruence and corrosion of heat exchanger surfaces. The authors suggested that in order to address these problems, future research should focus on maximizing heat transfer by optimizing the configuration of the encapsulation through a parametric analysis using a PCM numerical model. The effective conductivity in encapsulated PCMs in a latent heat thermal energy storage (LHTES) system can also be increased by using conductors in the encapsulation that have high thermal conductivity. 47 refs., 1 tab., 1 fig.

Korean interim storage issues and R and D activities on spent fuel management

International Nuclear Information System (INIS)

Ji Sup Yoon; Seung-Gy Ro; Hyun-Soo Park

1999-01-01

Korea has witnessed over a decade of vicissitudes in the issue of radioactive waste management due mainly to the problem of site acquisition. As the major mission of the nation at radioactive waste management programme was to provide a center for disposal of low-level radwaste and for interim storage of spent nuclear fuel from nuclear power plants, the question of site securing has had a big impact on the implement action of overall programme. The site problem has resulted in, as an aftermath, restructuring of the overall programme for radioactive waste management. Missions of NEMAC (Nuclear Environment Management Center), originally established as a subsidiary of Korea Atomic Energy Research Institute (KAERI), for the national programme was dissolved as of the end of last year. Beginning of this year, a new entity NETEC (Nuclear Environment Technology Center) as a subsidiary of KEPCO (Korea Electric Power Co.) has taken over major tasks of the past NEMAC, while the R and D work associated with the past task of NEMAC is transferred back to KAERI. This paper gives a review on the past background which has driven the radioactive waste management in Korea to the current state of the affairs, with special emphasis on R and D activities associated with spent nuclear fuel transportation, handling, and storage. (author)

Modeling of hydrogen/deuterium dynamics and heat generation on palladium nanoparticles for hydrogen storage and solid-state nuclear fusion.

Science.gov (United States)

Tanabe, Katsuaki

2016-01-01

We modeled the dynamics of hydrogen and deuterium adsorbed on palladium nanoparticles including the heat generation induced by the chemical adsorption and desorption, as well as palladium-catalyzed reactions. Our calculations based on the proposed model reproduce the experimental time-evolution of pressure and temperature with a single set of fitting parameters for hydrogen and deuterium injection. The model we generated with a highly generalized set of formulations can be applied for any combination of a gas species and a catalytic adsorbent/absorbent. Our model can be used as a basis for future research into hydrogen storage and solid-state nuclear fusion technologies.

A solar receiver-storage modular cascade based on porous ceramic structures for hybrid sensible/thermochemical solar energy storage

Science.gov (United States)

Agrafiotis, Christos; de Oliveira, Lamark; Roeb, Martin; Sattler, Christian

2016-05-01

The current state-of-the-art solar heat storage concept in air-operated Solar Tower Power Plants is to store the solar energy provided during on-sun operation as sensible heat in porous solid materials that operate as recuperators during off-sun operation. The technology is operationally simple; however its storage capacity is limited to 1.5 hours. An idea for extending this capacity is to render this storage concept from "purely" sensible to "hybrid" sensible/ thermochemical one, via coating the porous heat exchange modules with oxides of multivalent metals for which their reduction/oxidation reactions are accompanied by significant heat effects, or by manufacturing them entirely of such oxides. In this way solar heat produced during on-sun operation can be used (in addition to sensibly heating the porous solid) to power the endothermic reduction of the oxide from its state with the higher metal valence to that of the lower; the thermal energy can be entirely recovered by the reverse exothermic oxidation reaction (in addition to sensible heat) during off-sun operation. Such sensible and thermochemical storage concepts were tested on a solar-irradiated receiver- heat storage module cascade for the first time. Parametric studies performed so far involved the comparison of three different SiC-based receivers with respect to their capability of supplying solar-heated air at temperatures sufficient for the reduction of the oxides, the effect of air flow rate on the temperatures achieved within the storage module, as well as the comparison of different porous storage media made of cordierite with respect to their sensible storage capacity.

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

Fluid bed dryer and Aeropep solidification system. Amendment 1 to topical report

International Nuclear Information System (INIS)

1975-01-01

Information is presented on interfaces between the aerojet fluid bed dryer and the liquid radwaste system, plant ventilation system, and radioactive solid waste handling system for BWR and PWR type reactors. (U.S.)

40 CFR 761.63 - PCB household waste storage and disposal.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 30 2010-07-01 2010-07-01 false PCB household waste storage and..., AND USE PROHIBITIONS Storage and Disposal § 761.63 PCB household waste storage and disposal. PCB... to manage municipal or industrial solid waste, or in a facility with an approval to dispose of PCB...

A solar receiver-storage modular cascade based on porous ceramic structures for hybrid sensible/thermochemical solar energy storage

OpenAIRE

Agrafiotis, Christos; de Oliveira, Lamark; Roeb, Martin; Sattler, Christian

2016-01-01

The current state-of-the-art solar heat storage concept in air-operated Solar Tower Power Plants is to store the solar energy provided during on-sun operation as sensible heat in porous solid materials that operate as recuperators during off-sun operation. The technology is operationally simple; however its storage capacity is limited to 1.5 hours. An idea for extending this capacity is to render this storage concept from “purely” sensible to “hybrid” sensible/ thermochemical one, via coating...

Site characterization data for Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Boegly, W.J. Jr.

1984-12-01

Currently, the only operating shallow land burial site for low-level radioactive waste at the Oak Ridge National Laboratory (ORNL) is Solid Waste Storage Area No. 6 (SWSA-6). In 1984, the US Department of Energy (DOE) issued Order 5820.2, Radioactive Waste Management, which establishes policies and guidelines by which DOE manages its radioactive waste, waste by-products, and radioactively contaminated surplus facilities. The ORNL Operations Division has given high priority to characterization of SWSA-6 because of the need for continued operation under DOE 5820.2. The purpose of this report is to compile existing information on the geologic and hydrologic conditions in SWSA-6 for use in further studies related to assessing compliance with 5820.2. Burial operations in SWSA-6 began in 1969 on a limited scale, and full operation was initiated in 1973. Since that time, ca. 29,100 m 3 of low-level waste containing ca. 251,000 Ci of activity has been buried in SWSA-6. No transuranic waste has been disposed of in SWSA-6; rather this waste is retrievably stored in SWSA-5. Estimates of the remaining usable space in SWSA-6 vary; however, in 1982 sufficient useful land was reported for about 10 more years of operation. Analysis of the information available on SWSA-6 indicates that more information is required to evaluate the surface water hydrology, the geology at depths below the burial trenches, and the nature and extent of soils within the site. Also, a monitoring network will be required to allow detection of potential contaminant movement in groundwater. Although these are the most obvious needs, a number of specific measurements must be made to evaluate the spatial heterogeneity of the site and to provide background information for geohydrological modeling. Some indication of the nature of these measurements is included

ORNL Solid Waste Storage Area 6 trench photos and geologic descriptions, July 1984-September 1985

International Nuclear Information System (INIS)

Davis, E.C.; Marshall, D.S.; Stansfield, R.G.; Dreier, R.B.

1986-03-01

The Environmental Sciences Division of the Oak Ridge National Laboratory has initiated a photographic and descriptive geologic study of low-level waste trenches opened in Solid Waste Storage Area 6 (SWSA-6). From July 1984 through September 1985, trenches were excavated, geologically described, and photographed before being filled and closed. Only three trenches (Nos. 438, 448, and 465) were excavated and closed before photography could be scheduled. It is recommended that the systematic trench characterization procedure outlined in this report be continued under the direction of ORNL's Operations Division with support from both Environmental Sciences and the Engineering divisions. Publication of such a compilation of trench photos on a yearly basis will serve not only as a part of Department of Energy trench documentation requirements but also as a component of a SWSA-6 geologic data base being developed for current research and development activities. 2 refs., 38 figs

Form-stable paraffin/high density polyethylene composites as solid-liquid phase change material for thermal energy storage: preparation and thermal properties

International Nuclear Information System (INIS)

Sari, Ahmet

2004-01-01

This paper deals with the preparation of paraffin/high density polyethylene (HDPE) composites as form-stable, solid-liquid phase change material (PCM) for thermal energy storage and with determination of their thermal properties. In such a composite, the paraffin (P) serves as a latent heat storage material and the HDPE acts as a supporting material, which prevents leakage of the melted paraffin because of providing structural strength. Therefore, it is named form-stable composite PCM. In this study, two kinds of paraffins with melting temperatures of 42-44 deg. C (type P1) and 56-58 deg. C (type P2) and latent heats of 192.8 and 212.4 J g -1 were used. The maximum weight percentage for both paraffin types in the PCM composites without any seepage of the paraffin in the melted state were found as high as 77%. It is observed that the paraffin is dispersed into the network of the solid HDPE by investigation of the structure of the composite PCMs using a scanning electronic microscope (SEM). The melting temperatures and latent heats of the form-stable P1/HDPE and P2/HDPE composite PCMs were determined as 37.8 and 55.7 deg. C, and 147.6 and 162.2 J g -1 , respectively, by the technique of differential scanning calorimetry (DSC). Furthermore, to improve the thermal conductivity of the form-stable P/HDPE composite PCMs, expanded and exfoliated graphite (EG) by heat treatment was added to the samples in the ratio of 3 wt.%. Thereby, the thermal conductivity was increased about 14% for the form-stable P1/HDPE and about 24% for the P2/HDPE composite PCMs. Based on the results, it is concluded that the prepared form-stable P/HDPE blends as composite type PCM have great potential for thermal energy storage applications in terms of their satisfactory thermal properties and improved thermal conductivity. Furthermore, these composite PCMs added with EG can be considered cost effective latent heat storage materials since they do not require encapsulation and extra cost to enhance

Advanced methods for incineration of solid, burnable LLW and melting for recycling of scrap metals

International Nuclear Information System (INIS)

Krause, G.; Lorenzen, J.; Lindberg, M.; Olsson, L.; Wirendal, B.

