WorldWideScience

Sample records for spent sealed sources

  1. Management of spent sealed sources in Indonesia

    International Nuclear Information System (INIS)

    Wisnubroto, D.S.

    2002-01-01

    This paper describes the effort of the Center for Development of Radioactive Waste Management (CDRWM) to develop and implement activities in maintaining and improving the safety of spent sealed radiation sources and the security of radioactive materials over their life cycle. There is a wide variety of uses of radiation sources and radioactive materials in Indonesia, while the CDRWM plan to cover all spent radiation sources. Primary consideration is given to sealed radiation sources with relatively high levels of radioactivity which might necessitate interventional measures should control over them be lost. The policy of the Government of Indonesia for spent radiation sources is, whenever possible, spent sealed sources should be returned to the supplier. CDRWM has a general principle that sealed sources should not be removed from their holders, or the holders physically modified (except for Ra-226 needles, smoke detector and lighting preventer). (author)

  2. Management of spent sealed radioactive sources

    International Nuclear Information System (INIS)

    Vicente, Roberto; Sordei, Gian-Maria; Hiromoto, Goro

    2002-01-01

    The number of sealed radiation sources used in industrial, medical, and research applications in Brazil amounts to hundreds of thousands. Spent or disused sources are being collected and stored as radioactive waste in nuclear research centers, awaiting for a decision on their final disposal. However, a safe and economically feasible disposal technology is unavailable. The aim of this paper is to report the development of the concept of a repository and a treatment process that will allow the final disposal of all the spent sealed sources in a safe, dedicated, and exclusive repository. The concept of the disposal system is a deep borehole in stable geologic media, meeting the radiological performance standards and safety requirements set by international organizations. (author)

  3. Sure confinement of spent sealed sources

    International Nuclear Information System (INIS)

    Lizcano, D.

    2013-10-01

    The industrial and technological development of the last decades produced and increment in the radiations application in different human activities. One of the main effects has been the production of radioactive wastes of all the levels. In Mexico, several stages of the waste management of low and intermediate level have not been completely resolved, as the case of the treatment and the final storage. In this work the confinement of spent sealed sources is described, maintaining as main objective the security of these sources and the protection to the workers and the people. (author)

  4. Handling, conditioning and disposal of spent sealed sources

    International Nuclear Information System (INIS)

    1990-02-01

    The series entitled ''Technical Manual for the Management of Low and Intermediate Level Wastes Generated at Small Nuclear Research Centres and by Radioisotope Users in Medicine, Research and Industry'' will serve as reference material to experts on technical assistance missions and provide ''direct know-how'' for technical staff in developing countries. This document is the first in the series. It provides the technical guidance and know-how necessary to permit developing Member States to safely handle, condition and store spent sealed radiation sources. It covers: characterization of sealed sources, legislation and regulations, management of spent sealed sources, transportation and disposal of spent sealed sources. 5 refs, 10 figs, 6 tabs

  5. Rendering harmless and deposition of spent sealed radiation sources

    International Nuclear Information System (INIS)

    Cholerzynski, A.

    1999-01-01

    The sealed radiation sources are commonly used in medicine, agriculture, industry and scientific research. There is millions of such sources being used all over the world. The purpose of this article is to present a modes of management and disposal of spent sealed radioactive sources in different countries as well as methods being recommended in Poland

  6. Management of spent sealed radioactive sources in the European Union

    International Nuclear Information System (INIS)

    Cecille, L.; Taylor, D.

    2000-01-01

    For several years, the European Commission (EC) has been active in the field of spent sealed radioactive sources (SSRS) to improve management schemes and to prepare Euratom Directives that will impact on national legislation and regulatory schemes in European Member States (MS). The main safety issues related to the management of SSRS are described and recommendations made are presented. Additional projects are outlined. (author)

  7. Conditioning and storage of spent sealed radium sources

    International Nuclear Information System (INIS)

    Cholerzynski, A.; Tomczak, W.

    2001-01-01

    In Poland sealed radioactive sources (SRS) are extensively used in medicine and in industry. There are mainly Co-60, Cs-137, lr-192 and also historical sources contain in Ra-226. The Radioactive Waste Management Department (ZDUOP) of the Institute of Atomic Energy at Swierk is the only organization licensed for the management, storage and disposal of radioactive waste in Poland. ZDUOP deals with all radioactive waste in the country. Storage and disposal of SRS is one of the most important part of its activity. Every year ZDUOP collects about 1000 spent SRS which total activity is near 600 GBq. Spent Ra-226 sources are a special case and therefore are required suitable procedures. Due to their production according to earlier standards and their undesirable characteristics, leakage of these sources is highly possible and practically observed. For this reason conditioning of radium sources needs strict requirements and quality assurance procedure to guarantee their safe storage for an extended period of time (e.g. 40-70 years). The National Radioactive Waste Repository is superficial type repository and considered as temporary storage site for long-lived waste. A storage facility for spent SRS has been properly prepared and licensed by the regulatory body. This facility consist of several concrete chambers which floor is lined stainless steel. The existing regulatory framework for sealed radioactive sources entered into force with issue of the Atomic Law in 1986

  8. Spent sealed radium sources conditioning in Latin America

    International Nuclear Information System (INIS)

    Mourao, R.P.

    1999-01-01

    The management of spent sealed sources is considered by the International Atomic Energy Agency (IAEA) one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency's initiatives to tackle this problem is the Spent Radium Sources Conditioning Project, a worldwide project relying on the regional co-operation between countries. A team from the Brazilian nuclear research institute Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) was chosen as the expert team to carry out the operations in Latin America; since December 1996 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala, Ecuador and Paraguay. A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,897 mg of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes and contaminated objects were stored in proper conditions and are now under control of the nuclear authorities of the visited countries

  9. Spent sealed radium sources conditioning in Latin America

    International Nuclear Information System (INIS)

    Mourao, Rogerio Pimenta

    1999-01-01

    The management of spent sealed sources is considered by the IAEA one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency's initiatives to tackle this problem is the 'Spent Radium Sources Conditioning Project', a worldwide project relying on the regional cooperation between countries. A CDTN team was chooses as the expert team to carry out the operations in Latin America; since Dec 96 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala and Ecuador. A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,629 mg (approx. 98 GBq) of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes (generated during the operations) and contaminated objects were stored in proper conditions and are now under control, of the nuclear authorities of the visited countries. (author)

  10. Experience and Lessons Learned from Conditioning of Spent Sealed Sources in Singapore - 13107

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Dae-Seok; Kang, Il-Sik; Jang, Kyung-Duk; Jang, Won-Hyuk [Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong, Daejeon (Korea, Republic of); Hoo, Wee-Teck [National Environment Agency, 40 Scotts Road 228231 (Singapore)

    2013-07-01

    In 2010, IAEA requested KAERI (Korea Atomic Energy Research Institute) to support Singapore for conditioning spent sealed sources. Those that had been used for a lightning conductor, check source, or smoke detector, various sealed sources had been collected and stored by the NEA (National Environment Agency) in Singapore. Based on experiences for the conditioning of Ra-226 sources in some Asian countries since 2000, KAERI sent an expert team to Singapore for the safe management of spent sealed sources in 2011. As a result of the conditioning, about 575.21 mCi of Am-241, Ra-226, Co-60, and Sr-90 were safely conditioned in 3 concrete lining drums with the cooperation of the KAERI expert team, the IAEA supervisor, the NEA staff and local laborers in Singapore. Some lessons were learned during the operation: (1) preparations by a local authority are very helpful for an efficient operation, (2) a preliminary inspection by an expert team is helpful for the operation, (3) brief reports before and after daily operation are useful for communication, and (4) a training opportunity is required for the sustainability of the expert team. (authors)

  11. Sure confinement of spent sealed sources; Confinamiento seguro de fuentes selladas gastadas

    Energy Technology Data Exchange (ETDEWEB)

    Lizcano, D., E-mail: david.lizcano@inin.gob.mx [ININ, Departamento de Desechos Radiactivos, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    The industrial and technological development of the last decades produced and increment in the radiations application in different human activities. One of the main effects has been the production of radioactive wastes of all the levels. In Mexico, several stages of the waste management of low and intermediate level have not been completely resolved, as the case of the treatment and the final storage. In this work the confinement of spent sealed sources is described, maintaining as main objective the security of these sources and the protection to the workers and the people. (author)

  12. Spent sealed radioactive sources conditioning technology for the disposal at the national repository Baita-Bihor

    International Nuclear Information System (INIS)

    Bujoreanu, D.; Popescu, I.V.

    2006-01-01

    A spent sealed radioactive source(SRS) is a high integrity capsule which contains a small amount of concentrated radionuclide with an activity which ranges from a few MBq up to levels of hundreds TBq. Presently, there are now many spent and unusable SRS in Romania, which have been used a long time in various industrial applications (smoke detectors, weld testing etc.). Considering the activity of the Radioactive Waste Treatment Plant (STDR) at the Institute for Nuclear Research Pitesti regarding radioactive source collecting from various economic agents, several radioactive sources are held in the intermediate storage deposit facility on the institute platform awaiting conditioning for the final disposal. This paper presents the conditioning technology for this sources, which has as ultimate purpose to completion of a product which matches the waste acceptance requirements imposed by the National Authority Control of Nuclear Activities, CNCAN, for the disposal site DNDR Baita - Bihor. The technology used for obtaining the final product allows two options for the immobilization of the sources in the 218 L steel drum and these are: Sources placed in the original packages and which can not be dismantled will be isolated by encapsulation in 10 litters metal capsules and then conditioned in 218 l steel drum, with a concrete biological shielding; Sources removed from the initial package are isolated in stainless steel capsules, which are to be conditioned in the same 218 L steel drum. The final product obtained as a result of the concrete conditioning operations of the spent SRS in 218 L steel drum is the steel drum - concrete - low radioactive waste assembly which presents itself as a concrete block which includes one or more capsules containing SRS. (author)

  13. Management of spent and disused sealed radiation sources in Russian Federation

    International Nuclear Information System (INIS)

    Sobolev, I.A.; Ojovan, M.I.; Karlina, O.K.; Arustamov, A.E.

    2001-01-01

    Full text: The system of management of spent and disused sealed radiation sources (SDSRS) in Russian Federation is based on centralised approach. This system involves 16 regional facilities of the system 'Radon' which provide safe management of SDSRS. The scientific and methodical guidance on activities of regional facilities 'Radon' carries out the Scientific and Industrial Association 'Radon', Moscow. Recently the Moscow SIA 'Radon' examined activities at regional facilities 'Radon' accordingly with the program approved by the State Supervision Authority of Russia (GAN). It was revealed that the main type of radioactive waste at these facilities comprises SDSRS. This is the case both on summarised quantity of accumulated radioactivity (more than 99%) and on general quantity of the containers with waste (more than 80%). The average radionuclide composition of the SDSRS accumulated at regional facilities 'Radon' is as follows: Cs-137 (40%), Co-60 (25%), Sr-90 (22%), Ir-192 (8%) and Tm-170 (4%). The content of other radionuclides in SDSRS is not more than 1%. At regional facilities 'Radon' SDSRS mainly are disposed of in bore hole type repositories. Nevertheless SDSRS are also stored in containers being placed into repositories for solid radioactive waste. SDSRS which contain long lived radionuclides are stored until the decision on their final disposal into a deep geological formation. So far as free (not conditioned) storage of SDSRS can not provide safe conditions for environment for a long time, it is necessary to immobilise sources additionally into a suitable matrix material. Supplemental sources inclusion in a lead (or lead based alloy) matrix using Moscow SIA 'Radon' mobile plant was carried out at five regional 'Radon' facilities as follows: Zagorsk branch of Moscow SIA 'Radon', Volgograd, Ekaterinburg, Nizhny Novgorod, and Ufa. More than 1 million Ci of SDSRS are stored at present time in conditioned form in bore hole repositories. In 1998-1999 the Moscow

  14. Management of Spent Sealed Radioactive Sources in Bulgaria, Latvia, Lithuania, Romania and Slovakia

    International Nuclear Information System (INIS)

    Angus, M.; Cowley, M.; Moreton, T.; Wells, D.

    2003-01-01

    This study has been performed to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in five of the Central and Eastern European (C and EE) countries that are being considered for admission to the EU, namely, Bulgaria, Latvia, Lithuania, Romania and Slovakia. Two previous studies have considered the situation in the current EU member states(1) and in the Czech Republic, Estonia, Hungary, Poland and Slovenia(2). The general aim of this study has been to acquire a thorough understanding of the management of SSRS in the five countries, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous. This report is structured in the following manner; following the Introduction (Section 1), there is a description of the current and proposed regulatory requirements in the EU, together with a summarised comparison of the regulatory systems in the five countries with EU standards (Section 2). Sections 3 to 7 are dedicated to each of the five countries. Each of these sections is similarly sub-divided to enable country-by-country and topic-by-topic comparison. In each of Sections 3 to 7 there is an overview, description of the sealed source inventory, regulations, current management practices, retrieval of unregistered (sometimes known as lost or orphan sources) SSRS, conclusions and a description of possible future technical assistance projects. In addition, there is a description in each of Sections 3 to 7 of the management of 226 Ra sources, which is receiving special attention in many countries (Table I provides a summary and comparison of the management of 226 Ra in the five countries).both country-specific and generic recommendations. A common concern in the five countries and many other countries, including the EU member states, is the problem of accidental inclusion of SSRS in consignments of scrap metal. The detection of

  15. Sealed can of spent fuel

    International Nuclear Information System (INIS)

    Suzuki, Yasuyuki.

    1976-01-01

    Object: To provide a seal plug cover with a gripping portion fitted to a canning machine and a gripping portion fitted to a gripper of the same configuration as a fuel body for handling the fuel body so as to facilitate the handling work. Structure: A sealed can comprises a vessel and a seal plug cover, said cover being substantially in the form of a bottomed cylinder, which is slipped on the vessel and air-tightly secured by a fastening bolt between it and a flange. The spent fuel body is received into the vessel together with coolant during the step of canning operation. Said seal plug cover has two gripping portions, one for opening and closing the plug cover of the canning machine as an exclusive use member, the other being in the form of a hook-shaped peripheral groove, whereby the gripping portions may be effectively used using the same gripper when the spent fuel body is transported while being received in the sealed can or when the fuel body is removed from the sealed can. (Kawakami, Y.)