2003-01-01

Radioactive contaminated waste is a great cost factor for nuclear power plants and other nuclear industry. On the deregulated electricity market the price on produced kWh is an important competition tool. Therefore the waste minimisation and volume reduction has given highest priority by many power producers in the process to achieve savings and hence low production cost. Studsvik RadWaste AB in Nykoeping, Sweden, is a company specialised in volume reduction of LLW, as solid combustible waste and as scrap metal for melting and recycling. The treatment facility in Sweden offers this kind of services - together with segmentation and decontamination when necessary - for several customers from Europe, Japan and USA. In addition to these treatment services a whole spectrum of services like transportation, measurement and safeguard, site assistance, industrial cleaning and decontamination in connection with demolition at site is offered from the Studsvik company. (orig.)

A method and apparatus for preparing the storage of noxious substances, in particular radioactive substances

International Nuclear Information System (INIS)

1974-01-01

The invention relates to the storage of radioactive substances. It deals with a method for storing a substance, in particular a noxious or radioactive substance, comprising trapping said substance in a solid substance by bombarding said solid substance with ions of the above substance, so that the latter reaches a certain concentration level in the solid substance. This is applicable to the storage of radioactive wastes [fr

Recent Progress and New Perspectives on Metal Amide and Imide Systems for Solid-State Hydrogen Storage

Directory of Open Access Journals (Sweden)

Sebastiano Garroni

2018-04-01

Full Text Available Hydrogen storage in the solid state represents one of the most attractive and challenging ways to supply hydrogen to a proton exchange membrane (PEM fuel cell. Although in the last 15 years a large variety of material systems have been identified as possible candidates for storing hydrogen, further efforts have to be made in the development of systems which meet the strict targets of the Fuel Cells and Hydrogen Joint Undertaking (FCH JU and U.S. Department of Energy (DOE. Recent projections indicate that a system possessing: (i an ideal enthalpy in the range of 20–50 kJ/mol H2, to use the heat produced by PEM fuel cell for providing the energy necessary for desorption; (ii a gravimetric hydrogen density of 5 wt. % H2 and (iii fast sorption kinetics below 110 °C is strongly recommended. Among the known hydrogen storage materials, amide and imide-based mixtures represent the most promising class of compounds for on-board applications; however, some barriers still have to be overcome before considering this class of material mature for real applications. In this review, the most relevant progresses made in the recent years as well as the kinetic and thermodynamic properties, experimentally measured for the most promising systems, are reported and properly discussed.

Modeling of hydrogen/deuterium dynamics and heat generation on palladium nanoparticles for hydrogen storage and solid-state nuclear fusion

Directory of Open Access Journals (Sweden)

Katsuaki Tanabe

2016-01-01

Full Text Available We modeled the dynamics of hydrogen and deuterium adsorbed on palladium nanoparticles including the heat generation induced by the chemical adsorption and desorption, as well as palladium-catalyzed reactions. Our calculations based on the proposed model reproduce the experimental time-evolution of pressure and temperature with a single set of fitting parameters for hydrogen and deuterium injection. The model we generated with a highly generalized set of formulations can be applied for any combination of a gas species and a catalytic adsorbent/absorbent. Our model can be used as a basis for future research into hydrogen storage and solid-state nuclear fusion technologies.

Hydrogen storage in graphitic nanofibres

OpenAIRE

McCaldin, Simon Roger

2007-01-01

There is huge need to develop an alternative to hydrocarbons fuel, which does not produce CO2 or contribute to global warming - 'the hydrogen economy' is such an alternative, however the storage of hydrogen is the key technical barrier that must be overcome. The potential of graphitic nanofibres (GNFs) to be used as materials to allow the solid-state storage of hydrogen has thus been investigated. This has been conducted with a view to further developing the understanding of the mechanism(s) ...

Physical principles and current status of emerging non-volatile solid state memories

Science.gov (United States)

Wang, L.; Yang, C.-H.; Wen, J.

2015-07-01

Today the influence of non-volatile solid-state memories on persons' lives has become more prominent because of their non-volatility, low data latency, and high robustness. As a pioneering technology that is representative of non-volatile solidstate memories, flash memory has recently seen widespread application in many areas ranging from electronic appliances, such as cell phones and digital cameras, to external storage devices such as universal serial bus (USB) memory. Moreover, owing to its large storage capacity, it is expected that in the near future, flash memory will replace hard-disk drives as a dominant technology in the mass storage market, especially because of recently emerging solid-state drives. However, the rapid growth of the global digital data has led to the need for flash memories to have larger storage capacity, thus requiring a further downscaling of the cell size. Such a miniaturization is expected to be extremely difficult because of the well-known scaling limit of flash memories. It is therefore necessary to either explore innovative technologies that can extend the areal density of flash memories beyond the scaling limits, or to vigorously develop alternative non-volatile solid-state memories including ferroelectric random-access memory, magnetoresistive random-access memory, phase-change random-access memory, and resistive random-access memory. In this paper, we review the physical principles of flash memories and their technical challenges that affect our ability to enhance the storage capacity. We then present a detailed discussion of novel technologies that can extend the storage density of flash memories beyond the commonly accepted limits. In each case, we subsequently discuss the physical principles of these new types of non-volatile solid-state memories as well as their respective merits and weakness when utilized for data storage applications. Finally, we predict the future prospects for the aforementioned solid-state memories for

Liquid radwaste processing with spiral wound reverse osmosis

International Nuclear Information System (INIS)

Sengupta, S.K.; Buckley, L.P.; Rimpelainen, S.; Tremblay, A.Y.

1996-05-01

Two different reverse osmosis systems were investigated. The first was a 50-element plant-scale system that is used to treat 2200 m 3 of AECL liquid radwastes annually.It uses thin-film composite (TFC) membranes and operates at an applied pressure of 2760 kPa, with a fixed crossflow of about 40 L/min. The other system uses the same thin-film composite membranes for waste processing but is a two-element pilot-scale system. It is operated at pressures m ranging between 1500 and 7000 kPa, at a fixed crossflow of 55 L/min. The average lifetime of the thin-film composite membranes in the plant-scale processing application at AECL is about 3000 h. After this service life has expired the rejection efficiency declines rapidly from 99.5% to about 95% as the membranes become impaired from chemical cleaning procedures that are required after each 100 m 3 of waste is treated. The permeation flux for the plant-scale system decreases from about 2.2 L/min/element to below 0.5 L/min/element at the end of the membrane's useful service life. The plant-scale membrane elements, fouled by an assortment of chemicals including calcium phosphate and various organics, were successfully regenerated by exposing them to a threestep chemical cleaning procedure, using detergent, HCI, and an alkaline-based cleaning with EDTA. The three-step procedure was successful in elevating the flux from 0.5 L/min for the spent membrane to 1.2 L/min after cleaning. The 1.2-L/min postcleaning flux could be maintained provided that the crossflow velocity remained high. The decontamination factor (DF) for cesium for the plant-scale system, decreased from about 100 when the membranes were new, to about 30 after they were replaced. The strontium DF was unaffected by the applied pressure. 9 refs., 1 tab., 6 figs

Assessment of Hanford burial grounds and interim TRU storage

International Nuclear Information System (INIS)

Geiger, J.F.; Brown, D.J.; Isaacson, R.E.