  16. Assessment of the Proposed Design of a New Spent Sealed Radioactive Sources Storage Facility at Novi Han

    International Nuclear Information System (INIS)

    Alardin, J.M.; Lacroix, J.P.; Glibert, R.; Marneffe, L. de

    2001-09-01

    The NOVI HAN radioactive waste repository (NHRWR) in Bulgaria, built according to a Soviet design, was commissioned in 1964. The State Committee on the Use of Atomic Energy for Peaceful Purposes (CUAEPP) temporarily stopped operations at the repository from October 1994 until measures for improvement of the facility are undertaken. Since 1994, the Spent Sealed Radioactive Sources (SSRS) have been temporarily stored at the facilities at IRT-2000 research reactor of the Bulgarian Academy of Sciences (BAS) in Sofia. In view of the importance of the radiological risks associated with the present management of the SSRS in Bulgaria, the present study contract has been launched to critically review the proposal to provide a new interim storage facility for SSRS at NHRWR. A comprehensive critical review was performed of the feasibility study for the construction of a new SSRS facility at Novi Han, carried out by the local consultant engineering company (EQE), and detailed recommendations were made concerning the proposed new development at the site. The authors think that new concepts and procedures in the management of all categories of SSRS including smoke detectors have to be introduced, taking into account the regulatory framework and the inventories of existing and anticipated SSRS. This should be the basis for the technical specification of the new facilities for conditioning and storage of spent sealed radioactive sources (not only SHARS). (author)

  17. Sealed radioactive source management

    International Nuclear Information System (INIS)

    2005-01-01

    Sealed radioactive sources have been used in a wide range of application in medicine, agriculture, geology, industry and other fields. Since its utilization many sources have become out of use and became waste but no proper management. This has lead to many accidents causing deaths and serious radiation injuries worldwide. Spent sources application is expanding but their management has seen little improvements. Sealed radioactive sources have become a security risk calling for prompt action. Source management helps to maintain sources in a good physical status and provide means of source tracking and control. It also provides a well documented process of the sources making any future management options safe, secure and cost effective. Last but not least good source management substantially reduces the risk of accidents and eliminates the risk of malicious use. The International Atomic Energy Agency assists Member States to build the infrastructure to properly manage sealed radioactive sources. The assistance includes training of national experts to handle, condition and properly store the sources. For Member States that do not have proper facilities, we provide the technical assistance to design a proper facility to properly manage the radioactive sources and provide for their proper storage. For Member States that need to condition their sources properly but don't have the required infrastructure we provide direct assistance to physically help them with source recovery and provide an international expert team to properly condition their sources and render them safe and secure. We offer software (Radioactive Waste Management Registry) to properly keep a complete record on the sources and provide for efficient tracking. This also helps with proper planning and decision making for long term management

  18. Management of Spent Sealed Radioactive Sources in Central and Eastern Europe (Czech Rep., Estonia, Hungary, Poland and Slovenia)

    International Nuclear Information System (INIS)

    Angus, M.J.; Moreton, A.D.; Wells, D.A.

    2001-04-01

    This study has been performed to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in five central and Eastern European (C and EE) countries currently being considered for admission to the EU: the Czech Republic, Estonia, Hungary, Poland and Slovenia. The general aim of this study has been to acquire a thorough understanding of the management of SSRS in these five countries, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous. This report is structured in the following manner; following the Introduction (Section 1), there is description of current and proposed regulatory requirements in the EU, together with a summarised comparison of the regulatory systems in C and EE countries with EU standards in Section 2. Sections 3 to 7 are dedicated to the situation in each of the five countries. Each of these sections is similarly sub-divided to enable country-by-country and topic-by-topic comparison. In each of Sections 3 to 7 there is an overview, description of the sealed source inventory, regulations, current management practices, retrieval of unregistered SSRS, conclusions and a description of possible future technical assistance projects. Section 8 brings together a summary of the situation in each country, with conclusions and both country-specific and generic recommendations. A common concern in the five countries and also in existing EU member states is the problem of accidental inclusion of SSRS in consignments of scrap-metal. The detection of radioactive material at entrances to scrap metal facilities and at national borders has therefore received considerable attention in recent years. Practical issues regarding the detection of SSRS in scrap metal are described in Appendix A. None of the five countries considered in this report have any plans to develop regional disposal facilities and no specific common

  19. Sealed radioactive sources toolkit

    International Nuclear Information System (INIS)

    Mac Kenzie, C.

    2005-09-01

    The IAEA has developed a Sealed Radioactive Sources Toolkit to provide information to key groups about the safety and security of sealed radioactive sources. The key groups addressed are officials in government agencies, medical users, industrial users and the scrap metal industry. The general public may also benefit from an understanding of the fundamentals of radiation safety

  20. Spent fuel shipping cask sealing concepts

    International Nuclear Information System (INIS)

    Sonnier, C.S.

    1989-05-01

    In late 1985, the International Atomic Energy Agency (IAEA) requested the US Program for Technical Assistance to IAEA Safeguards (POTAS) to provide a study which examined sealing concepts for application to spent fuel shipping casks. This request was approved, and assigned to Sandia National Laboratories (Sandia). In the course of this study, discussions were held with personnel in the International Safeguards Community who were familiar with the shipping casks used in their States. A number of shipping casks were examined, and discussions were held with two shipping cask manufacturers in the US. As a result of these efforts, it was concluded that the shipping casks provided an extremely good containment, and that many of the existing casks can be effectively sealed by applying the seal to the cask closure bolts/nuts

  1. Reference design for a centralized spent sealed sources facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1995-07-01

    To assist Member States in establishing facilities in which the most frequently occurring spent sealed sources can be safely conditioned, the IAEA has financed the development of a generic design for a Spent Sealed Sources Facility (SSS Facility). The purpose of this TECDOC is to provide enough general information about the functions and capabilities of the SSS Facility to enable the reader to understand what the facility can do to contribute towards the management of spent sealed sources without providing all the technical and/or design information available. Sufficient information is provided to enable the reader to judge how and to what extent such a facility can contribute to national radioactive waste management infrastructure. 2 refs, 5 figs, 1 tab

  2. Reference design for a centralized spent sealed sources facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    To assist Member States in establishing facilities in which the most frequently occurring spent sealed sources can be safely conditioned, the IAEA has financed the development of a generic design for a Spent Sealed Sources Facility (SSS Facility). The purpose of this TECDOC is to provide enough general information about the functions and capabilities of the SSS Facility to enable the reader to understand what the facility can do to contribute towards the management of spent sealed sources without providing all the technical and/or design information available. Sufficient information is provided to enable the reader to judge how and to what extent such a facility can contribute to national radioactive waste management infrastructure. 2 refs, 5 figs, 1 tab.

  3. Sealed sources in Peru: advances and outlook

    International Nuclear Information System (INIS)

    Rodriguez, C.G.

    1998-01-01

    Cementation of spent sealed sources is performed by the Radioactive Waste Management Group of the Peruvian Institute of Nuclear Energy (IPEN). The sealed sources are collected in different areas of the country and brought to the RACSO nuclear centre, a national storage and conditioning facility for spent sources from industry and medical institutions. In addition to its amenities dedicated to research and the production of radioisotopes, the RACSO nuclear centre features a complex of some 1.5 ha for radioactive waste management that includes an infiltration bed and chemical treatment plant for liquid waste, compacting equipment and trenches for solid radioactive waste, a tank for the elimination of biological residues and a temporary storage emplacement for radioactive waste immobilized in cement cylinder casings. The steps described are the unpacking, identification of spent sealed sources, placement of the source in shielding, cementation, solidification, tagging and storage, as well as the actions taken to comply with the appropriate measures of radiological protection. (author)

  4. Production of sealed sources

    International Nuclear Information System (INIS)

    Bandi, L.N.

    2016-01-01

    Radioisotope production has been an ongoing activity in India since the sixties. Radioisotopes find wide-ranging applications in various fields, including industry, research, agriculture and medicine. Board of Radiation and Isotope Technology, an industrial unit of Department of Atomic Energy is involved in fabrication and supply of wide variety of sealed sources. The main radioisotopes fabricated and supplied by BRIT are Cobalt-60, Iridium-192. These isotopes are employed in industrial and laboratory irradiators, teletherapy machines, radiography exposure devices, nucleonic gauges. The source fabrication facilities of BRIT are located at Rajasthan Atomic Power Project Cobalt-60 Facility (RAPPCOF), Kota, Radiological Laboratories Group (RLG) and High Intensity Radiation Utilization Project (HIRUP) at Trombay

  5. Handling, conditioning and storage of spent sealed radioactive sources. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    2000-05-01

    This report is intended to provide reference material, guidance and know-how on handling, conditioning and storage of spent sealed radioactive sources (SRS) to both users of SRS and operators of waste management facilities. The scope of this report covers all types of SRS except those exempted from regulatory control. The report contains in some detail technical procedures for the conditioning of spent SRS, describes the means required to assure the quality of the resulting package and discusses the measures to prepare waste packages with a certain flexibility to accommodate possible future disposal requirements

  6. Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

    OpenAIRE

    Marpaung, T

    2012-01-01

    In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS), due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed ...

  7. Conditioning of spent radiation sources in developing countries

    International Nuclear Information System (INIS)

    1990-01-01

    This video presents the safe handling and conditioning of radioactive spent sealed sources when technological resources are limited and specialized equipment is not available. The process is divided into three phases which are demonstrated in detail: 1) Planning, including training; 2) Conditioning, which is the actual incorporation of the spent sources; and 3) Follow-up, which includes radiological control, documentation and safe storage

  8. Management of Spent Radiation Source from Radiotherapy

    International Nuclear Information System (INIS)

    Aisyah

    2008-01-01

    Nowadays the use of radioactive source for both radiodiagnostic and radiotherapy in Indonesia hospital increases rapidly. Sealed source used in radiotherapy among others for brachytherapy, teletherapy, bone densitometry, whole blood irradiation and gamma knife (radiosurgery). In line with this, the waste of spent radiation sources will be generated in hospitals. Of course these spent radiation sources must be treated correctly in order to maintain the safety of both the public and the environment. According to the Act No. 10/1997, BATAN, in care of the Radioactive Waste Management Center is the national appointed agency for the management of radioactive waste. The option for waste management by hospitals needs to be expound, either by re-exporting to the supplier of origin, re-exporting to other supplier, re-use by other licensee or sending to the Radioactive Waste Management Center. Usually the waste sent by the hospitals to the center comprises of sealed radiation source of 60 Co, 137 Cs or 226 Ra. The management of spent radiation source in the center is carried out in several steps i.e. conditioning, temporary storage, and long-term storage (final disposal). The conditioning of non 226 Ra is carried out by placing the waste in a 200 litter drum shell, 950 or 350 litter concrete shells, depends on the activity and dimension of the spent radiation source. The conditioning of 226 Ra is carried out by encapsulating the waste in a stainless steel container for long-term storage shield which then placed in a 200 litter drum shell. The temporary storage of the conditioned spent radiation source is carried out by storing it in the center’s temporary storages, either low or medium activity waste. Finally, the conditioned spent radiation source is buried in a disposal facility. For medium half-life spent radiation source, the final disposal is burial it in a shallow-land disposal; mean while, for long half-life spent radiation source, the final disposal is burial it in

  9. Sealed source peer review plan

    International Nuclear Information System (INIS)

    Feldman, Alexander; Leonard, Lee; Burns, Ron

    2009-01-01

    Sealed sources are known quantities of radioactive materials that have been encapsulated in quantities that produce known radiation fields. Sealed sources have multiple uses ranging from instrument calibration sources to sources that produce radiation fields for experimental applications. The Off-Site Source Recovery (OSR) Project at Los Alamos National Laboratory (LANL), created in 1999, under the direction of the Waste Management Division of the U.S. Department of Energy (DOE) Albuquerque has been assigned the responsibility to recover and manage excess and unwanted radioactive sealed sources from the public and private sector. LANL intends to ship drums containing qualified sealed sources to the Waste Isolation Pilot Plant (WIPP) for disposal. Prior to shipping, these drums must be characterized with respect to radiological content and other parameters. The U. S. Environmental Protection Agency (EPA) requires that ten radionulcides be quantified and reported for every container of waste to be disposed in the WIPP. The methods traditionally approved by the EPA include non-destructive assay (NDA) in accordance with Appendix A of the Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (DOE, 2002) (CH WAC). However, because of the nature and pedigree of historical records for sealed sources and the technical infeasibility of performing NDA on these sources, LANL proposes to characterize the content of these waste drums using qualified existing radiological data in lieu of direct measurement. This plan describes the process and documentation requirements for the use of the peer review process to qualify existing data for sealed radiological sources in lieu of perfonning radioassay. The peer review process will be performed in accordance with criteria provided in 40 CFR (section) 194.22 which specifies the use of the NUREG 1297 guidelines. The plan defines the management approach, resources, schedule, and technical requirements

  10. Safe management of spent radiation source

    International Nuclear Information System (INIS)

    Kosako, Toshiso; Sugiura, Nobuyuki; Valdezco, E.M.; Choi, Kwang-Sub

    2003-01-01

    Presented are 8 investigation reports concerning the safe management of spent radiation source (SRS) during the current 2 years. Four reports from Japan are: Scheme for SRS management (approach and present status of the SRS management and consideration toward solving problems); Current International Atomic Energy Agency (IAEA) activities related to safety of radiation sources (Chronology of action plan development, Outline of revised action plan, and Asian regional activities); Current status of SRS management in Japan (Regulation system, Obligations of licensed users, Regulatory system on sealed sources, Status in the incidents on sources occurred, Incident of source loss, and Incidents of orphan sources); and SRS management system in Japan (Current status of using of sealed sources, collection system of SRS-Japan Radioisotope Association (JRIA) services, and Disposal of SRS). Four reports from the Asian countries also concern the current statuses of SRS management in the Philippine (Radioactive waste sources, Waste management strategies, Conditioning of Ra sources, Ra project action plan, as low as reasonably achievable (ALARA) program, Dose assessment, Regulations on radioactive waste, Action plan on the safety and security of sources, IAEA Regional Demonstration Centers, and sitting studies for a near surface disposal facility); Thailand (Current status of using sealed sources, Inventory of SRS, and Current topics of SRS management); Indonesia (Principles of management of radiation sources, Legislative framework of SRS management practices, Regulatory on SRS, management of sealed SRS, management hurdles, and reported incidents); and Korea (Regulatory frame work, Collection systems of SRS, Radioisotope waste generation, Radiation exposure incident, and Scrap monitoring system). (N.I.)

  11. Keeping Sealed Radioactive Sources Safe and Secure

    International Nuclear Information System (INIS)

    Potterton, Louise

    2013-01-01

    Radioactive sources are used in a wide variety of devices in medical, industrial, agricultural and research facilities worldwide. These sources, such as cobalt-60 and caesium-137, emit high levels of ionizing radiation, which can treat cancer, measure materials used in industry and sterilize food and medical appliances. Problems may arise when these sources are no longer needed, or if they are damaged or decayed. If these sources are not properly stored they can be a threat to human health and the environment and pose a security risk. Procedures to secure these spent or 'disused' sources are often highly expensive and need specialized assistance. The IAEA helps its States find long term solutions for the safe and secure storage of disused sealed radioactive sources (DSRSs)

  12. Methods to identify and locate spent radiation sources

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs and tabs.

  13. Methods to identify and locate spent radiation sources

    International Nuclear Information System (INIS)

    1997-06-01

    The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs, tabs

  14. Methods to identify and locate spent radiation sources

    International Nuclear Information System (INIS)

    1995-07-01

    The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs and tabs

  15. Fabrication of sealed radiation sources

    International Nuclear Information System (INIS)

    Mars, Jean.

    1977-01-01

    The description is given for fabricating a sealed radiation source, consisting in depositing on a metal substrate a thin active coat of a radioelement, termed first coat, submitting this coated substrate to an oxidation treatment in order to obtain on the first coat an inactive coat of an oxide of the metal, termed second coat, and depositing a coat of varnish on this second inactive coat [fr

  16. Safety considerations of disposal of disused sealed sources in near surface facilities

    International Nuclear Information System (INIS)

    Pla, E.

    2003-01-01

    The report presents European commission studies on sealed radioactive sources - Management of Spent Radiation Sources in the European Union: Quantities, Storage, Recycling and Disposal. EUR 16960 EN. EC 1996; Management of sealed radioactive sources produced and sold in the Russian Federation. EUR 18191 EN. EC, 1999; Management and Disposal of Disused Sealed Radioactive Sources in the European Union. EUR 18186 EN. EC, 2000; Management of Spent Sealed Radioactive Sources in Central and Eastern Europe. EUR 19842 EN. EC, April 2001; Management of Spent Sealed Radioactive Sources in Bulgaria, Latvia, Lithuania, Romania and Slovakia. EUR 20654 EN. EC, January 2003. The conclusions and recommendations in them are given. The International catalogue of sealed radioactive sources and devices is described

  17. Management of disused sealed sources

    International Nuclear Information System (INIS)

    Lukauskas, D.; Skridaila, N.

    2003-01-01

    The report presents the requirements on management of disused sealed sources in Lithuania; disused sealed source disposal facilities; performed safety analysis and planed repository safety improvements. The requirements on pre-disposal management of Disused Sealed Sources (DSS) are presented. The requirements on disposal of short lived VLLW and LILW (A, B and C classes) radioactive waste approved in 2002-2003. Generic Waste Acceptance Criteria for Near Surface Disposal, P-2003-01 approved in 2003. Requirements on disposal of Low and intermediate level long lived waste do not exist (D and E classes). Requirements for the disposal of disused sealed sources (F class) do not exist. Disposal method for the F class - Near Surface or Deep geological repository, depending on the waste acceptance criteria. Only one repository for institutional radioactive waste exist in Lithuania - Maisiagala repository. It is near surface RADON type disposal facility, built in 1963 and closed in 1988. It was constructed of the monolithic reinforced concrete with the dimensions 5 m x 15 m x 3 m, the thickness of the sidewalls is about 0.25 m and the thickness of the bottom is about 0.2 m. The overall volume is about 200 m 3 . At time of closure only three fifths of the volume had been filled. The empty two fifths of the vault were filled with concrete, then with sand, then with the concrete (0.01 m), hot bitumen and the 0.05 m asphalt layers. Monolithic concrete that was covered with bitumen and 0.05 m thick layer of asphalt closed the vault. Sand layer the thickness of which was not less than 1.2 m formed the cap. Disused radioactive sources embedded in a biological shielding were buried together with their shielding, the sources without the shielding were buried in two stainless steel containers. The total activity of buried radioactive nuclides is 3.42.10 -15 Bq (calculated according the documentation). There are some uncertainties about the inventory: from 1963 to 1973. After the

  18. Spent fuel assembly source term parameters

    International Nuclear Information System (INIS)

    Barrett, P.R.; Foadian, H.; Rashid, Y.R.; Seager, K.D.; Gianoulakis, S.E.

    1993-01-01

    Containment of cask contents by a transport cask is a function of the cask body, one or more closure lids, and various bolting hardware, and seals associated with the cavity closure and other containment penetrations. In addition, characteristics of cask contents that impede the ability of radionuclides to move from an origin to the external environment also provide containment. In essence, multiple release barriers exist in series in transport casks, and the magnitude of the releasable activity in the cask is considerably lower than the total activity of its contents. A source term approach accounts for the magnitude of the releasable activity available in the cask by assessing the degree of barrier resistance to release provided by material characteristics and inherent barriers that impede the release of radioactive contents. Standardized methodologies for defining the spent-fuel transport packages with specified regulations have recently been developed. An essential part of applying the source term methodology involves characterizing the response of the spent fuel under regulatory conditions of transport. Thermal and structural models of the cask and fuel are analyzed and used to predict fuel rod failure probabilities. Input to these analyses and failure evaluations cover a wide range of geometrical and material properties. An important issue in the development of these models is the sensitivity of the radioactive source term generated during transport to individual parameters such as temperature and fluence level. This paper provides a summary of sensitivity analyses concentrating on the structural response and failure predictions of the spent fuel assemblies

  19. Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

    Directory of Open Access Journals (Sweden)

    T. Marpaung

    2012-08-01

    Full Text Available In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS, due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed source. The reuse and recycle policy for spent and disused sealed sources are not already specified yet. The reuse of spent sealed sources can be applied only for the sources which had been used in the medical field for radiotherapy, namely the reuse of a teletherapy Co-60 source in a calibration facility. The recycle of a spent sealed source can be performed for radioactive sources with relatively high activities and long half-lives; however, the recycling activity may only be performed by the manufacturer. To avoid legal conflicts, in the amendment to the Government Regulation No.27 Year 2002 on Management of Radioactive Waste, there will be a recommendation for a new scheme in the management of radioactive waste to facilitate the application of the principles of reduce, reuse, and recycle

  20. Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

    International Nuclear Information System (INIS)

    Marpaung, T.

    2012-01-01

    In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS), due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed source. The reuse and recycle policy for spent and disused sealed sources are not already specified yet. The reuse of spent sealed sources can be applied only for the sources which had been used in the medical field for radiotherapy, namely the reuse of a teletherapy Co-60 source in a calibration facility. The recycle of a spent sealed source can be performed for radioactive sources with relatively high activities and long half-lives; however, the recycling activity may only be performed by the manufacturer. To avoid legal conflicts, in the amendment to the Government Regulation No.27 Year 2002 on Management of Radioactive Waste, there will be a recommendation for a new scheme in the management of radioactive waste to facilitate the application of the principles of reduce, reuse, and recycle (author)

  1. Nature and magnitude of the problem of spent radiation sources

    International Nuclear Information System (INIS)

    1991-09-01

    Various types of sealed radiation sources are widely used in industry, medicine and research. Virtually all countries have some sealed sources. The activity in the sources varies from kilobecquerels in consumer products to hundreds of pentabecquerels in facilities for food irradiation. Loss or misuse of sealed sources can give rise to accidents resulting in radiation exposure of workers and members of the general public, and can also give rise to extensive contamination of land, equipment and buildings. In extreme cases the exposure can be lethal. Problems of safety relating to spent radiation sources have been under consideration within the Agency for some years. The first objective of the project has been to prepare a comprehensive report reviewing the nature and background of the problem, also giving an overview of existing practices for the management of spent radiation sources. This report is the fulfilment of this first objective. The safe management of spent radiation sources cannot be studied in isolation from their normal use, so it has been necessary to include some details which are relevant to the use of radiation sources in general, although that area is outside the scope of this report. The report is limited to radiation sources made up of radioactive material. The Agency is implementing a comprehensive action plan for assistance to Member States, especially the developing countries, in all aspects of the safe management of spent radiation sources. The Agency is further seeking to establish regional or global solutions to the problems of long-term storage of spent radiation sources, as well as finding routes for the disposal of sources when it is not feasible to set up safe national solutions. The cost of remedial actions after an accident with radiation sources can be very high indeed: millions of dollars. If the Agency can help to prevent even one such single accident, the cost of its whole programme in this field would be more than covered. Refs

  2. Encapsulation, shielding, and packaging for conditioning of spent radium sources

    International Nuclear Information System (INIS)

    Kang, I. S.; Kim, T. K.; Lee, B. C.; Kim, G. J.; Hong, K. P.

    2002-01-01

    The appropriate management and conditioning of spent radium sources have been risen to one of the greatest challenges faced by the international society. The expert teams in Korea were organized to tackle this problem by the request of IAEA and supported to condition sources in Southeastern Asia. The main object of this paper is to apply safely and effectively conditioning of spent sealed sources in our country near future by virtue of describing the technology on conditioning the national inventory of spent radium sources in Singapore. The paper is the result that the Korean expert team successfully carried out the conditioning of spent radium sources in Singapore with accumulated experiences. The conditioning operation was carried out under the supervision of IAEA's technical officer, Mr. Al-Mughrabi and Singapore Nuclear Cancer Centre. The 204 sources of spent radium stored in Singapore were encapsuled and welded in 17 small capsules and a large capsule, and conditioned in 2 lead shields, producing 2 package. As a result of this operation, a total amount of 938.56mg were conditioned and distributed into 2 shielding devices, holding 497.5mg and 441.06mg. In addition, the contaminated objects and the secondary wastes produced during segregation and dismantling of sources were immobilized in a plastic box

  3. Control of sealed radioactive sources in Peru

    International Nuclear Information System (INIS)

    Ramirez Quijada, R.

    2001-01-01

    The paper describes the inventory of radioactive sources in Peru and assesses the control. Three groups of source conditions are established: controlled sources, known sources, and lost and orphan sources. The potential risk, described as not significant, for producing accidents is established and the needed measures are discussed. The paper concludes that, while the control on sealed sources is good, there is still room for improvement. (author)

  4. Management of Disused Sealed Sources in Hungary - 13077

    International Nuclear Information System (INIS)

    Kapitany, Sandor

    2013-01-01

    Since 1976 the spent and disused radioactive sources arisen in Hungary are stored in a central storage facility called Radioactive Waste Treatment and Disposal Facility operated by Public Limited Company for Radioactive Waste Management. The Facility is responsible for the record keeping, the waste acceptance procedure, the shipment and the storage or disposal (whether a certain source meets the waste acceptance criteria for disposal or not) of sources. Based on the more than 35 year old operation of the facility many experiences have been gathered regarding the technology for long-term storage of sources, the attitude of the users of sources, the evolution of the legislation and the national record keeping system. Recently a new legislation for the security of radioactive materials (including sources) was introduced, first in Central-Europe. It requires special security arrangements from the facility for transport and for storage. Due to the ongoing retrieval of radioactive waste formerly disposed of, partly containing sealed sources, there is a new challenge in the physical inventory control of historical waste. The paper would show the effect of the changes in the legislation system of record keeping or security on the users' attitude for discard of sources and on the management of the sources in the facility. The facility has a unique storage technology (shallow boreholes) in the narrow region. The sealed sources are placed into vertical pipes sunk into the surface. In the beginning, each of the sources were dropped into the pipe directly, recently they are placed in a metal tube first ensuring the retrieval. The lessons learned will be presented. There were several issues to introduce the new security arrangements (partly financially supported by US DOE) for storage and for transportation of sealed sources. These issues are addressed. In the past part of the sealed sources were disposed together with solid radioactive waste packaged in plastic bags. A waste

  5. Management of Disused Sealed Sources in Hungary - 13077

    Energy Technology Data Exchange (ETDEWEB)

    Kapitany, Sandor [PURAM, Puskas Tivadar street 11, Budaors, Pest 2040 (Hungary)

    2013-07-01

    Since 1976 the spent and disused radioactive sources arisen in Hungary are stored in a central storage facility called Radioactive Waste Treatment and Disposal Facility operated by Public Limited Company for Radioactive Waste Management. The Facility is responsible for the record keeping, the waste acceptance procedure, the shipment and the storage or disposal (whether a certain source meets the waste acceptance criteria for disposal or not) of sources. Based on the more than 35 year old operation of the facility many experiences have been gathered regarding the technology for long-term storage of sources, the attitude of the users of sources, the evolution of the legislation and the national record keeping system. Recently a new legislation for the security of radioactive materials (including sources) was introduced, first in Central-Europe. It requires special security arrangements from the facility for transport and for storage. Due to the ongoing retrieval of radioactive waste formerly disposed of, partly containing sealed sources, there is a new challenge in the physical inventory control of historical waste. The paper would show the effect of the changes in the legislation system of record keeping or security on the users' attitude for discard of sources and on the management of the sources in the facility. The facility has a unique storage technology (shallow boreholes) in the narrow region. The sealed sources are placed into vertical pipes sunk into the surface. In the beginning, each of the sources were dropped into the pipe directly, recently they are placed in a metal tube first ensuring the retrieval. The lessons learned will be presented. There were several issues to introduce the new security arrangements (partly financially supported by US DOE) for storage and for transportation of sealed sources. These issues are addressed. In the past part of the sealed sources were disposed together with solid radioactive waste packaged in plastic bags. A

  6. Application of IAEA seals to spent-fuel cooling ponds at the Bruno Leuschner NPP, Greifswald

    International Nuclear Information System (INIS)

    Burmester, M.; Kahnmeyer, W.; Heidenreich, D; Kannenberg, D.

    1985-01-01

    A description is given of the technical appliances developed and routinely used at the Greifswald NPP to allow IAEA seals to be attached to the spent fuel cooling ponds as a whole or to their lower storage levels. (author)

  7. Radioactive sealed sources production process for industrial radiography

    International Nuclear Information System (INIS)

    Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S.

    2017-01-01

    providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

  8. Radioactive sealed sources production process for industrial radiography

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: hobeddaniel@gmail.com, E-mail: jrcamara@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energética s e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

  9. Radioactive sealed sources inventory and management

    International Nuclear Information System (INIS)

    Rodriguez C, G.; Mallaupoma G, M.; Cruz C, W.

    1996-01-01

    This report is related to the management of radioactive wastes, that is to say, related to the sealed sources utilized in industry, medicine and research jobs, that can not be used anymore, because of their life time termination or their activity decay to useless limits. Owing to this fact, it is necessary to take them to the Management Plant of Radioactive waste in the 'RACSO' Nuclear Center, as it is specified by the National Authority Technical Office (OTAN) regulations in Peru. The experience gained by IPEN in the sealed source management is shown in the table which informs about the radionuclide types, activity and volume amount for years. In the 'RACSO' Nuclear Center, 63 sealed sources are stored and right measures are being adopted in order to be conditioned by cementation in 200 lt steel reinforced cylinders, which are proper to their transportation and storage. A flow-chart shows the steps that the national users should follow in order to manage radioactive sealed sources and so that minimize the risks. Resulting from the agreement between the users and managers, a systematic coordination is developed, verifying the information related to the source characterization, the way of transportation and the future conditioning. It also involves the cost aspects, which in some cases, represent a big problem in the management. (authors). 3 refs., 3 figs., 1 tab

  10. Quality control of concretes for conditioning of spent radioactive sources

    International Nuclear Information System (INIS)

    Gonzalez N, M.

    2015-01-01

    The spent sealed radioactive sources are considered as a specific type of radioactive wastes and should be properly stored to ensure their integrity and prevent or limit the release of radionuclides in the geosphere. For this, these sources can be put up in concrete matrices. This research presents the evaluation and characterization of five concretes prepared with 4 brands of commercial cements: CPC Extra RS, CPC 30R Impercem of Cemex, Cruz Azul CPC 30R and CPC 30R of Apasco; three sizes of coarse aggregate (<30 mm, 29-11 mm and <10 mm) and fine aggregate (0.0797 mm) used as matrices for conditioning of spent sealed radioactive sources, in order to verify if these specific concretes accredit the standard NOM-019-Nucl-1995. After hardening for 28 days the concrete specimens were subjected to the tests: compressive strength; thermal cycles, irradiation, leaching and permeability, later to be characterized by: 1) X-ray diffraction in order to meet their crystalline phases; 2) scanning electron microscopy, to determine changes in morphology; 3) infrared spectroscopy, to determine the structural changes of concrete from its functional groups; 4) Raman spectroscopy to determine their structural changes and 5) Moessbauer spectroscopy, which determines changes in the oxidation state of iron in the concrete. According to the results and the changes presented by each concrete after applying the tests set by NOM-019-Nucl-1995, is concluded that the concrete made with cement Cemex brand (CPC 30-RS Extra), gravel of particle size 11-29 mm and sieved sand (0.0797 mm) can be used as matrices of spent sealed sources conditioning. Is remarkable a morphological and structural change of the concrete due to gamma irradiation and heat treatment. (Author)

  11. Installation for producing sealed radioactive sources

    International Nuclear Information System (INIS)

    Fradin, J.; Hayoun, C.