1977-08-01

A review and assessment is made of the Hanford low level solid radioactive waste management sites and facilities. Site factors considered favorable for waste storage and disposal are (1) limited precipitation, (2) a high deficiency of moisture in the underlying sediments (3) great depth to water table, all of which minimize radionuclide migration by water transport, and (4) high sorbtive capacity of the sediments. Facilities are in place for 20 year retrievable storage of transuranic (TRU) wastes and for disposal of nontransuranic radioactive wastes. Auxiliary facilities and services (utilities, roads, fire protection, shops, etc.) are considered adequate. Support staffs such as engineering, radiation monitoring, personnel services, etc., are available and are shared with other operational programs. The site and associated facilities are considered well suited for solid radioactive waste storage operations. However, recommendations are made for study programs to improve containment, waste package storage life, land use economy, retrievability and security of TRU wastes

Boron-Based Hydrogen Storage: Ternary Borides and Beyond

Energy Technology Data Exchange (ETDEWEB)

Vajo, John J. [HRL Laboratories, LLC, Malibu, CA (United States)

2016-04-28

DOE continues to seek reversible solid-state hydrogen materials with hydrogen densities of ≥11 wt% and ≥80 g/L that can deliver hydrogen and be recharged at moderate temperatures (≤100 °C) and pressures (≤100 bar) enabling incorporation into hydrogen storage systems suitable for transportation applications. Boron-based hydrogen storage materials have the potential to meet the density requirements given boron’s low atomic weight, high chemical valance, and versatile chemistry. However, the rates of hydrogen exchange in boron-based compounds are thus far much too slow for practical applications. Although contributing to the high hydrogen densities, the high valance of boron also leads to slow rates of hydrogen exchange due to extensive boron-boron atom rearrangements during hydrogen cycling. This rearrangement often leads to multiple solid phases occurring over hydrogen release and recharge cycles. These phases must nucleate and react with each other across solid-solid phase boundaries leading to energy barriers that slow the rates of hydrogen exchange. This project sought to overcome the slow rates of hydrogen exchange in boron-based hydrogen storage materials by minimizing the number of solid phases and the boron atom rearrangement over a hydrogen release and recharge cycle. Two novel approaches were explored: 1) developing matched pairs of ternary borides and mixed-metal borohydrides that could exchange hydrogen with only one hydrogenated phase (the mixed-metal borohydride) and only one dehydrogenated phase (the ternary boride); and 2) developing boranes that could release hydrogen by being lithiated using lithium hydride with no boron-boron atom rearrangement.

Transmutation of actinides in power reactors.

Science.gov (United States)

Bergelson, B R; Gerasimov, A S; Tikhomirov, G V

2005-01-01

Power reactors can be used for partial short-term transmutation of radwaste. This transmutation is beneficial in terms of subsequent storage conditions for spent fuel in long-term storage facilities. CANDU-type reactors can transmute the main minor actinides from two or three reactors of the VVER-1000 type. A VVER-1000-type reactor can operate in a self-service mode with transmutation of its own actinides.

An effect of surface properties on detachment of adhered solid to cooling surface for formation of clathrate hydrate slurry

Science.gov (United States)

Daitoku, Tadafumi; Utaka, Yoshio

In air-conditioning systems, it is desirable that the liquid-solid phase change temperature of a cool energy storage material is approximately 10 °C from the perspective of improving coefficient of performance (COP). Moreover, a thermal storage material that forms slurry can realize large heat capacity of working fluids. Since the solid that adheres to the heat transfer surface forms a thermal resistance layer and remarkably reduces the rate of cold storage, it is important to avoid the adhesion of a thick solid layer on the surface so as to realize efficient energy storage. Considering a harvest type cooling unit, the force required for removing the solid phase from the heat transfer surface was studied. Tetra-n-butylammonium Bromide (TBAB) clathrate hydrate was used as a cold storage material. The effect of the heat transfer surface properties on the scraping force for detachment of adhered solid of TBAB hydrate to the heat transfer surface was examined experimentally.

Inside Solid State Drives (SSDs)

CERN Document Server

Micheloni, Rino; Eshghi, Kam

2013-01-01

Solid State Drives (SSDs) are gaining momentum in enterprise and client applications, replacing Hard Disk Drives (HDDs) by offering higher performance and lower power. In the enterprise, developers of data center server and storage systems have seen CPU performance growing exponentially for the past two decades, while HDD performance has improved linearly for the same period. Additionally, multi-core CPU designs and virtualization have increased randomness of storage I/Os. These trends have shifted performance bottlenecks to enterprise storage systems. Business critical applications such as online transaction processing, financial data processing and database mining are increasingly limited by storage performance. In client applications, small mobile platforms are leaving little room for batteries while demanding long life out of them. Therefore, reducing both idle and active power consumption has become critical. Additionally, client storage systems are in need of significant performance improvement as well ...

Radwaste minimization successes at Duke Power Company

International Nuclear Information System (INIS)

Lan, C.D.; Johnson, G.T.; Groves, D.C.; Smith, T.A.

1996-01-01

At Duke Power Company, open-quotes Culture Changeclose quotes is a common term that we have used to describe the incredible transformation. We are becoming a cost conscious, customer driven, highly competitive business. Nowhere has this change been more evident then in the way we process and dispose of our solid radioactive waste. With top-down management support, we have used team-based, formalized problem solving methods and have implemented many successful waste minimization programs. Through these programs, we have dramatically increased employees' awareness of the importance of waste minimization. As a result, we have been able to reduce both our burial volumes and our waste processing and disposal costs. In June, 1994, we invited EPRI to conduct assessments of our waste minimization programs at Oconee and Catawba nuclear stations. Included in the assessments were in-depth looks at contamination control, an inventory of items in the plant, the volume of waste generated in the plant and how it was processed, laundry reject data, site waste-handling operations, and plant open-quotes housekeepingclose quotes routines and process. One of the most important aspects of the assessment is the open-quotes dumpster dive,close quotes which is an evaluation of site dry active waste composition by sorting through approximately fifteen bags of radioactive waste. Finally, there was an evaluation of consumable used at each site in order to gain knowledge of items that could be standardized at all stations. With EPRI recommendations, we made several changes and standardized the items used. We have made significant progress in waste reduction. We realize, however, that we are aiming at a moving target and we still have room for improvement. As the price of processing and disposal (or storage) increases, we will continue to evaluate our waste minimization programs

Thermal energy storages analysis for high temperature in air solar systems

International Nuclear Information System (INIS)

Andreozzi, Assunta; Buonomo, Bernardo; Manca, Oronzio; Tamburrino, Salvatore

2014-01-01

In this paper a high temperature thermal storage in a honeycomb solid matrix is numerically investigated and a parametric analysis is accomplished. In the formulation of the model it is assumed that the system geometry is cylindrical, the fluid and the solid thermo physical properties are temperature independent and radiative heat transfer is taken into account whereas the effect of gravity is neglected. Air is employed as working fluid and the solid material is cordierite. The evaluation of the fluid dynamic and thermal behaviors is accomplished assuming the honeycomb as a porous medium. The Brinkman–Forchheimer–extended Darcy model is used in the governing equations and the local thermal non equilibrium is assumed. The commercial CFD Fluent code is used to solve the governing equations in transient regime. Numerical simulations are carried out with storage medium for different mass flow rates of the working fluid and different porosity values. Results in terms of temperature profiles, temperatures fields and stored thermal energy as function of time are presented. The effects of storage medium, different porosity values and mass flow rate on stored thermal energy and storage time are shown. - Highlights: • HTTES in a honeycomb solid matrix is numerically investigated. • The numerical analysis is carried out assuming the honeycomb as a porous medium. • The Brinkman–Forchheimer–extended Darcy model is used in the governing equations. • Results are carried out for different mass flow rates and porosity values. • The main effect is due to the porosity which set the thermal energy storage value

Characterization of polymer-modified cement as a solidification agent for the radwaste

International Nuclear Information System (INIS)

Ji, Young-Yong; Kwak, Kyung-Kil; Hong, Dae-Seok; Ryu, Woo-Seog

2012-01-01

Highlights: ► Polymer-modified cement (PMC) by modification with water-based resins. ► Determination of the optimized polymer content. ► Evaluation of the improved chemical resistance of the PMC. ► Decrease of the amount of ions released into the demineralized water. ► Highly improved property for the nuclide diffusivity at the Co-60. - Abstract: Polymer-modified cement can be produced by partially replacing cement hydrate binders in ordinary Portland cement with polymeric compounds. It is known that the addition of the polymer to the cement paste leads to improved quality, which would be expected to have a high chemical resistance. In order to investigate the application as a solidification agent for the radwaste, polymer-modified cement specimens, by modification with water-based resins, were prepared according to the polymer content from 0% to 30%. The optimized polymer content in the cement pastes was then determined through the compressive strength and the porosity test. Finally, the improved chemical resistance of the polymer-modified cement with the optimized polymer content was evaluated by the thermal cycling, the immersion, and the leaching tests. From the test results, the amount of ions released into the water showed lower values of about 20% at the polymer-modified cement. Especially, a highly improved nuclide diffusivity of Co-60 was observed in the polymer-modified cement.