    1969-01-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [fr

  12. Development of methodology for the characterization of radioactive sealed sources

    International Nuclear Information System (INIS)

    Ferreira, Robson de Jesus

    2010-01-01

    Sealed radioactive sources are widely used in many applications of nuclear technology in industry, medicine, research and others. The International Atomic Energy Agency (IAEA) estimates tens of millions sources in the world. In Brazil, the number is about 500 thousand sources, if the Americium-241 sources present in radioactive lightning rods and smoke detectors are included in the inventory. At the end of the useful life, most sources become disused, constitute a radioactive waste, and are then termed spent sealed radioactive sources (SSRS). In Brazil, this waste is collected by the research institutes of the Nuclear Commission of Nuclear Energy and kept under centralized storage, awaiting definition of the final disposal route. The Waste Management Laboratory (WML) at the Nuclear and Energy Research Institute is the main storage center, having received until July 2010 about 14.000 disused sources, not including the tens of thousands of lightning rod and smoke detector sources. A program is underway in the WML to replacing the original shielding by a standard disposal package and to determining the radioisotope content and activity of each one. The identification of the radionuclides and the measurement of activities will be carried out with a well type ionization chamber. This work aims to develop a methodology for measuring or to determine the activity SSRS stored in the WML accordance with its geometry and determine their uncertainties. (author)

  13. An ideal sealed source life-cycle

    International Nuclear Information System (INIS)

    Tompkins, Joseph Andrew

    2009-01-01

    In the last 40 years, barriers to compliant and timely disposition of radioactive sealed sources have become apparent. The story starts with the explosive growth of nuclear gauging technologies in the 1960s. Dozens of companies in the US manufactured sources and many more created nuclear solutions to industrial gauging problems. Today they do not yet know how many Cat 1, 2, or 3 sources there are in the US. There are, at minimum, tens of thousands of sources, perhaps hundreds of thousands of sources. Affordable transportation solutions to consolidate all of these sources and disposition pathways for these sources do not exist. The root problem seems to be a lack of necessary regulatory framework that has allowed all of these problems to accumulate with no national plan for solving the problem. In the 1960s, Pu-238 displaced Pu-239 for most neutron and alpha source applications. In the 1970s, the availability of inexpensive Am-241 resulted in a proliferation of low energy gamma sources used in nuclear gauging, well logging, pacemakers, and X-ray fluorescence applications for example. In the 1980s, rapid expansion of worldwide petroleum exploration resulted in the expansion of Am-241 sources into international locations. Improvements of technology and regulation resulted in a change in isotopic distribution as Am-241 made Pu-239 and Pu-238 obsolete. Many early nuclear gauge technologies have been made obsolete as they were replaced by non-nuclear technoogies. With uncertainties in source end of life disposition and increased requirements for sealed source security, nuclear gauging technology is the last choice for modern process engineering gauging solutions. Over the same period, much was learned about licensing LLW disposition facilities as evident by the closure of early disposition facilities like Maxey Flats. The current difficulties in sealed source disposition start with adoption of the NLLW policy act of 1985, which created the state LLW compact system they

  14. Management of disused long lived sealed radioactive sources (LLSRS)

    International Nuclear Information System (INIS)

    2003-06-01

    The document provides advice the sealed source users and the national waste management organizations with the technical know-how on the management of disused and spent long lived sealed radioactive sources (LLSRS) and with the particular guidelines required for handling, conditioning for storage, and storage of these sources. The guidance is intended to assist in establishing compliance with the present standards, requirements, and adopted practices. It also provides background material for any possible technical assistance to developing countries and serves as a reference for technical staff involved with IAEA programmes on the subject. Because of the historic nature of many of the sources under this category and the lack of well developed technical procedures recognized on the international level, this publication can serve as a basis for establishing future handling and conditioning procedures. The LLSRS addressed in this publication are primarily those containing radionuclides having half-lives greater than 30 years. These sources may contain long lived alpha-emitters, mainly 238 Pu, 239 Pu, 237 Np, 241 Am, 226 Ra; beta-emitters: 14 C, and 63 Ni and could be neutron sources such as PuBe, RaBe and AmBe

  15. Conditioning experience for spent radium sources

    International Nuclear Information System (INIS)

    Kang, I. S.; Shon, J. S.; Kim, K. J.; Min, D. K.

    2001-01-01

    In order to avoid accidents that could be resulted from improper storage of spent radium sources, it is necessary to condition and store them safely. The program for safe conditioning of spent radium sources by IAEA has been established to assist the developing countries. The main object of this paper is to apply the technology that was adapted by IAEA for the conditioning the national inventory of Ra-226 sources in member states, as a part of IAEA's project with the Korean expert team. This paper is the result that the Korean expert team carried out spent radium conditioning, under the project title 'Radium Conditioning in Myanmar(INT4131-06646C)'. The whole inventory of spent radium sources 1,429.5mCi, was safely conditioned by the Korean expert team according to the manual under the supervision of IAEA's technical officer and the control of Myanmar authority on behalf of Myanmar. These sources were encapsuled and welded into 27 small capsules and 3 large capsules, and conditioned in 3 lead shields, producing 3 concrete-shielded drums. The inventories were distributed into 3 shielding devices, holding 500mCi, 459.5mCi, and 470mCi

  16. Reliability in sealing of canister for spent nuclear fuel

    International Nuclear Information System (INIS)

    Ronneteg, Ulf; Cederqvist, Lars; Ryden, Haakan; Oeberg, Tomas; Mueller, Christina

    2006-06-01

    The reliability of the system for sealing the canister and inspecting the weld that has been developed for the Encapsulation plant was investigated. In the investigation the occurrence of discontinuities that can be formed in the welds was determined both qualitatively and quantitatively. The probability that these discontinuities can be detected by nondestructive testing (NDT) was also studied. The friction stir welding (FSW) process was verified in several steps. The variables in the welding process that determine weld quality were identified during the development work. In order to establish the limits within which they can be allowed to vary, a screening experiment was performed where the different process settings were tested according to a given design. In the next step the optimal process setting was determined by means of a response surface experiment, whereby the sensitivity of the process to different variable changes was studied. Based on the optimal process setting, the process window was defined, i.e. the limits within which the welding variables must lie in order for the process to produce the desired result. Finally, the process was evaluated during a demonstration series of 20 sealing welds which were carried out under production-like conditions. Conditions for the formation of discontinuities in welding were investigated. The investigations show that the occurrence of discontinuities is dependent on the welding variables. Discontinuities that can arise were classified and described with respect to characteristics, occurrence, cause and preventive measures. To ensure that testing of the welds has been done with sufficient reliability, the probability of detection (POD) of discontinuities by NDT and the accuracy of size determination by NDT were determined. In the evaluation of the demonstration series, which comprised 20 welds, a statistical method based on the generalized extreme value distribution was fitted to the size estimate of the indications

  17. Reliability in sealing of canister for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Ronneteg, Ulf [Bodycote Materials Testing AB, Nykoeping (Sweden); Cederqvist, Lars; Ryden, Haakan [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Oeberg, Tomas [Tomas Oeberg Konsult AB, Karlskrona (Sweden); Mueller, Christina [Federal Inst. for Materials Research and Testing, Berlin (Germany)

    2006-06-15

    The reliability of the system for sealing the canister and inspecting the weld that has been developed for the Encapsulation plant was investigated. In the investigation the occurrence of discontinuities that can be formed in the welds was determined both qualitatively and quantitatively. The probability that these discontinuities can be detected by nondestructive testing (NDT) was also studied. The friction stir welding (FSW) process was verified in several steps. The variables in the welding process that determine weld quality were identified during the development work. In order to establish the limits within which they can be allowed to vary, a screening experiment was performed where the different process settings were tested according to a given design. In the next step the optimal process setting was determined by means of a response surface experiment, whereby the sensitivity of the process to different variable changes was studied. Based on the optimal process setting, the process window was defined, i.e. the limits within which the welding variables must lie in order for the process to produce the desired result. Finally, the process was evaluated during a demonstration series of 20 sealing welds which were carried out under production-like conditions. Conditions for the formation of discontinuities in welding were investigated. The investigations show that the occurrence of discontinuities is dependent on the welding variables. Discontinuities that can arise were classified and described with respect to characteristics, occurrence, cause and preventive measures. To ensure that testing of the welds has been done with sufficient reliability, the probability of detection (POD) of discontinuities by NDT and the accuracy of size determination by NDT were determined. In the evaluation of the demonstration series, which comprised 20 welds, a statistical method based on the generalized extreme value distribution was fitted to the size estimate of the indications

  18. Repatriation of disused sealed sources in Peru

    International Nuclear Information System (INIS)

    Mallaupoma, Mario; Abeyta, Cristy; Matzke, Jim

    2013-01-01

    Sealed radioactive sources are used around the world in medicine, industry and research within a wide range of applications. Sources may contain a large spectrum of radionuclides, which can have different levels of activity as well as different periods of half-life. At the end of their useful life, they are considered as worn-out or obsolete. However, the residual levels of radioactivity, which have those sources, can be high, representing a high radiation risk. This publication describes the technical actions carried out by the specialized group of the Peruvian Institute of Nuclear energy (IPEN) and Los Alamos National Laboratory which supports the program of 'Global Threat Reduction Initiative's' (GTRI) within the implementation of 'Offsite Source Recovery Program' (OSRP)

  19. Conditioning technology of spent radium sources

    International Nuclear Information System (INIS)

    Kang, Il Sik; Kim, K. J.; Jang, K. D.

    2001-03-01

    In order to avoid accidents that could be resulted from improper storage of spent radium sources, it is necessary to condition and store them safely. The program for safe conditioning of spent radium sources by IAEA has been established to assist the developing countries. The main object of this report is to understand well and apply the technology that was applied in conditioning the national inventory of Ra-226 sources in Myanmar, as a part of IAEA's project by the Korean expert team. The report is the result that the Korean expert team carried out in Myanmar under the project title 'Radium Conditioning Service in Myanmar(INT4131-06646C)'. As a result of the mission, a whole inventory, 1,429.5 mCi of spent radium sources was safely conditioned by the Korean expert team according to the manual under the supervision of IAEA's technical officer, Mr. Al-Mughrabi, and under the control of DAE authority. These sources were encapsuled in 27 small capsules and 3 large capsules, and conditioned in 3 lead shields, producing 3 packages. The inventories were distributed into 3 shielding devices, holding 500, 459.5, and 470 mCi

  20. C-188 cobalt-60 sealed source integrity: source monitoring

    International Nuclear Information System (INIS)

    Defalco, G.M.; Shah, V.

    1995-01-01

    The integrity of C-188 cobalt-60 sealed sources used for radiation processing will be a key factor in the continued industrial acceptance and growth of gamma irradiation technology. Given the public's relatively poor understanding of most nuclear topics and the news media's tendency to sensationalize events, it is appropriate for suppliers and users of gamma technology to be vigilant and conservative regarding the application of cobalt-60 sources to industrial purposes. Nordion's recent decision to extend the optional warranty on its C-188 cobalt-60 sealed source from 15 years to 20 years is based on over 30 years of data generated from its on-going SOURCE SURVEILLANCE PROGRAM. This paper presents an overview of the C-188 SOURCE SURVEILLANCE PROGRAM. (author)

  1. Disposal of disused sealed sources in France

    International Nuclear Information System (INIS)

    Certes, C.

    2003-01-01

    The current status of the disused sealed sources in France is presented and a proposal for future management is given.About 150 000 disused source are registered, most of which are located in the Centre de l'Aube (130 000) and the rest are in about 250 installations. Since 2002 the tracing of the sources are made bu the IRSN/UES. A scheme of sealed sources management is given consisting of collecting, channeling (recycling, reconditioning, interim storage, denaturation) and elimination (surface disposal, long interim or deep disposal). The capacity of the CDA for disposal is 1 mill. m 3 (about 2 mill. tons of waste). It is intended for waste packages containing (basic safety rule I.2) - Low and Intermediate specific activity levels ( ∼ 103 ∼ 106 Bq/g); Short-lived radionuclides (half-life 60 Co). For sources containing one concentrated long-lived radionuclide in case of non-conformity with the basic safety rule I.2 (heterogeneity and long half-life) for example refusal is received for a few sources containing 241 Am). Radiological capacity id base on inventories nad safety evaluation scenarios. Fixed by decree (TBq) are: 60 Co(5.3 y) - 400 000; 3 H(12.3 y) - 4000; 137 Cs(30 y); - 200 000; 90 Sr(29 y) -40 000; Σ alpha (at 300 years) - 750. Waste acceptance criterion is based on the mass activity limit. The importance of the calculation method in this criterion is emphasised. IRSN reflexion basis for disposal is discussed

  2. Aspects related to the testing of sealed radioactive sources

    International Nuclear Information System (INIS)

    Olteanu, C. M.; Nistor, V.; Valeca, S. C.

    2016-01-01

    Sealed radioactive sources are commonly used in a wide range of applications, such as: medical, industrial, agricultural and scientific research. The radioactive material is contained within the sealed source and the device allows the radiation to be used in a controlled way. Accidents can result if the control over a small fraction of those sources is lost. Sealed nuclear sources fall under the category of special form radioactive material, therefore they must meet safety requirements during transport according to regulations. Testing sealed radioactive sources is an important step in the conformity assessment process in order to obtain the design approval. In ICN Pitesti, the Reliability and Testing Laboratory is notified by CNCAN to perform tests on sealed radioactive sources. This paper wants to present aspects of the verifying tests on sealed capsules for Iridium-192 sources in order to demonstrate the compliance with the regulatory requirements and the program of quality assurance of the tests performed. (authors)

  3. Guidelines for testing sealed radiation sources

    International Nuclear Information System (INIS)

    1989-01-01

    These guidelines are based on article 16(1) of the Ordinance on the Implementation of Atomic Safety and Radiation Protection dated 11 October 1984 (VOAS), in connection with article 36 of the Executory Provision to the VOAS, of 11 October 1984. They apply to the testing of sealed sources to verify their intactness, tightness and non-contamination as well as observance of their fixed service time. The type, scope and intervals of testing as well as the evaluation of test results are determined. These guidelines also apply to the testing of radiation sources forming part of radiation equipment, unless otherwise provided for in the type license or permit. These guidelines enter into force on 1 January 1990

  4. Sealed radionuclide sources - new technical specifications and current practice

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D

    1987-03-01

    Basic technical specifications are discussed valid in Czechoslovakia for sealed radionuclide sources, based on international ISO and CMEA standards. Described are the standardization of terminology, relationships of tests, testing methods, types of sealed sources and their applications, relations to Czechoslovak regulations on radiation protection and to IAEA specifications for radioactive material shipment, etc. Practical impact is shown of the introduction of the new standards governing sealed sources on the national economy, and the purpose is explained of various documents issued with sealed sources. (author). 2 figs., 45 refs.

  5. Management of Disused Radioactive Sealed Sources in Egypt - 13512

    International Nuclear Information System (INIS)

    Mohamed, Y.T.; Hasan, M.A.; Lasheen, Y.F.

    2013-01-01

    The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Egypt depends on the safe and secure management of disused radioactive sealed sources. In the past years have determined the necessity to formulate and apply the integrated management program for radioactive sealed sources to assure harmless and ecological rational management of disused sealed sources in Egypt. The waste management system in Egypt comprises operational and regulatory capabilities. Both of these activities are performed under legislations. The Hot Laboratories and Waste Management Center HLWMC, is considered as a centralized radioactive waste management facility in Egypt by law 7/2010. (authors)

  6. Concretes characterization for spent radioactive sources

    International Nuclear Information System (INIS)

    Martinez B, J.; Monroy G, F. P.

    2013-10-01

    The present work includes the preparation and characterization of the concrete used as conditioning matrix of spent radioactive sources in the Treatment Plant of Radioactive Wastes of the Instituto Nacional de Investigaciones Nucleares (ININ). The concrete tests tubes were subjected to resistance assays to the compression, leaching, resistance to the radiation and porosity, and later on characterized by means of X rays diffraction, scanning electron microscopy and infrared spectrometry, with the purpose of evaluating if this concrete accredits the established tests by the NOM-019-Nucl-1995. The results show that the concrete use in the Treatment Plant fulfills the requirements established by the NOM-019-Nucl-1995. (author)

  7. The borehole disposal of spent sources (BOSS)

    International Nuclear Information System (INIS)

    Heard, R.G.

    2002-01-01

    During the International Atomic Energy Agency (IAEA) Regional Training Course on 'The Management of Low-Level Radioactive Waste from Hospitals and Other Nuclear Applications' hosted by the Atomic Energy Corporation of SA Ltd. (AEC), now NECSA, during July/August 1995, the African delegates reviewed their national radioactive waste programmes. Among the issues raised, which are common to most African countries, were the lack of adequate storage facilities, lack of disposal solutions and a lack of equipment to implement widely used disposal concepts to dispose of their spent sources. As a result of this meeting, a Technical Co-operation (TC) project was launched to look at the technical feasibility and economic viability of such a concept. Phase I and II of the project have been completed and the results can be seen in three reports produced by NECSA. The Safety Assessment methodology used in the evaluation of the concept was that developed during the ISAM programme and detailed in Van Blerk's PhD thesis. This methodology is specifically developed for shallow land repositories, but was used in this case as the borehole need not be more than 100m deep and could fit into the definition of a shallow land disposal system. The studies found that the BOSS concept would be suitable for implementation in African countries as the borehole has a large capacity for sources and it is possible that an entire country's disused sources can be placed in a single borehole. The costs are a lot lower than for a shallow land trench, and the concept was evaluated using radium (226) sources as the most limiting inventory. The conclusion of the initial safety assessment was that the BOSS concept is robust, and provides a viable alternative for the disposal of radium needles. The concept is expected to provide good assurance of safety at real sites. The extension of the safety assessment to other types of spent sources is expected to be relatively straightforward. Disposal of radium needles

  8. 10 CFR 39.35 - Leak testing of sealed sources.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Leak testing of sealed sources. 39.35 Section 39.35 Energy....35 Leak testing of sealed sources. (a) Testing and recordkeeping requirements. Each licensee who uses... record of leak test results in units of microcuries and retain the record for inspection by the...

  9. Methods to identify and locate spent radiation sources; Metodos para la identificacion y localizacion de fuentes radiactivas gastadas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs, tabs.

  10. Management and disposal of disused sealed radioactive sources in Europe

    International Nuclear Information System (INIS)

    Wells, D.A.; Angus, M.J.; Cecille, L.

    2001-01-01

    Full text: Sealed radioactive sources have been widely used for many decades in industry, medicine and research. Although most countries have laid down a regulatory framework to control sealed sources, there are still a number of uncertainties concerning the management of historical Ra- 226 alpha sources and the possibility of retrieving non-registered sources. Both these uncertainties may represent high radiological risks for the population. In addition, management schemes and practises implemented in different countries can be somewhat conflicting and create problems for storage and disposal. This paper describes the results of three studies that were carried out between 1998 and 2001 to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in each of the fifteen current European Union (EU) member states and the ten central and eastern European (C and EE) countries that are currently being considered for admission to the European Union (namely, Bulgaria, Czech Republic, Estonia, Hungary, Latvia, Lithuania, Poland, Romania, Slovakia and Slovenia). The general aim of the studies was to acquire a thorough understanding of the management of SSRS in each country, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous. The studies covered the following activities: Estimation of the inventory of SSRS in store and disposed in each country; Analysis of the relevant regulations and regulatory framework in each country; Description and review of the current management practises in each country; Estimation of the number of unregistered SSRS (including identification of the reasons why SSRS are lost' and recommending ways of recovering lost' sources). It was important to understand the full life-cycle of sealed radioactive sources, from manufacture through to disposal. Much of the information contained in these studies was obtained

  11. BOSS: Borehole Disposal of Disused Sealed Sources. A Technical Manual

    International Nuclear Information System (INIS)

    2011-01-01

    The management of disused radioactive sources is the responsibility of individual Member States. Accordingly, interest in technologies to allow the safe, secure and sustainable management of disused sealed radioactive sources is growing. This publication is a technical summary on preparing and planning predisposal and disposal activities with regard to the BOSS (borehole disposal of disused sealed sources) system, a safe, simple and cost effective solution for the management of disused sealed radioactive sources. It advises potential implementers and decision makers on the implementation of BOSS, which is expected to provide Member States with a successful tool to contribute to the safety and security of current and future generations.

  12. Management for the prevention of accidents from disused sealed radioactive sources

    International Nuclear Information System (INIS)

    2001-04-01

    The objective of this report is to provide advice to sealed radiation source (SRS) users, radioactive waste operators, and other concerned public sectors on the measures to be taken to reduce the risk of accidents associated with disused or spent SRS. The report also explains policies as well as technical and administrative procedures to minimize the risk of accidents and to mitigate the consequences should an accident occur. The report emphasizes areas of high risk in handling disused or spent SRS in any form and condition to help to save health, life and financial resources

  13. Introduction on the recycling of spent and disused radioactive sources

    International Nuclear Information System (INIS)

    Zhao Mingqiang; Zang Ruihua

    2011-01-01

    It is not only a stress of environment safety, but also a waste of huge resources to send directly to store spent and disused radioactive sources. This article reviews some important aspects of management suggestions recommended by IAEA and requirements of regulations in China for disposing the spent and disused radioactive sources. The present condition and benefit of recycling spent and disused sources are analyzed. Some suggestions on carrying out recycling in China are put forward too. (authors)

  14. Safe management of discussed sealed sources in Peru

    International Nuclear Information System (INIS)

    Mallaupoma, M.

    2000-01-01

    The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Peru, in the past years have determined the necessity to formulate and apply an Institutional policy to assure harmless and ecologically rational management of disused sealed sources in Peru. Some results of the studies, which served as a basis for design and construction of a facility for treatment, conditioning and storage of conditioned sealed sources are presented in this paper. The waste management system in Peru comprises operational and regulatory capabilities. Both of these activities are performed under a legislation. The Nuclear Research Center RACSO has a radioactive waste management department which is in charge of the management of disused sealed sources produced in the country. It is considered as a centralized waste processing and storage facility (WPSF). (author)

  15. Sealed Source Security and Disposition: Progress and Prospects - 13515

    International Nuclear Information System (INIS)

    Jennison, Meaghan; Martin, David W.; Cuthbertson, Abigail

    2013-01-01

    Due to their high activity and portability, unsecured or abandoned sealed sources could cause significant health or environmental damage. Further, some of these sources could be used either individually or in aggregate in radiological dispersal devices commonly referred to as 'dirty bombs', resulting in significant social disruption and economic impacts in the billions of dollars. Disposal access for disused sealed sources, however, has been a serious challenge. From 2008 to 2012, sealed source disposal was available to only 14 states; additionally, waste acceptance criteria for sealed sources at the low-level waste disposal facilities in operation both prior to and after 2012 exclude some common yet potentially dangerous sealed sources. Recent developments, however, suggest that significant improvement in addressing this challenge is possible, although challenges remain. These developments include 1) the initiation of operations at the Waste Control Specialists (WCS) commercial low-level radioactive waste (LLRW) disposal facility in Andrews County, Texas; 2) the potential for significant revisions of the U.S. Nuclear Regulatory Commission's (NRC) 1995 'Final Branch Technical Position on Concentration Averaging and Encapsulation' (1995 BTP); and 3) the Utah Department of Environmental Quality's (UDEQ) approval of a license variance for sealed source disposal at the EnergySolutions LLRW disposal facility near Clive, Utah. (authors)

  16. Categorization of In-use Radioactive Sealed Sources in Egypt

    International Nuclear Information System (INIS)

    Hasan, M.A.; Mohamed, Y.T.; El Haleim, K.A.

    2006-01-01

    Radioactive sealed sources have widespread applications in industry, medicine, research and education. While most sources are of relatively low activity, there are many of medium or very high activity. The mismanagement of high activity sources is responsible for most of the radiological accidents that result in loss of life or disabling injuries. Because of the variety of applications and activities of radioactive sources, a categorization system is necessary so that the controls that are applied to the sources are adequate with its radiological risk. The aim of this work is to use the international Atomic Energy Agency (IAEA) categorization system to provide a simple, logical system for grading radioactive sealed sources in Egypt. The categorizations of radioactive sealed sources are based on their potential to cause harm to human health. This study revealed that total of 1916 sources have been used in Egypt in the different applications with a total activity of 89400 Ci according to available data in October 2005. (authors)

  17. INEL storage facility for sealed sources from the commercial sector

    International Nuclear Information System (INIS)

    Kingsford, C.O.; Satterthwaite, B.C.

    1994-08-01

    Commercially owned sealed radiation sources determine by the US Nuclear Regulatory Commission to be a public health or safety hazard are accepted by the US Department of Energy, under the Atomic Energy Act of 1954, as material for reuse of recycle. To implement this policy, the sealed sources must be stored until proper disposition is determined. This report documents the investigation and selection process undertaken to locate a suitable storage facility at the Idaho National Engineering Laboratory

  18. Acceptance of spent nuclear fuel in multiple element sealed canisters by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E.R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: (1) failed fuel; (2) consolidated fuel and associated structural parts; (3) non-fuel-assembly hardware; (4) fuel in metal storage casks; (5) fuel in multi-element sealed canisters; (6) inspection and testing requirements for wastes; (7) canister criteria; (8) spent fuel selection for delivery; and (9) defense and commercial high-level waste packages. 14 refs., 27 figs

  19. International Catalogue of Sealed Radioactive Sources and Devices

    International Nuclear Information System (INIS)

    2010-01-01

    The international catalogue of sealed radioactive sources and devices have two major objectives. The first objective is to provide vital information for a wide range of individuals and organizations on industrially manufactured radioactive sources and devices. The second objective is to facilitate identification of design specifications based on limited information from orphan sources and devices to allow safe handling of these items.

  20. Spent grain as energy source for breweries

    Energy Technology Data Exchange (ETDEWEB)

    Scharf, P; Meyer-Pittroff, R [Technical Univ. of Munich, Freising (West Germany)

    1990-01-01

    About 1.7 million tons of spent grain are produced from brewing operations each year in the Federal Republic of Germany. Because there is more spent grain than can be sold as cattle fodder, other uses for this product are being sought. These include composting, methane generation, and direct combustion. Researchers are using anaerobic fermentation as a means of producing biogas and using waste energy from the brewery to heat the fermenter. Combustion of spent grain can give a net energy of 12.8 MJ per kg dry grain. With biogas production, about 15-20% of the whole primary energy or 50% of the primary energy used in the boiling house could be substituted by the biogas.

  1. R1800: a new Co 60 sealed source

    International Nuclear Information System (INIS)

    Freijo, Jose L.; Gomez, Gonzalo

    2005-01-01

    The increasing demand of Co 60 sealed sources in the international market has made necessary the development of new models of sealed sources. R 1800 type source up to 65 KCi has a design that allows to accommodate a wide spectrum of capsules with different specific activities. The company Dioxitek has developed the fabrication process and the design specifications needed to obtain the approval of the product. A first shipment of 100 KCi has been made with success to the United Kingdom in October of the current year. (author) [es

  2. Reducing Risks from Sealed Radioactive Sources in Medicine

    International Nuclear Information System (INIS)

    2014-01-01

    Sealed radioactive sources are commonly used in a variety of medical applications for both diagnosis and therapy. The sources used in medical applications usually have high levels of radioactivity and, therefore, have the potential to cause serious and life threatening injuries if used improperly or maliciously, or risky if they become lost or are stolen

  3. Potential GTCC LLW sealed radiation source recycle initiatives

    International Nuclear Information System (INIS)

    Fischer, D.

    1992-04-01

    This report suggests 11 actions that have the potential to facilitate the recycling (reuse or radionuclide) of surplus commercial sealed radiation sources that would otherwise be disposed of as greater-than-Class C low-level radioactive waste. The suggestions serve as a basis for further investigation and discussion between the Department of Energy, Nuclear Regulatory Commission, Agreement States, and the commercial sector. Information is also given that describes sealed sources, how they are used, and problems associated with recycling, including legal concerns. To illustrate the nationwide recycling potential, Appendix A gives the estimated quantity and application information for sealed sources that would qualify for disposal in commercial facilities if not recycle. The report recommends that the Department of Energy initiate the organization of a forum to explore the suggested actions and other recycling possibilities

  4. The Nonactinide Isotope and Sealed Sources Management Group

    International Nuclear Information System (INIS)

    Low, J. L.; Polansky, G. F.; Parks, D. L.

    2002-01-01

    The Nonactinide Isotope and Sealed Sources Management Group (NISSMG) is sponsored by the Department of Energy (DOE) Office of Environmental Management and managed by Albuquerque Operations Office (DOE/AL) to serve as a complex-wide resource for the management of DOE-owned Nonactinide Isotope and Sealed Source (NISS) materials. NISS materials are defined as including: any isotope in sealed sources or standards; and isotopes, regardless of form, with atomic number less than 90. The NISSMG assists DOE sites with the storage, reuse, disposition, transportation, and processing of these materials. The NISSMG has focused its efforts to date at DOE closure sites due to the immediacy of their problems. Recently, these efforts were broadened to include closure facilities at non-closure sites. Eventually, the NISSMG plans to make its resources available to all DOE sites. This paper documents the lessons learned in managing NISS materials at DOE sites to date

  5. Development of radioactive sealed sources in epoxy matrix

    International Nuclear Information System (INIS)

    Benega, Marcos A.G.; Nagatomi, Helio R.; Rostelato, Maria Elisa C.M.; Karan Junior, Dib; Souza, Carla D.; Tiezzi, Rodrigo; Rodrigues, Bruna T.; Peleias Junior, Fernando S.

    2013-01-01

    The aim of the present work is to study and develop commercial resins for manufacturing solid sealed sources. The sources are produced with radionuclides of barium-133, cesium-137 and cobalt-57. They are used in radiation detectors verification. For the immobilization of the radionuclides in the epoxy matrix, it is made use of emulsifying agents that ensure the miscibility between resin and aqueous radioactive solution, as well as curing agents for controlling, curing and sealing the standard radioactive solution completely. As a result, it is expected to obtain standard sealed sources and equivalent to water. The equivalence to water is an important and necessary characteristic. The radioisotopes used in nuclear medicine are supplied in an aqueous form and the resin applied must have a very similar density comparing to the water. The sources must also be comparable in quality to sources produced internationally, but with low cost and wide available materials in the market. It is intended to create a national technology able to meet the demand of this product in the domestic market and achieve excellence in quality through accreditation and certification of the product by the appropriate agencies. The study of the necessary parameters used in the production of these sources, will bring technology for the manufacture of other categories of standard sealed sources, those used for nuclear medicine, image, laboratories and industry. (author)

  6. Radiation exposure management over a decade in sealed sources fabrication

    International Nuclear Information System (INIS)

    Chougule, Nitin V.; Swaminathan, N.; Singh, P.; Sreenivas, V.; Bairwa, S.M.; Rath, D.P.; Patil, B.N.; Sastry, K.V.S.

    2008-01-01

    Radioactive sealed sources find innumerable applications in medical and industrial applications. 60 Co teletherapy sources are used for the treatment of cancer. In brachytherapy; 137 Cs and 192 Ir are used. Industrial sources using 60 Co, 137 Cs find applications in nucleonic gauges, tracer studies etc. 60 Co and 192 Ir sources are used in radiography also. In addition, 60 Co is widely used in irradiator facilities. Board of Isotopes and Radiation Technology (BRIT) has committed in supply of these sealed sources to various hospitals and industrial institutions in India. Annually, PetaBq (PBq) level of above mentioned isotopes are handled remotely in hot cells, RLG, BARC. This paper brings out a detailed account on the radiological surveillance provided during the fabrication of these sources implementing ALARA. The decrease in collective dose per activity handled is the outcome of improved operation practices which were carried out at various stages of source fabrication. (author)

  7. Management of spent sealed sources: The Philippine experience

    International Nuclear Information System (INIS)

    Valdezco, E.M.; Salom, D.S.; Dela Cruz, J.M.; Soriano, V.N.

    2000-01-01

    The Radiation Protection Services (RPS) provide nuclear services to all authorized users of radiation and radioactive materials in the country, including the operation and maintenance of the only centralized facility for the management, treatment and interim storage of conditioned low level radioactive wastes. Two basic waste treatment and conditioning options, adopted by the Philippine Nuclear Research Institute (PNRI) Centralized Waste Management Facility for the types and volume of waste arising in the country, are outlined. International activities within the framework of an IAEA project on a regional demonstration of predisposal waste management methods and procedures for the East Asia Pacific region are described. Information is provided on siting studies and related research and development activities for a waste repository facility. (author)

  8. Sealed source and device removal and consolidation feasibility study

    International Nuclear Information System (INIS)

    Ward, J.E.; Carter, J.G.; Meyers, R.L.