Mobile liquid VR system: a cost effective alternative

International Nuclear Information System (INIS)

Soto, R.; Harkins, R.; HPD, Inc., Naperville, IL)

1985-01-01

The need for cost effective alternatives to treat large volumes of liquid radwaste has never been more evident. As part of a continuing effort to introduce such alternatives, HPD, Inc., and Chem-Nuclear Systems, Inc., have integrated two proven state-of-the-art technologies to offer a mobile liquid volume reduction system that satisfies nuclear industry requirements, with respect to liquid radwaste handling. This system optimizes proven technology by employing a crystallizer unit to concentrate the waste liquids to 50 weight percent solids, thereby reducing the volume to be solidified by factors of 40, while using only 20 percent of the energy required by conventional evaporative systems. In addition, the system employs a field proven cement solidification process which has been accepted in a Topical Report by the US NRC and which offers the highest waste to container volume ratios for stable waste forms in the industry. This volume reduction-solidification system is able to reduce over 7000 gallons of liquid waste per day to less than 30 cubic feet of 10CFR61 certified stable solidified waste for ultimate disposal or on-site storage. This document describes the GEODE System; its applicability; economics; volume reduction; scope of responsibility and experience. Major benefits include higher VR factors; assurance of continual regulatory compliance; and no capital investment

Low-level radioactive waste processing at nuclear power plants

International Nuclear Information System (INIS)

1992-12-01

The Solid Radwaste Processing Source Book is presented as a supplement to the Liquid Radwaste Source Book released in 1990 and updated in 1991. The publication is the result of an industry-wide survey, and is intended as a resource for technical and managerial decisions involving of the processing of solid radioactive waste including ''wet'' and ''dry'' active waste as found at both Pressurized and Boiling Water Reactor sites. In addition to information on processes, vendors, volumes, and in-plant management activities, technology under consideration for future use and computer applications are listed. Together with key personnel and contact information contained in the Liquid Source Books, the collected data will be of great use when seeking specific, unbiased experience on which to base decisions related to so processing, disposal policy, or potential economic and regulatory impact

Porous polymeric materials for hydrogen storage

Science.gov (United States)

Yu, Luping; Liu, Di-Jia; Yuan, Shengwen; Yang, Junbing

2013-04-02

A porous polymer, poly-9,9'-spirobifluorene and its derivatives for storage of H.sub.2 are prepared through a chemical synthesis method. The porous polymers have high specific surface area and narrow pore size distribution. Hydrogen uptake measurements conducted for these polymers determined a higher hydrogen storage capacity at the ambient temperature over that of the benchmark materials. The method of preparing such polymers, includes oxidatively activating solids by CO.sub.2/steam oxidation and supercritical water treatment.

The new MAW scrap processing facility

International Nuclear Information System (INIS)

Kueppers, L.

1994-01-01

The shielded bunker for heat-generating waste attached to the MAW scrap processing cell will be modified and extended to comprise several MAW scrap processing cells of enhanced throughput capacity, and a new building to serve as an airlock and port for acceptance of large shipping casks (shipping cask airlock, TBS). The new facility is to process scrap from decommissioned nuclear installations, and in addition radwaste accrued at operating plants of utilities. This will allow efficient and steady use of the new MAW scrap processing facility. The planning activities for modification and extension are based on close coordination between KfK and the GNS mbH, in order to put structural dimensioning and capacity planning on a realistic basis in line with expected amounts of radwaste from operating nuclear installations of utilities. The paper indicates the currently available waste amount assessments covering solid radwaste (MAW) from the decommissioning of the WAK, MZFR, and KNK II, and existing waste amounts consisting of core internals of German nuclear power plant. The figures show that the MAW scrap processing facility will have to process an overall bulk of about 1100 Mg of solid waste over the next ten years to come. (orig./HP) [de

Groundwater quality monitoring well installation for waste area grouping 7 and solid waste storage area 1, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Mortimore, J.A.; Ebers, M.L.

1994-09-01

The purpose of this report is to document the drilling and installation of the groundwater quality monitoring (GQM) wells on the perimeter of Waste Area Grouping (WAG) 7 and at Solid Waste Storage Area (SWSA) 1, which is a part of WAG 1. Installation of GQM wells was required at Oak Ridge National Laboratory (ORNL) for regulatory compliance. Data obtained from these wells will be used to characterize and assess groundwater quality at the perimeter of each WAG in accordance with applicable Department of Energy, state, and Environmental Protection Agency regulatory requirements. The wells in WAG 7 and SWSA 1 were drilled and developed during the period from June 1989 to March 1990

JOINTS AND SYN-SEDIMENTARY FAULTS NETWORKS IN MARINE CLAYS AND MUDSTONES. Importance for Radwaste storage

Science.gov (United States)

Arnould, M.

2009-12-01

material with rather small throws are difficult to identify. Their number increases wifh accuracy of geophysical research. Conclusions for underground storage of radioactive waste . There are four underground laboratories on duty in mudstones and clays in Western Europe. No natural discontinuities, joints or faults have been observed during their excavation rapidly followed by lining.This draw some people to the imprudent conclusion that there were no natural discontinuities. In accordance to the very low permeabilities measured by in situ tests all natural discontinuities are closed up at depth by the stresss field. They are sealed but not healed because the temperature of diagenesis remained below 50°C. They can reopen by relaxation of stresses and by desiccation, as in Tournemire tunnel /URL in toarcian mudstones and at Mont Terri URL in Opalinus Clay. Open fissures visible in non lined parts of galleries appear weeks or months after the excavation. After the change of concept from burial to storage and retrievability the problem should not be underestimated. References : Arnould M (2006) Discontinuity networks in mudstones : a geological approach. Bull Eng Geol Environ. Springer ed 65:413-422 Skempton & al (1969) Joints and fissures in the London Clay at Wraysbury and Edgware Geotechnique 19 : 205-217.

High-Capacity Hydrogen-Based Green-Energy Storage Solutions For The Grid Balancing

Science.gov (United States)

D'Errico, F.; Screnci, A.

One of the current main challenges in green-power storage and smart grids is the lack of effective solutions for accommodating the unbalance between renewable energy sources, that offer intermittent electricity supply, and a variable electricity demand. Energy management systems have to be foreseen for the near future, while they still represent a major challenge. Integrating intermittent renewable energy sources, by safe and cost-effective energy storage systems based on solid state hydrogen is today achievable thanks to recently some technology breakthroughs. Optimized solid storage method made of magnesium-based hydrides guarantees a very rapid absorption and desorption kinetics. Coupled with electrolyzer technology, high-capacity storage of green-hydrogen is therefore practicable. Besides these aspects, magnesium has been emerging as environmentally friend energy storage method to sustain integration, monitoring and control of large quantity of GWh from high capacity renewable generation in the EU.

Modular Firewalls for Storage Areas

Science.gov (United States)

Fedor, O. H.; Owens, L. J.

1986-01-01

Giant honeycomb structures assembled in modular units. Flammable materials stored in cells. Walls insulated with firebrick to prevent spread of fire among cells. Portable, modular barrier withstands heat of combustion for limited time and confines combustion products horizontally to prevent fire from spreading. Barrier absorbs heat energy by ablation and not meant to be reused. Designed to keep fires from spreading among segments of solid rocket propellant in storage, barrier erected between storage units of other flammable or explosive materials; tanks of petroleum or liquid natural gas. Barrier adequate for most industrial purposes.

Improving hydrogen storage in Ni-doped carbon nanospheres

Energy Technology Data Exchange (ETDEWEB)

Zubizarreta, L.; Menendez, J.A.; Pis, J.J.; Arenillas, A. [Instituto Nacional del Carbon, CSIC, Apartado 73, 33080 Oviedo (Spain)

2009-04-15

The effect of nickel distribution and content in Ni-doped carbon nanospheres on hydrogen storage capacity under conditions of moderate temperature and pressure was studied. It was found that the nickel distribution, obtained by using different doping techniques and conditions, has a noticeable influence on hydrogen storage capacity. The samples with the most homogeneous nickel distribution, obtained by pre-oxidising the carbon nanospheres, displayed the highest storage capacity. In addition, storage capacity is influenced by the amount of nickel. It was found a higher storage capacity in samples containing 5 wt.% of Ni. This is due to the greater interactions between the nickel and the support that produce a higher activation of the solid through a spillover effect. (author)

Research and development of radioactive waste treatment methods

International Nuclear Information System (INIS)

Nguyen Thi Nang

2000-01-01

The Nuclear Research Institute (NRI) uses the reactor for research, training, isotope production and activation analyses. NRI generates about 150 m 3 of liquid and 5 m 3 of solid wastes every year. The researched methods applied to treatment of radwastes are coagulation-precipitation and two steps ion-exchange for liquid waste and compaction for solid waste are described. (author)

Graphene Based Ultra-Capacitors for Safer, More Efficient Energy Storage

Science.gov (United States)

Roberson, Luke B.; Mackey, Paul J.; Zide, Carson J.

2016-01-01

Current power storage methods must be continuously improved in order to keep up with the increasingly competitive electronics industry. This technological advancement is also essential for the continuation of deep space exploration. Today's energy storage industry relies heavily on the use of dangerous and corrosive chemicals such as lithium and phosphoric acid. These chemicals can prove hazardous to the user if the device is ruptured. Similarly they can damage the environment if they are disposed of improperly. A safer, more efficient alternative is needed across a wide range of NASA missions. One solution would a solid-state carbon based energy storage device. Carbon is a safer, less environmentally hazardous alternative to current energy storage materials. Using the amorphous carbon nanostructure, graphene, this idea of a safer portable energy is possible. Graphene was electrochemically produced in the lab and several coin cell devices were built this summer to create a working prototype of a solid-state graphene battery.

Solid forms for Savannah River Plant radioactive wastes

International Nuclear Information System (INIS)

Wallace, R.M.; Hale, W.H.; Bradley, R.F.; Hull, H.L.; Kelley, J.A.; Stone, J.A.; Thompson, G.H.

1976-01-01

Methods are being developed to immobilize Savannah River Plant wastes in solid forms such as cement, asphalt, or glass. 137 Cs and 90 Sr are the major biological hazards and heat producers in the alkaline wastes produced at SRP. In the conceptual process being studied, 137 Cs removed from alkaline supernates, together with insoluble sludges that contain 90 Sr, will be incorporated into solid forms of high integrity and low volume suitable for storage in a retrievable surface storage facility for about 100 years, and for eventual shipment to an off-site repository. Mineralization of 137 Cs, or its fixation on zeolite prior to incorporation into solid forms, is also being studied. Economic analyses to reduce costs and fault-tree analyses to minimize risks are being conducted. Methods are being studied for removal of sludge from (and final decontamination of) waste tanks

Solid waste and the water environment in the new European Union perspective. Process analysis related to storage and final disposal

Energy Technology Data Exchange (ETDEWEB)

Marques, Marcia [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Chemical Engineering and Technology

2000-11-01

Processes that occur during storage and final disposal of solid waste were studied, with emphasis on physical and chemical aspects and their effects on the water environment, within the New European Union perspective for landfilling (Council Directive 1999/31/EC of 26 April 1999). In the new scenario, landfilling is largely restricted; waste treatments such as incineration, composting, recycling, storage and transportation of materials are intensified. Landfill sites are seen as industrial facilities rather than merely final disposal sites. Four main issues were investigated within this new scenario, in field- and full-scale, mostly at Spillepeng site, southern Sweden. (1) Adequacy of storage piles: Regarding the increasing demand for waste storage as fuel, the adequacy of storage in piles was investigated by monitoring industrial waste (IND) fuel compacted piles. Intense biodegradation activity, which raised the temperature into the optimum range for chemical oxidation reactions, was noticed during the first weeks. After about six months of storage, self-ignition occurred in one IND pile and one refuse derived fuel (RDF) pile. Heat, O{sub 2} and CO{sub 2} distribution at different depths of the monitored IND pile suggested that natural convection plays an important role in the degradation process by supplying oxygen and releasing heat. Storage techniques that achieve a higher degree of compaction, such as baling, are preferable to storage in piles. ( 2) Discharge from landfill for special waste: Regarding changes in the composition of the waste sent to landfills and the consequences for its hydrological performance in active and capped landfills, discharge from a full-scale landfill for special/hazardous waste (predominantly fly ash from municipal solid waste (MSW) incineration) was modelled using the U.S. EPA HELP model. Hydraulic properties of the special waste were compared with those from MSW. Lower practical field capacity and higher hydraulic conductivity at

Solid waste and the water environment in the new European Union perspective. Process analysis related to storage and final disposal

Energy Technology Data Exchange (ETDEWEB)

Marques, Marcia [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Chemical Engineering and Technology

2000-11-01

Processes that occur during storage and final disposal of solid waste were studied, with emphasis on physical and chemical aspects and their effects on the water environment, within the New European Union perspective for landfilling (Council Directive 1999/31/EC of 26 April 1999). In the new scenario, landfilling is largely restricted; waste treatments such as incineration, composting, recycling, storage and transportation of materials are intensified. Landfill sites are seen as industrial facilities rather than merely final disposal sites. Four main issues were investigated within this new scenario, in field- and full-scale, mostly at Spillepeng site, southern Sweden. (1) Adequacy of storage piles: Regarding the increasing demand for waste storage as fuel, the adequacy of storage in piles was investigated by monitoring industrial waste (IND) fuel compacted piles. Intense biodegradation activity, which raised the temperature into the optimum range for chemical oxidation reactions, was noticed during the first weeks. After about six months of storage, self-ignition occurred in one IND pile and one refuse derived fuel (RDF) pile. Heat, O{sub 2} and CO{sub 2} distribution at different depths of the monitored IND pile suggested that natural convection plays an important role in the degradation process by supplying oxygen and releasing heat. Storage techniques that achieve a higher degree of compaction, such as baling, are preferable to storage in piles. ( 2) Discharge from landfill for special waste: Regarding changes in the composition of the waste sent to landfills and the consequences for its hydrological performance in active and capped landfills, discharge from a full-scale landfill for special/hazardous waste (predominantly fly ash from municipal solid waste (MSW) incineration) was modelled using the U.S. EPA HELP model. Hydraulic properties of the special waste were compared with those from MSW. Lower practical field capacity and higher hydraulic conductivity at

Evaluation of volatile profiles obtained for minimally-processed pineapple fruit samples during storage by headspace-solid phase microextraction gas chromatography-mass spectrometry

Directory of Open Access Journals (Sweden)

Francielle Crocetta TURAZZI

Full Text Available Abstract This paper describes the application of the solid-phase microextraction (SPME technique for the determination and monitoring of the volatile profile of minimally-processed pineapple fruit stored at various temperatures (-12 °C, 4 °C and 25 °C for different periods (1, 4 and 10 days. The SPME fiber coating composed of Car/PDMS presented the best performance. The optimal extraction conditions obtained through a Doehlert design were 60 min at 35 °C. The profiles for the volatile compounds content of the fruit at each stage of storage were determined by gas chromatography-mass spectrometry (GC-MS. The variation in the volatile profile over time was greater when the fruit samples were stored at 25 °C and at -12 °C compared to 4 °C. Thus, according to the volatile profiles associated with the storage conditions evaluated in this study, packaged pineapple retains best its fresh fruit aroma when stored at 4 °C.

Management of industrial solid residues; Gerenciamento de residuos solidos industriais

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This chapter gives an overview on the management of industrial solid wastes, approaching the following subjects: classification of industrial solid residues; directives and methodologies for the management of industrial solid residues; instruments for the management of industrial solid residues; handling, packing, storage and transportation; treatment of industrial solid residues; final disposal - landfill for industrial residues; the problem of treatment and final disposer of domestic garbage in Brazil; recycling of the lubricant oils used in brazil; legislation.

Multi-Purpose Storage Complex description

International Nuclear Information System (INIS)

Nyman, D.H.

1993-01-01

The Multi-Purpose Storage Complex will provide interim storage of radioactive material (irradiated fuel, cesium/strontium capsules, plutonium residuals, canisters of vitrified high-level waste glass, and other radioactive material) at the Hanford Site near Richland, Washington. A Storage Preparation and Shipping Facility is included that will have the capability to stabilize failed metal fuel, segregate high-level solid waste, and package/repackage any of the materials for interim storage/final disposal or subsequent processing. Current technology, both domestic and foreign, will be adapted with the expectation that no new technology will be required. This cost-effective approach will use fuel casks, transport systems, and/or modular vaults that have been licensed in the United States. The complex will have a central control room, and appropriate safeguards and security measures will be incorporated. A specific design objective will be to minimize the amount of secondary waste

Study of Baffle Boundary and System Parameters on Liquid-Solid Coupling Vibration of Rectangular Liquid-Storage Structure

Directory of Open Access Journals (Sweden)

Wei Jing

2016-01-01

Full Text Available In order to study the vibration problem of liquid-solid coupling of rectangular liquid-storage structure with horizontal elastic baffle, ignoring the influence of surface gravity wave, two different velocity potential functions corresponding to the liquid above and below the elastic baffle are assumed; based on the theory of mathematical equation and energy method, the formulas of basic frequency of liquid-solid coupling vibration system are derived, the baffle joined to the tank wall with 3 kinds of boundary conditions, namely, four edges simply supported, two opposite edges clamped and two opposite edges simply supported, and four edges clamped; the influence rules of baffle length-width ratio, the ratio of baffle height to liquid level, baffle elastic modulus, baffle density, baffle thickness, and liquid density on the coupling vibration performance are studied. The results show that the frequency of the clamped boundary is minimum; the influences of baffle length-width ratio and relative height on the basic frequency are much greater than that of the other system parameters; the relation between baffle length-width ratio and the frequency is exponential, while baffle relative height has a parabola relation with the frequency; the larger the baffle length-width ratio, the closer the baffle to the liquid level; the coupling frequency will be reduced more obviously.

Households willingness to pay for improved solid waste management

Directory of Open Access Journals (Sweden)

S. Akhtar

2017-04-01

Full Text Available Waste is a byproduct of human life. Nowadays, municipal solid waste is being produced in excessive amounts and in this way, both developing and developed countries are facing challenges regarding generation of waste. Economic development, urbanization and improved living standards in cities have contributed to increase in the amount and complexity of solid waste produced. The present study was conducted in the residential area of main Boulevard Gulberg, Lahore to determine the present methods and efficiency of current solid waste management facility and to estimate the willingness of the selected households to pay for the improvement of solid waste management through questionnaire survey. It was found that current Solid waste management system in the area is fair but needs more improvement in terms of improved collection efficiency and rates, recycling bins, and segregation of waste at storage. According to the questionnaire survey, majority of the respondents despite belonging to middle class incomes are willing to pay an amount less than USD 4.8 for the improvement of waste management facility in the area. The area lacks frequent collection of waste containers. Therefore, there is a need for upgradation of storage and collection facilities in terms of increase in collection efficiency and rates, introduction of recycling facility and segregation of waste at source. Waste storage and collection sites of the area should be monitored periodically and waste should be disposed of in a scientific manner in sanitary landfills.