    1993-02-01

    The purpose of this study is to assess the feasibility of removing Greater-Than-Class C (GTCC) sealed sources from their containment device and consolidating them for transport to a storage or disposal facility. A sealed source is a sealed capsule containing a radioactive material that is placed in a device providing radioactive containment. It is used in the medical, industrial, research, and food-processing communities for calibrating, measuring, gauging, controlling processes, and testing. This feasibility study addresses the key operational, safety, regulatory, and financial requirements of the removal/consolidation process. This report discusses the process to receive, handle, repackage, and ship these sources to an interim or dedicated storage facility until a final disposal repository can be built and become operational (∼ c. 2010). The study identifies operational and facility requirements to perform this work. Hanford, other DOE facilities, and private hot-cell facilities were evaluated to determine which facilities could perform this work. The personnel needed, design and engineering, facility preparation, process waste disposal requirements, and regulatory compliance were evaluated to determine the cost to perform this work. Cost requirements for items that will have to meet future changing regulatory requirements for transportation, transportation container design and engineering, and disposal were not included in this study. The cost associated with in-process consolidation of the sealed sources reported in this study may have not been modified for inflation and were based on 1992 dollars. This study shows that sealed source consolidation is possible with minimal personnel exposure, and would reduce the risk of radioactive releases to the environment. An initial pilot-scale operation could evaluate the possible methods to reduce the cost and consolidate sources

  9. Dismantling, conditioning and repatriation of disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Aguilar, S.L.; Miranda, C.A.; Saire, A.E.; Ontiveros, G.P.

    2015-01-01

    In Bolivia sealed radioactive sources for medical, industrial and research applications are used; radioactive sources containing a wide range of radionuclides and have different levels of activity and half-lives, they generated a problem when they stop being used. At the end of its useful life these sources are considered obsolete. However, residual levels of radioactivity, which have these sources can be high constituting a potential hazard to personnel and applies to those who benefit from its use and the general public. The aim of this work has been focused mainly on safety issues in the safe handling and management of disused sealed sources. Assignments listed below: 1. Dismantling; 2. Packaging; 3. Return of disused sealed radioactive sources. The actions taken were carried out by the technical teams of the Bolivian Institute of Nuclear Science and Technology (IBTEN) and Los Alamos National Laboratory (LANS) which supports the program 'Global Threat Reduction Initiative's' (GTRI) in the implementation of 'Off -site Source Recovery Program' (OSRP). [es

  10. Radioactive waste management in sealed sources laboratory production

    International Nuclear Information System (INIS)

    Carvalho, Gilberto

    2001-01-01

    The laboratory of sealed sources production, of Instituto de Pesquisas Energeticas e Nucleares, was created in 1983 and since then, has produced radioactive sources for industry and engineering in general, having specialization in assembly of radiation sources for non destructive testings, by gammagraphy, with Iridium-192, that represents 98% of the production of laboratory and 2% with the Cobalt-60, used in nuclear gages. The aim of this work, is to quantify and qualify the radioactive wastes generated annually, taking into account, the average of radioactive sources produced, that are approximately 220 sources per year

  11. R I 800. A new cobalt-60 sealed source design

    International Nuclear Information System (INIS)

    Freijo, Jose L.; Gomez, Gonzalo

    2006-01-01

    The consolidation of the international market of Co-60 sources and the perspective of its growth has encouraged the development of new types of sealed sources. The model R I 800 is designed for activities up to 65 kCi and allows a large spectrum of capsules with different specific activities. During three years Dioxitek developed the process of fabrication and qualifications to comply the design requirements and succeeded in the product approval. Today, the initial lot at an industrial scale of R I 800 sources is under fabrication and a first partial shipment of 100 kCi to the United Kingdom was successfully carried out at the end of October 2005. The whole lot is for export. Due to the versatility of the R I 800 sealed sources it was possible to use as raw material 1 MCi of Co-60 imported from Russia, irradiated in Leningrad nuclear power plant. (author) [es

  12. Management of disused high-activity sealed radioactive sources: Opting for removal from the national territory

    Energy Technology Data Exchange (ETDEWEB)

    Mourão, Rogério Pimenta, E-mail: mouraor@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Since 2007 Brazil has been using the removal from its territory as a strategy for the management of sealed sources. Three campaigns have been carried out so far, each aiming at specific source types or categories. In the first of these campaigns in 2007, 126 neutron sources of American origin were repatriated to the USA, followed in 2010 by around 900 low activity sources (Categories 3 to 5, according to the IAEA classification system). Both operations were conducted by teams of the American institute Los Alamos National Laboratory. A third campaign, focused on high activity sources – essentially Cobalt-60 sources for teletherapy – was carried out between 2016 and 2017 and resulted in 81 spent high activity radioactive sources of American- and Canadian-origin been sent to Germany and the USA. This operation was carried out by a team of South Africa using a dedicated Mobile Hot Cell. The benefits to Brazil resulting from these operations are clear: increase in safety and security; availability of new precious storage space; less effort dedicated to the disused sealed sources storage; less space in the future borehole facility; financial gains in the selling or reuse of steel, lead and depleted uranium from the original shields. An overexposure incident occurred during the operation, in which a worker was exposed to a dose above the annual statutory limit. (author)

  13. Characterization of Greater-Than-Class C sealed sources. Volume 2, Sealed source characterization and future production

    International Nuclear Information System (INIS)

    Harris, G.; Griffel, A.

    1994-09-01

    Sealed sources are small, relatively high-activity radioactive sources typically encapsulated in a metallic container. The activities can range from less than 1 mCi to over 1,000 Ci. They are used in a variety of industries and are commonly available. Many of the sources will be classified as Greater-Than-Class C low-level radioactive waste (GTCC LLW) for the purpose of waste disposal. The US Department of Energy is responsible for disposing of this class of low-level radioactive waste. The characterization of a sealed source is essentially a function of the type of radiation it emits, the principal use for which it is applied, and the activity it contains. The types of radiation of most interest to the GTCC LLW Program are gamma rays and neutrons, since these are emitted by the highest activity sources. The principal uses of most importance are gamma irradiators, medical teletherapy, well logging probes, and other general neutron applications. Current annual production rates of potential Greater-Than-Class C (PGTCC) sources sold to specific licensees were estimated based on data collected from device manufacturers. These estimates were then adjusted for current trends in the industry to estimate future annual production rates. It is expected that there will be approximately 8,000 PGTCC sealed sources produced annually for specific licensees

  14. Sealed Radioactive Sources. Information, Resources, and Advice for Key Groups about Preventing the Loss of Control over Sealed Radioactive Sources

    International Nuclear Information System (INIS)

    2013-10-01

    Among its many activities to improve the safety and security of sealed sources, the IAEA has been investigating the root causes of major accidents and incidents since the 1980's and publishes findings so that others can learn from them. There are growing concerns today about the possibility that an improperly stored source could be stolen and used for malicious purposes. To improve both safety and security, information needs to be in the hands of those whose actions and decisions can prevent a source from being lost or stolen in the first place. The IAEA developed this booklet to help improve communication with key groups about hazards that may result from the loss of control over sealed radioactive sources and measures that should be implemented to prevent such loss of control. Many people may benefit from the information contained in this booklet, particularly those working with sources and those likely to be involved if control over a source is lost; especially: officials in government agencies, first responders, medical users, industrial users and the metal recycling industry. The general public may also benefit from an understanding of the fundamentals of radiation safety. This booklet is comprised of several stand-alone chapters intended to communicate with these key groups. Various accidents that are described and information that is provided are relevant to more than one key group and therefore, some information is repeated throughout the booklet. This booklet seeks to raise awareness of the importance of the safety and security of sealed radioactive sources. However, it is not intended to be a comprehensive 'how to' guide for implementing safety and security measures for sealed radioactive sources. For more information on these measures, readers are encouraged to consult the key IAEA safety and security-related publications identified in this booklet

  15. Integrated Management Program for Radioactive Sealed Sources in Egypt IMPRSS

    International Nuclear Information System (INIS)

    Hasan, A.; El-Adham, K.

    2004-01-01

    Sealed sources are usually in capsules made of stainless steel. They are the size of a pen or a finger and contain one of hundreds of radioactive elements (e.g., Iridium, Radium) or their isotopes. They are air-tight and very durable, contain the radioactive material but not radiation. They are used in the health sector, industry, military, and universities. Incidents occurred in Met Halfa, Egypt, 2000 (Iridium-192); Goiania, Brazil, 1987 (Cesium-137); Mexico and Southwest U.S., 1977 -1984 (Cobalt-60); Peru, 1999 (Iridium-1992); Poland 2001 (Cobalt-60). The IMPRSS Mission is based on a joined partnership between the Egyptian Atomic Energy Authority, the Egyptian Ministry of Health, the Sandia National Laboratories, the International Atomic Energy Agency and others. The IMPRSS Mission protects human health and the environment in Egypt from mismanaged sealed sources, is developed jointly with MOH and EAEA, provides capabilities for managing radioactive sealed sources in Egypt, increases public awareness, provides education and training, improves emergency response capabilities, develops a permanent disposal facility, ensures the program is self-sustaining and ensures close coordination with the IAEA. Infrastructure how to manage sealed sources is discussed. It includes awareness, tracking and inventory control, security, recovery, conditioning and storage, recycling and disposal. Emergency response, regulatory reform, education and training and its targets are provided. The government of Egypt can protect the people of Egypt and is ready for emergencies. Prevention is the first line of defence and detection is the second line of defence. Adequate Emergency Response saves lives and adequate control reduces risk of mismanaged uses or deliberate misuses of sources. A Cradle-to-Grave approach is built on existing capabilities at EAEA and MOH

  16. Characterization and packaging of disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Aguilar, S.L.

    2013-01-01

    In Bolivia are generated disused sealed sources and radioactive waste resulting from the use of radioactive materials in industrial, research and medicine. The last includes the diagnosis and treatment. Whereas exposure to ionizing radiation is a potential hazard to personnel who applies it, to those who benefit from its use or for the community at large, it is necessary to control the activities in this field. The Instituto Boliviano de Ciencia y Tecnologia Nuclear - IBTEN is working on a regional project from International Atomic Energy Agency - IAEA, RLA/09/062 Project - TSA 4, Strengthening the National Infrastructure and Regulatory Framework for the Safe Management of Radioactive waste in Latin America. This Project has strengthened the regulatory framework regarding the safe management of radioactive waste. The aim of this work was focused primarily on the security aspects in the safe management of disused sealed sources. The tasks are listed below: 1. Characterization of disused sealed sources 2. Preparation for transport to temporary storage 3. Control of all disused radioactive sources. (author)

  17. Radiation safety of sealed sources and equipment containing them

    International Nuclear Information System (INIS)

    1993-01-01

    The guide gives information and requirements concerning the technical construction, installation, use and licensing of devices containing sealed radioactive sources in order to ensure the operational safety. The requirements are in accordance with the international standards ISO 1677, ISO 2919, ISO 7205 and Nordic Recommendations on radiation protection for radionuclide gauges in permanent installation. The guide explains also the practical measures that must be taken into account when a radiation device is repaired, maintained or removed from the use. (8 refs.)

  18. Evaluation of methods to leak test sealed radiation sources

    International Nuclear Information System (INIS)

    Arbeau, N.D.; Scott, C.K.

    1987-04-01

    The methods for the leak testing of sealed radiation sources were reviewed. One hundred and thirty-one equipment vendors were surveyed to identify commercially available leak test instruments. The equipment is summarized in tabular form by radiation type and detector type for easy reference. The radiation characteristics of the licensed sources were reviewed and summarized in a format that can be used to select the most suitable detection method. A test kit is proposed for use by inspectors when verifying a licensee's test procedures. The general elements of leak test procedures are discussed

  19. Radiation safety and inventory of sealed radiation sources in Pakistan

    International Nuclear Information System (INIS)

    Ali, M.; Mannan, A.

    2001-01-01

    Sealed radiation sources (SRS) of various types and activities are widely used in industry, medicine, agriculture, research and teaching in Pakistan. The proper maintenance of records of SRS is mandatory for users/licensees. Since 1956, more than 2000 radiation sources of different isotopes having activities of Bq to TBq have been imported. Of these, several hundred sources have been disposed of and some have been exported/returned to the suppliers. To ensure the safety and security of the sources and to control and regulate the safe use of radiation sources in various disciplines, the Directorate of Nuclear Safety and Radiation Protection (DNSRP), the implementing arm of the regulatory authority in the country, has introduced a system for notifying, registering and licensing the use of all types of SRS. In order to update the inventory of SRS used throughout the country, the DNSRP has developed a database. (author)

  20. Control of sealed sources and equipments used in gammagraphy

    International Nuclear Information System (INIS)

    Sahyun, A.; Sordi, G.-M.A.A.; Biazzini Filho, F.L.

    1988-01-01

    The Radiation Protection Department of the IPEN-CNEN/SP, in 1987, formed a section incharged to control all radioactive material: a) received by the IPEN-CNEN/SP; b) produced by the IPEN-CNEN/SP; c) delivered from the IPEN-CNEN/SP. The aim of this section is to maintain a permanent control of all radioactive sources movement got at the IPEN-CNEN/SP. This control is performed with a microcomputer, trademark MICRODIGITAL, model TK3000 //e, 256 KBytes of memory, utilizing the TOTALWORKS program. This program permits to have the origin, characteristics and address of the radioactive sources, its sites in the IPEN, its uses, etc. Already we have put in the microcomputer, the control of the sealed sources produced used in nondestructive test, the inspection control of the gamagraphy irradiator and the control of the depleted sources. The next step is to introduce in the computer the inspection of the remote control of the irradiator. The aim of this paper is to describe the control program that was already put on. This radioactive material control was started with the sealed sources used in gamagraphy because we believe that is the field with the most likelihood of accident in the population, and therefore it's that need the most hard control about the site and the performance of the irradiation facility. (author) [pt

  1. Distribution of sealed sources in use or stored by user on-site in Republic of Bulgaria

    International Nuclear Information System (INIS)

    Simeonov, G.

    2001-01-01

    Full text: Distribution of the sealed sources (SS) in use or stored by user on-site in Republic of Bulgaria has been determined by using the categorization system proposed by Institut National des Radioelements (IRE), Belgium. The criteria used to categorize the SS were the handling and monitoring equipment needed for dismantling, checking and treatment of spent sealed sources (SSS) before storage and/or final disposal. The categorization system was proposed as a basis for estimation of the needs of equipment for the new treatment and storage facility for SSS in the site of Novi Han radioactive waste repository. The categorization used to evaluate the distribution of SS in use or stored by user on-site is shown in Table I. Sealed sources are widely used in Bulgaria for industrial, medical, domestic and scientific purposes. Presently, the list of registered users of sealed beta-gamma and neutron SS consists of 387 industrial users, 78 research and control users and 14 medical users. In addition there are 48 registered users of Pu-239 static eliminators and an estimated number shows about 1000 users of Pu-239, Am- 241 or Kr-85 sources in smoke detectors. Wide range of activities with SS is controlled by CUEAPP, as license is required for use and/or storage by user of every single source. An electronic data base of the licenses for use of atomic energy is operated by CUAEPP. The investigation covered the sealed sources registered in the data base. The number of sources in different categories, their use and typical activity have been determined. The same approach has been used separately for sealed sources in use, as well as for spent sources stored by user on-site. Special attention has been paid to high activity gamma-sources used in teletherapy and irradiators, as their activities were corrected for radioactive decay (reference date: March 2001); the exact location and conditions of use or storage of every such source were established. As a result of the

  2. Management of Spent and Disused Radiation Sources - The Zambian Experience

    International Nuclear Information System (INIS)

    Chabala, F.