Integration of a municipal solid waste gasification plant with solid oxide fuel cell and gas turbine

DEFF Research Database (Denmark)

Bellomare, Filippo; Rokni, Masoud

2013-01-01

An interesting source of producing energy with low pollutants emission and reduced environmental impact are the biomasses; particularly using Municipal Solid Waste (MSW) as fuel, can be a competitive solution not only to produce energy with negligible costs but also to decrease the storage...... in landfills. A Municipal Solid Waste Gasification Plant Integrated with Solid Oxide Fuel Cell (SOFC) and Gas Turbine (GT) has been studied and the plant is called IGSG (Integrated Gasification SOFC and GT). Gasification plant is fed by MSW to produce syngas by which the anode side of an SOFC is fed wherein...

Assessment of DOE low-level radioactive solid waste disposal storage activities: task 103. Final report

International Nuclear Information System (INIS)

Duguid, J.O.

1977-01-01

From a survey of DOE sites, facilities, and practices for the disposal/storage of low-level radioactive solid waste, the following can be summarized: (1) No health hazard has been reported. (2) Some burial grounds are releasing small quantities of radionuclides to the immediate environment. These releases are well within release limits at all sites with the exception of on-site concentrations at ORNL. At ORNL, concentrations in the Clinch River are less than 1% of the release limits. (3) Many practices have been instituted in the last few years which have improved disposal/storage operations considerably. The most notable are: (a) improved record keeping and a centralized computer data file, (b) improved burial site surface maintenance and drainage control, (c) initiation of the use of waste compactors and current plans for their use at most burial sites, (d) initiation of studies at major sites for evaluation of the long-term impact of buried waste, (e) improvement of modeling/monitoring programs at all major sites, (f) initiation of studies to provide engineering methods of reducing burial ground discharges at ORNL, and (g) initiation of the shallow land burial technologoy program.Overall, the low-level waste is being disposed of and stored in a safe and orderly manner. Recent and planned improvements will provide increased environmental protection. The only unsatisfactory area involves record keeping. Records of waste buried years ago are either poor or nonexistent. This makes it very difficult to evaluate the total impact of some 30 years of disposal operations. While some of this important history is lost forever, projects now under way should be able to reconstruct most of it

Slow heat release - solid fuel stove with acetat-trihydrate heat storage sodium; Slow heat release - Braendeovn med salthydratvarmelager

Energy Technology Data Exchange (ETDEWEB)

Zielke, U.; Bjerrum, M.; Noergaard, T. (Teknologisk Institut, Aarhus (Denmark))

2012-07-01

Of the 700,000 solid fuel stoves in Denmark, 600,000 are installed in permanent residences, and 100,000 are installed in summer cottages. Recent examinations have shown that in the heating season, these stoves contribute with a not negligible share of air pollution in the cities. The reason is often inexpedient firing and an inappropriate performance of the stove. In many cases the thermal output of the stove exceeds the heating demand of a modern residence; and the user typically reduces the stove's combustion air supply with the purpose of lowering the temperature of the accommodation space. The result is a sooting combustion followed by undesired and environmentally damaging emissions. In worst case the user fires throughout the night reducing the air to an absolutely minimum. In these situations the fuel smoulders all night, and the stove emits large amounts of undesirable and unhealthy emissions. By constructing the stove with a heat storage that can accumulate the heat from the stove and emit the heat later (when not firing), the problem with the unhealthy ''night firings'' should be eliminated. The project started with a pre-examination regarding suitable materials for a heat storage and a literature study of the subject. By using an OGC material, in this case sodiumacetat-trihydrat, the weight of the stove, in spite of the heat storage, could be held within reasonable frames, since 130 kg PCM can contain the same heat amount as 1,200 kg stone. The great challenge was to compensate for PCM's poor heat conductivities, to distribute the heat in the whole heat storage, making it melt regularly without generating local boiling. This problem was solved by construction measures. The system with sodiumacetat-trihydrat, which melts by 58 deg. C, came to function satisfactorily. 14 hours after the last firing, the temperature of the heat storage was 30 deg. C. The tests with PCM were followed by an extensive emission measuring program

Thermochemical heat storage for high temperature applications. A review

Energy Technology Data Exchange (ETDEWEB)

Felderhoff, Michael [Max-Planck-Institut fuer Kohlenforschung, Muelheim an der Ruhr (Germany); Urbanczyk, Robert; Peil, Stefan [Institut fuer Energie- und Umwelttechnik e.V. (IUTA), Duisburg (Germany)

2013-07-01

Heat storage for high temperature applications can be performed by several heat storage techniques. Very promising heat storage methods are based on thermochemical gas solid reactions. Most known systems are metal oxide/steam (metal hydroxides), carbon dioxide (metal carbonates), and metal/hydrogen (metal hydrides) systems. These heat storage materials posses high gravimetric and volumetric heat storage densities and because of separation of the reaction products and their storage in different locations heat losses can be avoided. The reported volumetric heat storage densities are 615, 1340 and 1513 [ kWh m{sup -3}] for calcium hydroxide Ca(OH){sub 2}, calcium carbonate CaCO{sub 3} and magnesium iron hydride Mg{sub 2}FeH{sub 6} respectively. Additional demands for gas storage decrease the heat storage density, but metal hydride systems can use available hydrogen storage possibilities for example caverns, pipelines and chemical plants. (orig.)

Microwave-induced solid-state synthesis of TiO2(B) nanobelts with enhanced lithium-storage properties

International Nuclear Information System (INIS)

Qiao Yun; Hu Xianluo; Huang Yunhui

2012-01-01

A fast and economical route based on an efficient microwave-induced solid-state process has been developed to synthesize metastable TiO 2 (B) nanobelts with widths of 30–100 nm and lengths up to a few micrometers on a large scale. This new method reduces the synthesis time for the preparation of TiO 2 (B) nanobelts to less than half an hour, allowing the screening of a wide range of reaction conditions for optimizing and scaling up the production and facilitating the formation of metastable phase TiO 2 (B). The as-formed TiO 2 (B) nanobelts exhibit enhanced lithium-storage performances, compared with the TiO 2 (B) product obtained by the conventional heating. This study provides a new way for large-scale industrial production of high-quality metastable TiO 2 (B) nanostructures. The products were characterized by X-ray diffraction, scanning electron microscopy, transmission electron microscopy, and Raman spectroscopy.

DARA Solid Storage Facility evaluation and recommendations, Y-12 Bear Creek Burial Grounds, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Barton, W.D. III; Hughey, J.C.

1992-08-01

The Disposal Area Remedial Action (DARA) Solid Storage Facility (SSF) is a rectangular concrete vault with two high-density Polyethlene (HDPE) liners and covered with a metal building. The SSF was originally designed and constructed to receive saturated sediments from the excavation of the Oil Retention Ponds and Tributary 7 at the Oak Ridge Y-12 Plant. The sediments placed in the SSF were generally high-water-content soils contaminated with polychlorinated biphenyls (PCBs) and volatile organic carbons. The facility was intended to dewater the sediments by allowing the free water to percolate to a 6-in. sand layer covering the entire floor of the facility. The sand layer then drained into sumps located at the east and west ends of the facility. An application for a Part-B Permit was submitted to the state of Tennessee in February 1992 (MMES 1992a). This report is being submitted to support approval of that permit application and to address certain issues known to the regulators regarding this facility

Physical properties and heat transfer characteristics of materials for krypton-85 storage

International Nuclear Information System (INIS)

Christensen, A.B.

1977-09-01

Krypton-85 decay results in heat generation, and the subsequent temperature increase in the krypton-85 storage media must be evaluated. This report compiles the physical properties of krypton and of potential krypton-85 storage materials which are required to calculate the maximum temperature developed during storage. Temperature calculations were made for krypton-85 stored as a gas or immobilized solid in steel storage cylinders. The effects of krypton-85 loading, cylinder radius, storage media properties, and exterior cooling on storage temperature were shown

Effects of solid-liquid separation and storage on monensin attenuation in dairy waste management systems

Science.gov (United States)

Hafner, Sarah C.; Watanabe, Naoko; Harter, Thomas; Bergamaschi, Brian; Parikh, Sanjai J.

2017-01-01

Environmental release of veterinary pharmaceuticals has been of regulatory concern for more than a decade. Monensin is a feed additive antibiotic that is prevalent throughout the dairy industry and is excreted in dairy waste. This study investigates the potential of dairy waste management practices to alter the amount of monensin available for release into the environment. Analysis of wastewater and groundwater from two dairy farms in California consistently concluded that monensin is most present in lagoon water and groundwater downgradient of lagoons. Since the lagoons represent a direct source of monensin to groundwater, the effect of waste management, by mechanical screen separation and lagoon aeration, on aqueous monensin concentration was investigated through construction of lagoon microcosms. The results indicate that monensin attenuation is not improved by increased solid-liquid separation prior to storage in lagoons, as monensin is rapidly desorbed after dilution with water. Monensin is also shown to be easily degraded in lagoon microcosms receiving aeration, but is relatively stable and available for leaching under typical anaerobic lagoon conditions.

Moessbauer study of Mg-Ni(Fe) alloys processed as materials for solid state hydrogen storage

Energy Technology Data Exchange (ETDEWEB)

Palade, P.; Principi, G., E-mail: giovanni.principi@unipd.it; Sartori, S.; Maddalena, A. [Universita di Padova, Settore Materiali, DIM (Italy); Lo Russo, S. [Universita di Padova, Dipartimento di Fisica (Italy); Schinteie, G.; Kuncser, V.; Filoti, G. [National Institute for Materials Physics, Solid State Magnetism Department (Romania)

2006-02-15

Mg-Ni-Fe magnesium-rich intermetallic compounds were prepared following two distinct routes. A Mg{sub 88}Ni{sub 11}Fe{sub 1} sample (A) was prepared by melt spinning Mg-Ni-Fe pellets and then by high-energy ball milling for 6 h the obtained ribbons. A (MgH{sub 2}){sub 88}Ni{sub 11}Fe{sub 1} sample (B) was obtained by high-energy ball milling for 20 h a mixture of Ni, Fe and MgH{sub 2} powders in the due proportions. A SPEX8000 shaker mill with a 10:1 ball to powder ratio was used for milling in argon atmosphere. The samples were submitted to repeated hydrogen absorption/desorption cycles in a Sievert type gas-solid reaction controller at temperatures in the range 520 - 590 K and a maximum pressure of 2.5 MPa during absorption. The samples were analysed before and after the hydrogen absorption/desorption cycles by X-ray diffraction and Moessbauer spectroscopy. The results concerning the hydrogen storage properties of the studied compounds are discussed in connection with the micro-structural characteristics found by means of the used analytical techniques. The improved kinetics of hydrogen desorption for sample A, in comparison to sample B, has been ascribed to the different behaviour of iron atoms in the two cases, as proved by Moessbauer spectroscopy. In fact, iron results homogeneously distributed in sample A, partly at the Mg{sub 2}Ni grain boundaries, with catalytic effect on the gas-solid reaction; in sample B, instead, iron is dispersed inside the hydride powder as metallic iron or superparamagnetic iron.

Design review report FFTF interim storage cask

International Nuclear Information System (INIS)

Scott, P.L.

1995-01-01

Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

Characterization of solidified radioactive wastes produced at Montalto di Castro BWR plant with reference to the site storage

International Nuclear Information System (INIS)

Donato, A.; Ricci, G.; Pace, A.

1985-01-01

The cement solidification of the Montalto di Castro BWR plant radwastes has been studied both from the point of view of the mixtures of formulation and of the product characterization. Five radwaste types and mixtures of them have been taken into consideration, determining the best chemical formulations starting from the compressive strenght as leading parameter. The solidified products have been characterized from the point of view of the freeze and thawing resistance, the water immersion resistance, the leachability, the dimensional changes and the free standing water. All the tests have been performed taking into account the real site conditions, so the leaching tests and the water immersion tests have been carried out using sea water and table water as leachant

Solid Waste Management: Abstracts From the Literature - 1964.

Science.gov (United States)

Connolly, John A.; Stainback, Sandra E.

The Solid Waste Disposal Act of 1965 (Public Law 89-272, Title II) and its amending legislation, the Resource Recovery Act of 1970 (Public Law 91-512, Title I), authorize collection, storage, and retrieval of information relevant to all aspects of solid-waste management. As part of this effort, the U.S. Environmental Protection Agency's…

The development of safety assessment technology for the radwaste disposal

International Nuclear Information System (INIS)

Han, Kyong Won; Cho, Won Jin; Lee, Han Soo; Lee, Jai Wan; Park, Chung Kyun; Lee, Myun Joo; Cho, Young Hwan; Choi, Heui Joo; Lee, Youn Myoung; Park, Hee Sung

1989-02-01

This report is composed of three parts. In part I, an improved radwaste disposal safety assessment code named SADROCM, was developed by upgrading the existing SADROC. A numerical approach was adopted for the simulation of diffusion into rock pore and advection in the fracture. Also quantification of resaturation time in repository was obtained by introducing theoretical resaturation model and groundwater flow model. In radiation dose model the calculated dose by existing model was compared with that by LIMCAL code. Part II resulted in several findings. Regarding the leaching of radionuclide, two steps were observed. It was identified that in the initial step, radionuclide leaching occurred at the surface of solidified waste, and then leaching proceeded by dissolution and diffusion of radionuclide from inside of the solidified waste.The results of the sorption experiments on Cs, Co, Sr for the rock samples from four regions, showed that Kd value of F-site quartz-porphery was the lowest, and that of B-site Rhyolitic tuff the highest. E-site granite, M-site granite gneiss showed medium sorption capacities. The Kd values of each radionuclide were in the following order: Cs > Co > Sr . For the radionuclide migration through fractured rock, examination of hydraulic dispersion model and channeling model was carried out to simulate the dispersion phenomena through the fractured rock. In part III, optimum model was established which allows mathematical prediction of the container corrosion rate and leach rate.Based on this model, the equations were obtained to predict corrosion rate and radionuclide leach rate. A good agreement of these equations and existing experimental data was considered to be an indication that it can be used effectively for the estimation of long-term leaching. (Author)

Estimation of restaurant solid waste generation rates

International Nuclear Information System (INIS)

Heck, H.H.; Major, I.

2002-01-01

Most solid waste utilities try to create a billing schedule that is proportional to solid waste generation rates. This research was trying to determine if the current billing rate structure was appropriate or if a different rate structure should be implemented. A multiple regression model with forward stepwise addition was developed which accurately predicts weekly solid waste generation rates for restaurants. The model was based on a study of daily solid waste generation at twenty-one different businesses. The weight and volume of solid waste generated was measure daily for two weeks during the winter and two weeks during the summer. Researchers followed the collection truck and measured the volume and weight of the container contents. Data was collected on the following independent variables describing each establishment; weight of waste per collection, volume per collection, container utilization factor, building area, contract haulers bill, yearly property tax, yearly solid waste tax, average number of collections per week, type of restaurant, modal number of collections per week, storage container size, waste density, number of employees, number of hours open per week, and weekly collection capacity (collections per week times storage container size). Independent variables were added to the regression equation based on their partial correlation coefficient and confidence level. The regression equations developed had correlation coefficients of 0.87 to 1.00, which was much better than the correlation coefficient (0.84) of an existing model DeGeare and Ongerth (1971) and a correlation coefficient of 0.54 based on the current solid waste disposal tax. (author)

GAT 4 production and storage of hydrogen. Report July 2004

International Nuclear Information System (INIS)

2004-01-01

This paper concerns two aspects of the hydrogen: the production and the storage. For both parts the challenges and a state of the art are presented. It discusses also the hydrogen production by renewable energies, by solar energy, the hydrogen of hydrocarbons reforming purification, active phases development, thermal transfer simulation. Concerning the hydrogen storage the hydrogen adsorption by large surface solid, the storage by metallic hydrides, the alanates and light hydrides, the adsorption on carbon nano-tubes, the storage in nano-structures, the thermal and mechanical simulation of the hydrogen are presented. (A.L.B.)

Summary of environmental characterization activities at the Oak Ridge National Laboratory Solid Waste Storage Area Six, FY 1986 through 1987

International Nuclear Information System (INIS)

Davis, E.C.; Solomon, D.K.; Dreier, R.B.; Lee, S.Y.; Kelmers, A.D.; Lietzke, D.A.; Craig, P.M.

1987-01-01

The Oak Ridge National Laboratory (ORNL) Remedial Action Program (RAP), has supported characterization activities in Solid Waste Storage Area (SWSA 6) to acquire information necessary for identification and planning of remedial actions that may be warranted, and to facilitate eventual closure of the site. In FY 1986 investigations began in the areas of site hydrology, geochemistry, soils, geology, and geohydrologic model application. This report summarizes work carried out in each of these areas during FY's 1986 and 1987 and serves as a status report pulling together the large volume of data that has resulted. Characterization efforts are by no means completed; however, a sufficient data base has been generated to begin data interpretation and analysis of site contaminants

Energy density and storage capacity cost comparison of conceptual solid and liquid sorption seasonal heat storage systems for low-temperature space heating

NARCIS (Netherlands)

Scapino, L.; Zondag, H.A.; Van Bael, J.; Diriken, J.; Rindt, C.C.M.

Sorption heat storage can potentially store thermal energy for long time periods with a higher energy density compared to conventional storage technologies. A performance comparison in terms of energy density and storage capacity costs of different sorption system concepts used for seasonal heat

Electrolyte for batteries with regenerative solid electrolyte interface

Science.gov (United States)

Xiao, Jie; Lu, Dongping; Shao, Yuyan; Bennett, Wendy D.; Graff, Gordon L.; Liu, Jun; Zhang, Ji-Guang

2017-08-01

An energy storage device comprising: an anode; and a solute-containing electrolyte composition wherein the solute concentration in the electrolyte composition is sufficiently high to form a regenerative solid electrolyte interface layer on a surface of the anode only during charging of the energy storage device, wherein the regenerative layer comprises at least one solute or solvated solute from the electrolyte composition.