    2002-01-01

    Zambia like all other countries in the world is faced with environmental problems brought about by a variety of human activities. In Zambia the major environmental issues as identified by Nation Environmental Action Plan (NEAP) of 1994 are water pollution, poor sanitation, land degradation, air pollution, poor waste management, misuse of chemicals, wildlife depletion and deforestation. Zambian has been using a lot of radioactive materials in its various industries. The country has taken several projects with help of external partners. These partners however left these projects in the hands of the Zambians without developing their capacities to manage these radioactive sources. The Government recognized the need to manage these sources and passed legislation governing the management of radioactive materials. The first act of Parliament on Radiation Protection work was passed in 1975 to legislate the use of ionizing radiation. However, because of financial constraints the Country is facing, these regulations have remained unimplemented. Fortunately the international Community has been working in partnership with the Zambian Government in the Management of Radioactive Material. Therefore this paper will present the following aspects of radioactive waste management in Zambia: review Existing Legislation in Zambia regarding management of spent/radioactive sources; capacity building in the field of management of radioactive waste; management of spent and disused radiation sources; existing disposal systems in Zambia regarding spent/orphaned sources; existing stocks of radioactive sources in the Zambian industries

  3. Characterization of Greater-Than-Class C sealed sources. Volume 3, Sealed sources held by general licensees

    International Nuclear Information System (INIS)

    Harris, G.

    1994-09-01

    This is the third volume in a series of three volumes characterizing the population of sealed sources that may become greater-than-Class C low-level radioactive waste (GTCC LLW). In this volume, those sources possessed by general licensees are discussed. General-licensed devices may contain sealed sources with significant amounts of radioactive material. However, the devices are designed to be safe to use without special knowledge of radiological safety practices. Devices containing Am-241 or Cm-244 sources are most likely to become GTCC LLW after concentration averaging. This study estimates that there are about 16,000 GTCC devices held by general licensees; 15,000 of these contain Am-241 sources and 1,000 contain Cm-244 sources. Additionally, this study estimates that there are 1,600 GTCC devices sold to general licensees each year. However, due to a lack of available information on general licensees in Agreement States, these estimates are uncertain. This uncertainty is quantified in the low and high case estimates given in this report, which span approximately an order of magnitude

  4. Prototypes of phosphorus-32 sealed sources for use in Brachytherapy

    International Nuclear Information System (INIS)

    Anaya Garro, Olgger; Vela Mora, Mariano; Revilla Silva, Angel Revilla

    2005-01-01

    It has developed prototypes of phosphorus-32 sealed sources for use in Brachytherapy. This one was made in two stages, at the first one, we designed and constructed the container (capsule), the filling system and the sealed system; at the second one, we made the irradiation of the capsules containing the 'target'. The prototypes was made of aluminum in cylindrical geometry. During the irradiation test was made using two different dimensions: one of 1 mm outer diameter and 1 cm length and another one of 0.8 mm outer diameter and 5 mm length. They were radiated in the core of the RP-10 research reactor, at 7.93 x10 13 n/cm 2 .s thermal neutron flux during 27 operation cycles. Activities of 144.53 MBq (3.91 mCi) and 107.67 MBq (2.91 mCi) was obtained for each case. This activities are adequate to restenosis and for some tumors treatment. We can observed that the capsules irradiated passed visual inspection in its physical integrity (leakage and geometry). It has been demonstrated, that the beta radiation for his minor power of penetration and its high interaction, causes major local damage to the malignant tissue, minimizing the damage of the healthy surrounding tissues. It has been advisable to use for the treatment of illnesses of the circulatory system and some tumors. At the present, the source of strontium-90 are the most beta ray source used, but of this one are obtained as fission product of uranium target, where valuable radioactive waste is generated, whereas if we were using phosphorus-32 that we propose, radioactive waste would not be generated since it would take place directly as sealed source, for reaction (n, β). (author)

  5. Design and production of activimeters verification sealed radioactive sources

    International Nuclear Information System (INIS)

    Serra, R.; Hernandez Rivero, A. T.; Oropesa, P.; Rapado, M.; Falcon, L.

    2006-01-01

    Measurement in a radionuclide calibrator (activimeter) of the doses to be administered to a patient for diagnosis or radiotherapeutic treatment is an essential element in Nuclear Medicine practice. To assure that patient will receive the optimal doses that guarantee the necessary quality of the image to be studied or optimum radiotherapeutic effect, the activity determination should fulfil established accuracy requirements. To this aim, the overall uncertainty in activity determination must not surpass a preestablished limit of about 10 % for the expanded uncertainty of the activity value (with a coverage factor k = 3). To have suitable equipment, periodically calibrated for specialized and authorized specialists and frequently verified in inter calibration periods to guarantee detection of any malfunctioning, are essential requirements to assure the compliance with the prescribed regulations and limiting values. This paper describes the design and production of two models of 137 Cs activimeters verification sealed radioactive sources elaborated with this aim at the Radionuclide Metrology Department of the Isotope Centre of Cuba. Taking into account the international experience in this field was defined 3 -10 MBq as convenient activity range, the 137 Cs as a suitable radionuclide, and a classification ISO/99/C22212 (ISO 2919:1999) for the sealed sources to be obtained. In designed and produced models the activity is bonded in a hydrogel copolymer obtained by gamma irradiation, in a 60 Co irradiator, of a mixture of a 137 Cs aqueous solution with an approximate activity of 5 MBq with two proper monomers (acrylamide and methacrylic acid). The density of obtained copolymer is similar to that of the radioactive solutions employed in nuclear medicine departments for diagnosis and therapy. The obtained sources have appropriate physical stability for a temperature range between 40 o C below zero and 80 o C, as well as for defined activity range. The stability of the

  6. Management of spent high activity radioactive sources (SHARS)

    International Nuclear Information System (INIS)

    2002-09-01

    The objective of this report is to provide all people involved in the handling and management of high activity sources with sufficient information about processes that are required for the safe management of spent high activity radioactive sources (SHARS). This includes examples of spent source management that are already taking place and also a description of the range of appropriate options that are available for each stage in the management process. This report also aims to identify the important issues to be addressed in order to develop a waste management strategy as part of the integrated management strategy that takes account of international experience and the guidance and principles that have been learned from that experience. This report relates specifically to SHARS, which are spent sources that have the potential, with short exposures, to produce acute health effects if handled incorrectly. In addition, they may also incur significant economic costs in any retrieval or environmental remediation operation, following loss of or damage to such a source. The report provides guidance on the technical, administrative and economic issues associated with SHARS from the moment they cease to be in use through to disposal, including temporary storage, transport, conditioning and interim storage

  7. The management and disposal of sealed sources in France

    International Nuclear Information System (INIS)

    Drogou, A.

    2005-01-01

    The utilisation of sealed sources is very widespread in France, both in the medical and industrial fields. The rules for the management and retrieval of the sources are defined in the Decree of 4 April 2002. The principle of the retrieval of the sources is reliant on the supplier who is obliged to take back these sources. Financial guarantee systems have consequently been established to provide compensation for any failure by the supplier to take back the sources. The problems today in France are the absence of a disposal route and the management of the orphan sources. These have been integrated into the drawing up of the National Waste Management Plan (PNGDR) issued by the Minister for the Environment. Certain ideas and principles for the disposal of the sources have already been presented: Development of the principles of justification and recycling, development of disposal routes, development of a retrieval system for orphan sources; the importance of the establishment of financial guarantees for all the sources, the importance of consistency between the European regulations in order to have a simple return to the supplier in the case of imported sources. (author)

  8. Borehole disposal of spent radiation sources: 1. Principles

    International Nuclear Information System (INIS)

    Blerk, J.J. van; Kozak, M.W.

    2000-01-01

    Large numbers of spent radiation sources from the medical and other technical professions exist in many countries, even countries that do not possess facilities related to the nuclear fuel cycle, that have to be disposed. This is particularly the case in Africa, South America and some members of the Russian Federation. Since these sources need to be handled separately from the other types of radioactive waste, mainly because of their activity to volume ratio, countries (even those with access to operational repositories) find it difficult to manage and dispose this waste. This has led to the use of boreholes as disposal units for these spent sources by some members of the Russian Federation and in South Africa. However, the relatively shallow boreholes used by these countries are not suitable for the disposal of isotopes with long half-lifes, such as 226 Ra and 241 Am. With this in mind the Atomic Energy Corporation of South Africa initiated the development of the BOSS disposal concept - an acronym for Borehole disposal Of Spent Sources - as part of an International Atomic Energy Agency (IAEA) AFRA I-14 Technical Corporation (TC) project. In this paper, the principles of this disposal concept, which is still under development, will be discussed. (author)

  9. Verification of Spent Nuclear Fuel in Sealed Dry Storage Casks via Measurements of Cosmic-Ray Muon Scattering

    Science.gov (United States)

    Durham, J. M.; Poulson, D.; Bacon, J.; Chichester, D. L.; Guardincerri, E.; Morris, C. L.; Plaud-Ramos, K.; Schwendiman, W.; Tolman, J. D.; Winston, P.

    2018-04-01

    Most of the plutonium in the world resides inside spent nuclear reactor fuel rods. This high-level radioactive waste is commonly held in long-term storage within large, heavily shielded casks. Currently, international nuclear safeguards inspectors have no stand-alone method of verifying the amount of reactor fuel stored within a sealed cask. Here we demonstrate experimentally that measurements of the scattering angles of cosmic-ray muons, which pass through a storage cask, can be used to determine if spent fuel assemblies are missing without opening the cask. This application of technology and methods commonly used in high-energy particle physics provides a potential solution to this long-standing problem in international nuclear safeguards.

  10. Review of Sealed Source Designs and Manufacturing Techniques Affecting Disused Source Management

    International Nuclear Information System (INIS)

    2012-10-01

    This publication presents an investigation on the influence of the design and technical features of sealed radioactive sources (SRSs) on predisposal and disposal activities when the sources become disused. The publication also addresses whether design modifications could contribute to safer and/or more efficient management of disused sources without compromising the benefits provided by the use of the sealed sources. This technical publication aims to collect information on the most typical design features and manufacturing techniques of sealed radioactive sources and examines how they affect the safe management of disused sealed radioactive sources (DSRS). The publication also aims to assist source designers and manufacturers by discussing design features that are important from the waste management point of view. It has been identified that most SRS manufacturers use similar geometries and materials for their designs and apply improved and reliable manufacturing techniques e.g. double- encapsulation. These designs and manufacturing techniques have been proven over time to reduce contamination levels in fabrication and handling, and improve source integrity and longevity. The current source designs and materials ensure as well as possible that SRSs will maintain their integrity in use and when they become disused. No significant improvement options to current designs have been identified. However, some design considerations were identified as important to facilitate source retrieval, to increase the possibility of re-use and to ensure minimal contamination risk and radioactive waste generation at recycling. It was also concluded that legible identifying markings on a source are critical for DSRS management. The publication emphasizes the need for a common understanding of the radioactive source's recommended working life (RWL) for manufacturers and regulators. The conditions of use (COU) are important for the determination of RWL. A formal system for specification

  11. Basic design and construction of a mobile hot cell for the conditioning of spent high activity radioactive sources

    International Nuclear Information System (INIS)

    An Hongxiang; Fan Zhiwen; Al-Mughrabi, M.

    2011-01-01

    The conditioning of spent high activity radioactive sources is one important step in sealed radioactive sources management strategies. Based on the practice on the designing of the immobilized hot cell, the handling of the sealed radioactive sources, and the reference of the mobile hot cell constructed in South Africa, SHARS conditioning process and the basic design of a mobile hot cell is developed. The mobile hot cell has been constructed and the tests including the cold test of the SRS conditioning, the hot cell assemble and disassemble and SRS recovery were done. The shielding capacity were tested by 3.8 x 10 13 Bq cobalt-60 sources and the dose rate of the equipment surface, below 2 m, is less than 0.016 mSv/h. It is proved that the designing requirement is meet and the function of the equipment is good. (authors)

  12. Seals

    International Nuclear Information System (INIS)

    Welsher, R.A.G.

    1982-01-01

    An aperture through a biological shield is sealed by a flexible sheath having a beading at one end located on an annular member slidable in the aperture such that the beading bears in sealing engagement against the sides of the aperture. The annular member is retained by a retractable latch and can be rejected by pushing it out of the aperture using a replacement annular member with a replacement sheath thereon to butt against the annular member to be rejected. The replacement annular member may be mounted on a tubular device having an outer co-axial member for operating the latch when the replacement annular member butts against the annular member to be rejected. Applications include effecting a seal between a remote handling equipment and a wall through which the equipment extends. (author)

  13. COBRA-SFS thermal analysis of a sealed storage cask for the Monitored Retrievable Storage of spent fuel

    International Nuclear Information System (INIS)

    Rector, D.R.; Wheeler, C.L.

    1986-01-01

    The COBRA-SFS (Spent Fuel Storage) computer code was used to predict temperature distributions in a concrete Sealed Storage Cask (SSC). This cask was designed for the Department of Energy in the Monitored Retrievable Storage (MRS) program for storage of spent fuel from commercial power operations. Analytical results were obtained for nominal operation of the SSC with spent fuel from 36 PWR fuel assemblies consolidated in 12 cylindrical canisters. Each canister generates 1650 W of thermal power. A parametric study was performed to assess the effects on cask thermal performance of thermal conductivity of the concrete, the fin material, and the amount of radial reinforcing steel bars (rebar). Seven different cases were modeled. The results of the COBRA-SFS analysis of the current cask design predict that the peak fuel cladding temperature in the SSC will not exceed the 37 0 C design limit for the maximum spent fuel load of 19.8 kW and a maximum expected ambient temperature of 37.8 0 C (100 0 F). The results of the parametric analyses illustrate the importance of material selection and design optimization with regard to the SSC thermal performance

  14. Overview in Argentina on spent/disused radiation sources

    International Nuclear Information System (INIS)

    Lavalle, M.B.

    2001-01-01

    Argentine nuclear activities have begun since about 1950. Since those days the peaceful applications of nuclear energy have been developed and together with then radioactive wastes have taken more and more relevance day by day. To deal with this special subject the Radioactive Waste Management Programme (RWMP) has been established. Spent/disused radiation sources are a very important task to consider in the management of radioactive waste. A great number of sources have been received along these years by the RWMP. Different sources categories handled together with their figures and radionuclide activities will be presented. Also described will be the steps that have to be followed by the users/owners of spent/disused radiation sources to transfer them to the RWMP. Once the sources are in the RWMP custody, they can be stored or they can be conditioned in order to be stored in an interim storage or disposed of. It is shown how the different sources are managed, taking into account the radionuclide's half life, its activity and the available facilities. Besides a record-keeping system for tracking all spent/disused radiation sources has been developed. It consists on a computerized database that contains essential information about the sources as well as the whole radioactive wastes managed by the RWMP. The main objective of the waste management registry-database system is to collect, identify, process and follow the related information about the radioactive wastes among al the management steps. It is also able to calculate the actualized activity inventory for the storage and final disposal facilities. In order to implement this system, it was necessary to write the related technical documentation. These documents established the radioactive waste acceptance requirements, that together with others integrates the Quality Assurance System applied to the radioactive waste management. Regarding the disused sources little could be done. They are stored in an appropriate

  15. Development and application of test apparatus for classification of sealed source

    International Nuclear Information System (INIS)

    Kim, Dong Hak; Seo, Ki Seog; Bang, Kyoung Sik; Lee, Ju Chan; Son, Kwang Je

    2007-01-01

    Sealed sources have to conducted the tests be done according to the classification requirements for their typical usages in accordance with the relevant domestic notice standard and ISO 2919. After each test, the source shall be examined visually for loss of integrity and pass an appropriate leakage test. Tests to class a sealed source are temperature, external pressure, impact, vibration and puncture test. The environmental test conditions for tests with class numbers are arranged in increasing order of severity. In this study, the apparatus of tests, except the vibration test, were developed and applied to three kinds of sealed source. The conditions of the tests to class a sealed source were stated and the difference between the domestic notice standard and ISO 2919 were considered. And apparatus of the tests were made. Using developed apparatus we conducted the test for 192 Ir brachytherapy sealed source and two kinds of sealed source for industrial radiography. 192 Ir brachytherapy sealed source is classified by temperature class 5, external pressure class 3, impact class 2 and vibration and puncture class 1. Two kinds of sealed source for industrial radiography are classified by temperature class 4, external pressure class 2, impact and puncture class 5 and vibration class 1. After the tests, Liquid nitrogen bubble test and vacuum bubble test were done to evaluate the safety of the sealed sources

  16. Development of quality assurance procedures for production of sealed radiation source

    CERN Document Server

    Nam, J H; Cho, W K; Han, H S; Hong, S B; Kim, K H; Kim, S D; Lee, Y G; Lim, N J

    2001-01-01

    The quality assurance procedures for sealed radiation sources production using HANARO and RIPF have been developed. The detailed quality assurance procedures are essential to manage the whole work process effectively and ensure the quality of the produced sealed sources. Through applying this quality assurance procedures to the entire production works of the sealed radiation sources, it is expected that the quality of the products, the safety of the works and the satisfaction of the customers will be increased.