Supply, storage and handling of elemental sulfur derived from sour gas

International Nuclear Information System (INIS)

Clark, P.D.; Davis, P.M.; Dowling, N.I.; Calgary Univ., AB

2003-01-01

This presentation reviews the supply picture for solid elemental sulfur. It also assesses methods for its storage as well as the disposal of the precursor hydrogen sulfide (H 2 S) by acid gas injection. Both above and below ground block storage is considered environmentally acceptable for sulfur storage as long as measures are taken to minimize the physical and biological breakdown of the sulfur. The preferred option is to store solid elemental sulfur underground, particularly if it is to remain in storage for a prolonged period. Future changes in supply of sulfur will likely be controlled by incremental production of sour gas and utilization of oil sands bitumen. It is expected that future sulfur production from conventional crude oil will remain static or will slowly decrease. The degree to which acid gas injection is applied to large sour gas developments in the Middle East and the Caspian regions will have a significant impact on world sulfur supply. 9 refs., 1 tab., 5 figs

1995 Baseline solid waste management system description

International Nuclear Information System (INIS)

Anderson, G.S.; Konynenbelt, H.S.

1995-09-01

This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

Solid and liquid radioactive wastes

International Nuclear Information System (INIS)

Cluchet, J.; Desroches, J.

1977-01-01

The problems raised by the solid and liquid radioactive wastes from the CEA nuclear centres are briefly exposed. The processing methods developed at the Saclay centre are described together with the methods for the wastes from nuclear power plants and reprocessing plants. The different storage techniques used at the La Hague centre are presented. The production of radioactive wastes by laboratories, hospitals and private industry is studied for the sealed sources and the various radioactive substances used in these plants. The cost of the radioactive wastes is analysed: processing, transport, long term storage [fr

Towards Sustainable Ambon Bay: Evaluation of Solid Waste Management in Ambon City

Science.gov (United States)

Maryati, S.; Miharja, M.; Iscahyono, A. F.; Arsallia, S.; Humaira, AN S.

2017-07-01

Ambon Bay is a strategic area in the context of regional economic development, however it also faced environmental problems due to economic development and the growth of population. One of the environmental problems in the Ambon Bay is the growing solid waste which in turn lowers the quality of the water. The purpose of this study is to evaluate solid waste management in the Ambon City and propose recommendation in order to reduce solid waste in the Ambon Bay. The analytical method used is descriptive analysis by comparing a number of criteria based on the concept of solid waste management in coastal region with the current conditions of solid waste management in Ambon City. Criteria for waste management are divided into generation, storage, collection, transport, transfer and disposal. From the results of analysis, it can be concluded that the components of solid waste management at transport, transfer, and disposal level are generally still adequate, but solid waste management at source, storage and collection level have to be improved.

Public health response to striking solid waste management.

Science.gov (United States)

Murti, Michelle; Ayre, Reg; Shapiro, Howard; de Burger, Ron

2011-10-01

In 2009, the City of Toronto, Ontario, Canada, experienced a six-week labor disruption involving 24,000 city workers that included solid waste and public health employees. In an attempt to control illegal dumping and to manage garbage storage across the city during this period, 24 temporary garbage storage sites were established by the city (mostly in local parks) for residents to dispose of their household waste. No other municipality in North America has attempted to operate this many temporary sites for this long a period. Management and nonunion staff from Healthy Environments in Toronto Public Health performed daily inspections, responded to community questions, issued public health orders, and worked closely with Solid Waste Management and the Ministry of the Environment to actively manage the public health concerns associated with these sites. This intensive oversight mitigated public health risks to the community and facilitated an effective, safe solution to the temporary garbage storage problem.

Nano-porous inorganic-organic hybrid solids: some new materials for hydrogen storage?

International Nuclear Information System (INIS)

Serre, Ch.; Loiseau, Th.; Devic, T.; Ferey, G.; Latroche, M.; Llewellyn, Ph.; Chang, J.S.

2007-01-01

Recently have been studied chromium and aluminium carboxylates MIL-53(Cr, Al), formed from an assembly of octahedrons chains and for hybrid solids formed with octahedrons trimers (MIL-100 and MIL-101). The compounds MIL-53(Cr, Al) are microporous (φ ∼ 8 Angstroms, while the solids MIL-100 and MIL-101 have very large porous volumes (V ∼ 380-700000 (Angstroms) 3 ), meso-pores (φ ∼ 25-34 Angstroms) and a zeolitic architecture. The resulting specific surface areas are important (between 1000 m 2 .g -1 for the MIL-53 solids, until 4000 m 2 .g -1 for the MIL-101 compound. Here is presented their hydrogen adsorption properties, at 77 K and 298 K. The hydrogen adsorption kinetics has been tested on the MIL-53(Cr) solid at 77 K. Hydrogen adsorption micro-calorimetry experiments have been carried out on these solids between 0 and 1 bar in order to obtain data on the strongest interactions between hydrogen and the porous basic structure. (O.M.)

IGBT: a solid state switch

International Nuclear Information System (INIS)

Chatroux, D.; Maury, J.; Hennevin, B.

1993-01-01

A Copper Vapour Laser Power Supply has been designed using a solid state switch consisting in eighteen Isolated Gate Bipolar Transistors (IGBT), -1200 volts, 400 Amps, each-in parallel. This paper presents the Isolated Gate Bipolar Transistor (IGBTs) replaced in the Power Electronic components evolution, and describes the IGBT conduction mechanism, presents the parallel association of IGBTs, and studies the application of these components to a Copper Vapour Laser Power Supply. The storage capacitor voltage is 820 volts, the peak current of the solid state switch is 17.000 Amps. The switch is connected on the primary of a step-up transformer, followed by a magnetic modulator. The reset of the magnetic modulator is provided by part of the laser reflected energy with a patented circuit. The charging circuit is a resonant circuit with a charge controlled by an IGBT switch. When the switch is open, the inductance energy is free-wheeled by an additional winding and does not extend the charging phase of the storage capacitor. The design allows the storage capacitor voltage to be very well regulated. This circuit is also patented. The electric pulse in the laser has 30.000 Volt peak voltage, 2000 Amp peak current, and is 200 nanoseconds long, for a 200 Watt optical power Copper Vapour Laser

[Microbiological Aspects of Radioactive Waste Storage].

Science.gov (United States)

Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

2015-01-01

The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

Metal ammine complexes for hydrogen storage

DEFF Research Database (Denmark)

Christensen, Claus H.; Sørensen, Rasmus Zink; Johannessen, Tue

2005-01-01

The hopes of using hydrogen as an energy carrier are severely dampened by the fact that there is still no safe, high-density method available for storing hydrogen. We investigate the possibility of using metal ammine complexes as a solid form of hydrogen storage. Using Mg(NH3)(6)Cl-2 as the example......, we show that it can store 9.1% hydrogen by weight in the form of ammonia. The storage is completely reversible, and by combining it with an ammonia decomposition catalyst, hydrogen can be delivered at temperatures below 620 K....

High-level radioactive waste glass and storage canister design

International Nuclear Information System (INIS)

Slate, S.C.; Ross, W.A.

1979-01-01

Management of high-level radioactive wastes is a primary concern in nuclear operations today. The main objective in managing these wastes is to convert them into a solid, durable form which is then isolated from man. A description is given of the design and evaluation of this waste form. The waste form has two main components: the solidified waste and the storage canister. The solid waste form discussed in this study is glass. Waste glasses have been designed to be inert to water attack, physically rugged, low in volatility, and stable over time. Two glass-making processes are under development at PNL. The storage canister is being designed to provide high-integrity containment for solidified wastes from processing to terminal storage. An outline is given of the steps in canister design: material selection, stress and thermal analyses, quality verification, and postfill processing. Examples are given of results obtained from actual nonradioactive demonstration tests. 14 refs

Storage potential of ‘SCS426 Venice’ apples under different storage technologies

Directory of Open Access Journals (Sweden)

Mariuccia Schlichting de Martin

2018-04-01

Full Text Available Abstract This study aimed to evaluate the storage potential of SCS426 Venice apples under different storage technologies. Fruits were harvested in an experimental orchard located in Fraiburgo, SC and stored for up to eight and ten months in 2013 and 2014, respectively. Apples were treated or not with methylcyclopropene (1-MCP and stored under air atmosphere (AA, 0.5±0.5 °C/RH 85±5% or controlled atmosphere (CA; 1.5 kPa of O2 and 1.5 kPa of CO2 at 0.7±0.5 °C/RH of 93±3%. Fruits were evaluated every two months of storage, after one and seven days of shelf life (23 ± 0.3 °C/RH 93±3%. The storage period of ‘SCS426 Venice’ apples under AA without 1-MCP application should not extend beyond six months. Under this storage condition, fruits had higher incidence of decay, ethylene production and respiratory rates, higher skin degreening, lower flesh firmness, titratable acidity and soluble solids content than fruits stored under CA or AA with 1-MCP. ‘SCS426 Venice’ apples develop flesh browning and superficial scald after long-term storage. ‘SCS426 Venice’ apples under AA treated with 1-MCP or under CA (regardless of 1-MCP application can be stored for more than eight months, keeping flesh firmness above 14 lb and low incidence of physiological disorders even after ten months of storage.