  17. Closure of the Spent Fuel Repository in Forsmark - Studies of alternative concepts for sealing of ramp, shafts and investigation boreholes

    Energy Technology Data Exchange (ETDEWEB)

    Gylling, Bjoern [SKB AB, Stockholm (Sweden); Luterkort, David [SGI, Stockholm (Sweden); Johansson, Roland [Miljoe- och Energikonsult AB, Ekeroe (Sweden)

    2012-12-15

    In March 2011, SKB submitted applications under the Nuclear Activities Act and the Environmental Code for the construction and operation of a final repository for spent nuclear fuel in Forsmark. An important supporting document for the application under the Nuclear Activities Act was the SR-Site safety assessment. As a part of the work with the application and as background material for SR-Site, SKB prepared production reports, including the closure production report. The closure production report presented definitions, requirements and design premises, a reference design and the initial state for repository closure. SR-Site evaluated the reference design and related design premises that were presented in the closure production report. SR-Site thereby concluded that the design premises on which the reference design were based are adequate. Relaxing the requirements would require additional sensitivity analyses focusing on the hydraulic properties of the access, main and transport tunnels. SR-Site further concluded that the reference design could likely be simplified without violating the current design premises. Furthermore, additional simplifications could probably be made if the design premises could be revised. This has been studied in the project 'Closure - concept studies', whose results are presented in this report. SR-Site also evaluated the reference design for investigation boreholes that is presented in the production report. The evaluation showed that the impact of improper borehole seals is very moderate. Further, SR-Site concludes that the current design premises are appropriate but possibly too strict, since even open boreholes seem to have a limited impact on the groundwater flow in the repository. Since it might be difficult to inspect the outcome of the current design of borehole sealing, it could be of interest to assess whether a solution that may result in higher effective permeability of the borehole seals would provide sufficiently

  18. 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)

  19. Algorithms for the process management of sealed source brachytherapy

    International Nuclear Information System (INIS)

    Engler, M.J.; Ulin, K.; Sternick, E.S.

    1996-01-01

    Incidents and misadministrations suggest that brachytherapy may benefit form clarification of the quality management program and other mandates of the US Nuclear Regulatory Commission. To that end, flowcharts of step by step subprocesses were developed and formatted with dedicated software. The overall process was similarly organized in a complex flowchart termed a general process map. Procedural and structural indicators associated with each flowchart and map were critiqued and pre-existing documentation was revised. open-quotes Step-regulation tablesclose quotes were created to refer steps and subprocesses to Nuclear Regulatory Commission rules and recommendations in their sequences of applicability. Brachytherapy algorithms were specified as programmable, recursive processes, including therapeutic dose determination and monitoring doses to the public. These algorithms are embodied in flowcharts and step-regulation tables. A general algorithm is suggested as a template form which other facilities may derive tools to facilitate process management of sealed source brachytherapy. 11 refs., 9 figs., 2 tabs

  20. 10 CFR 34.27 - Leak testing and replacement of sealed sources.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Leak testing and replacement of sealed sources. 34.27... SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.27 Leak testing and replacement... radiographic exposure device and leak testing of any sealed source must be performed by persons authorized to...

  1. Management of disused sealed sources from the nuclear industry in China

    International Nuclear Information System (INIS)

    Fan Xuanlin

    2002-01-01

    Since the founding of the nuclear industry in China, more than 8000 disused sealed sources accumulated of which more than 1800 are Radium sources. Most of these sources were produced during the period 1960-1980. The disused radioactive sources are temporarily stored in a user's interim store. A project to manage these disused sealed sources is under way which includes inventory investigation, inspection, collection, transportation and long-term storage. (author)

  2. The ultimate solution. Disposal of disused sealed radioactive sources (DSRS)

    International Nuclear Information System (INIS)

    Heard, R.G.

    2011-01-01

    The borehole disposal concept (BDC) was first presented to ICEM by Potier, J-M in 2005. This paper repeats the basics introduced by Potier and relates further developments. It also documents the history of the development of the BDC. For countries with no access to existing or planned geological disposal facilities for radioactive wastes, the only options for managing high activity or long-lived disused radioactive sources are to store them indefinitely, return them to the supplier or find an alternative method of disposal. Disused sealed radioactive sources (DSRS) pose an unacceptable radiological and security risk if not properly managed. Out of control sources have already led to many high-profile incidents or accidents. One needs only to remember the recent accident in India that occurred earlier this year. Countries without solutions in place need to consider the future management of DSRSs urgently. An on-going problem in developing countries is what to do with sources that cannot be returned to the suppliers, sources for which there is no further use, sources that have not been maintained in a working condition and sources that are no longer suitable for their intended purpose. Disposal in boreholes is intended to be simple and effective, meeting the same high standards of long-term radiological safety as any other type of radioactive waste disposal. It is believed that the BDC can be readily deployed with simple, cost-effective technologies. These are appropriate both to the relatively small amounts and activities of the wastes and the resources that can realistically be found in developing countries. The South African Nuclear Energy Corporation Ltd (Necsa) has carried out project development and demonstration activities since 1996. The project looked into the technical feasibility, safety and economic viability of BDC under the social, economic, environmental and infrastructural conditions currently prevalent in Africa. Implementation is near at hand with

  3. Shielding design of disposal container for disused sealed radioactive source

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Suk Hoon; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of)

    2017-06-15

    Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised.

  4. Shielding design of disposal container for disused sealed radioactive source

    International Nuclear Information System (INIS)

    Kim, Suk Hoon; Kim, Ju Youl

    2017-01-01

    Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised

  5. Quality assurance program plan for FRG sealed isotopic heat sources project (C-229)

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This QAPP implements the Quality Assurance Program Plan for the FRG Sealed Isotopic Heat Sources Project (C-229). The heat source will be relocated from the 324 Building and placed in interim storage at the Central Waste Complex (CWC)

  6. Radiotracer and Sealed Source Applications in Sediment Transport Studies

    International Nuclear Information System (INIS)

    2014-01-01

    The investigation of sediment transport in seas and rivers is crucial for civil engineering and littoral protection and management. Coastlines and seabeds are dynamic regions, with sediments undergoing periods of erosion, transport, sedimentation and consolidation. The main causes for erosion in beaches include storms and human actions such as the construction of seawalls, jetties and the dredging of stream mouths. Each of these human actions disrupts the natural flow of sand. Current policies and practices are accelerating the beach erosion process. However, there are viable options available to mitigate this damage and to provide for sustainable coastlines. Radioactive methods can help in investigating sediment dynamics, providing important parameters for better designing, maintaining and optimizing civil engineering structures. Radioisotopes as tracers and sealed sources have been useful and often irreplaceable tools for sediment transport studies. The training course material is based on lecture notes and practical works delivered by many experts in IAEA supported activities. Lectures and case studies were reviewed by a number of specialists in this field

  7. Management of disused sealed sources from nuclear gauges

    International Nuclear Information System (INIS)

    Reis, Luiz Carlos Alves; Silva, Fabio

    2001-01-01

    In Brazil there are about 600 Radioactive Facilities that operate 3300 nuclear gauges. The management goal for these sources is minimize the waste that must be stored and disposed, through reutilization or a more efficient method of disposal conditioning. A database is being implemented in order to facilitate the organization and retrieval of information about sources stored at CDTN. Examples of the information being included are: radionuclide, activity and date (e.g. 60 Co, 1 GBq, January 14th 1988); physical and chemical form of radionuclide; producer of the source; source type including dimensions and shape; source serial number; results of tests which have been done, for example leak tests; details of the equipment, i.e. dimensions, material, etc.; measured dose rates (at the surface and at I-m distance from it); whether the source was originally conditioned as special form radioactive material; working life of the equipment, etc. It is intended to reutilize only sealed sources containing certified special form radioactive material. Sources received at CDTN with this certification will be wipe tested in a hot-cell. A special Geiger Muller detector for measuring very low level radiation will be used to detect leakage at detection levels, even lower than the established leakage limit in the CNEN-NE-5.01 Standard. If the source does not exhibit leakage and the shutter operation and shielding of the nuclear gauge is in good condition, it will made available for reuse at a cost savings to the user over the purchase of a new source. Nuclear gauges whose sources do not meet these requirements will be dismantled and the sources efficiently conditioned. The CDTN guidelines for establishing a methodology for conditioning disused sources are: Dismantling the nuclear gauges in the hot-cell; Collecting the sources in an double-lead shielded cylindrical cavity below the hot-cell, until the limit of activity or level is reached; Transferring the internal shielding with the

  8. Vacuum seals design and testing for a linear accelerator of the National Spallation Neutron Source

    International Nuclear Information System (INIS)

    Chen, Z.; Gautier, C.; Hemez, F.; Bultman, N.K.

    2000-01-01

    Vacuum seals are very important to ensure that the Spallation Neutron Source (SNS) Linac has an optimum vacuum system. The vacuum joints between flanges must have reliable seals to minimize the leak rate and meet vacuum and electrical requirements. In addition, it is desirable to simplify the installation and thereby also simplify the maintenance required. This report summarizes an investigation of the metal vacuum seals that include the metal C-seal, Energized Spring seal, Helcoflex Copper Delta seal, Aluminum Delta seal, delta seal with limiting ring, and the prototype of the copper diamond seals. The report also contains the material certifications, design, finite element analysis, and testing for all of these seals. It is a valuable reference for any vacuum system design. To evaluate the suitability of several types of metal seals for use in the SNS Linac and to determine the torque applied on the bolts, a series of vacuum leak rate tests on the metal seals have been completed at Los Alamos Laboratory. A copper plated flange, using the same type of delta seal that was used for testing with the stainless steel flange, has also been studied and tested. A vacuum seal is desired that requires significantly less loading than a standard ConFlat flange with a copper gasket for the coupling cavity assembly. To save the intersegment space the authors use thinner flanges in the design. The leak rate of the thin ConFlat flange with a copper gasket is a baseline for the vacuum test on all seals and thin flanges. A finite element analysis of a long coupling cavity flange with a copper delta seal has been performed in order to confirm the design of the long coupling cavity flange and the welded area of a cavity body with the flange. This analysis is also necessary to predict a potential deformation of the cavity under the combined force of atmospheric pressure and the seating load of the seal. Modeling of this assembly has been achieved using both HKS/Abaqus and COSMOS

  9. Vacuum seals design and testing for a linear accelerator of the National Spallation Neutron Source

    Energy Technology Data Exchange (ETDEWEB)

    Z. Chen; C. Gautier; F. Hemez; N. K. Bultman

    2000-02-01

    Vacuum seals are very important to ensure that the Spallation Neutron Source (SNS) Linac has an optimum vacuum system. The vacuum joints between flanges must have reliable seals to minimize the leak rate and meet vacuum and electrical requirements. In addition, it is desirable to simplify the installation and thereby also simplify the maintenance required. This report summarizes an investigation of the metal vacuum seals that include the metal C-seal, Energized Spring seal, Helcoflex Copper Delta seal, Aluminum Delta seal, delta seal with limiting ring, and the prototype of the copper diamond seals. The report also contains the material certifications, design, finite element analysis, and testing for all of these seals. It is a valuable reference for any vacuum system design. To evaluate the suitability of several types of metal seals for use in the SNS Linac and to determine the torque applied on the bolts, a series of vacuum leak rate tests on the metal seals have been completed at Los Alamos Laboratory. A copper plated flange, using the same type of delta seal that was used for testing with the stainless steel flange, has also been studied and tested. A vacuum seal is desired that requires significantly less loading than a standard ConFlat flange with a copper gasket for the coupling cavity assembly. To save the intersegment space the authors use thinner flanges in the design. The leak rate of the thin ConFlat flange with a copper gasket is a baseline for the vacuum test on all seals and thin flanges. A finite element analysis of a long coupling cavity flange with a copper delta seal has been performed in order to confirm the design of the long coupling cavity flange and the welded area of a cavity body with the flange. This analysis is also necessary to predict a potential deformation of the cavity under the combined force of atmospheric pressure and the seating load of the seal. Modeling of this assembly has been achieved using both HKS/Abaqus and COSMOS

  10. Offsite source recovery project - ten years of sealed source recovery and disposal

    Energy Technology Data Exchange (ETDEWEB)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA

    2010-01-01

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources (this number has since increased to more than 23,000). This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Decades later, these sources began to exceed their special form certifications or fall out of regular use. As OSRP has collected and stored sealed sources, initially using 'No Path Forward' waste exemptions for storage within the Department of Energy (DOE) complex, it has consistently worked to create disposal pathways for the material it has recovered. The project was initially restricted to recovering sealed sources that would meet the definition of Greater-than-Class-C (GTCC) low-level radioactive waste, assisting DOE in meeting its obligations under the Low-level Radioactive Waste Policy Act Amendments (PL 99-240) to provide disposal for this type of waste. After being transferred from DOE-Environmental Management (EM) to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as GTCC when it became waste, but also any other materials that might constitute a 'national security consideration.' It was recognized at the time that the GTCC category was a waste designation having to do with environmental consequence, rather than the threat posed by deliberate or accidental misuse. The project faces barriers to recovery in many areas, but disposal continues to be one of the more difficult to overcome. This paper discusses OSRP's disposal efforts over its 10-year history. For sources

  11. Strategy for verification and demonstration of the sealing process for canisters for spent fuel

    International Nuclear Information System (INIS)

    Mueller, Christina; Oeberg, Tomas

    2004-08-01

    Electron beam welding and friction stir welding are the two processes now being considered for sealing copper canisters with Sweden's radioactive waste. This report outlines a strategy for verification and demonstration of the encapsulation process which here is considered to consist of the sealing of the canister by welding followed by quality control of the weld by non-destructive testing. Statistical methodology provides a firm basis for modern quality technology and design of experiments has been successful part of it. Factorial and fractional factorial designs can be used to evaluate main process factors and their interactions. Response surface methodology with multilevel designs enables further optimisation. Empirical polynomial models can through Taylor series expansions approximate the true underlying relationships sufficiently well. The fitting of response measurements is based on ordinary least squares regression or generalised linear methods. Unusual events, like failures in the lid welds, are best described with extreme value statistics and the extreme value paradigm give a rationale for extrapolation. Models based on block maxima (the generalised extreme value distribution) and peaks over threshold (the generalised Pareto distribution) are considered. Experiences from other fields of the materials sciences suggest that both of these approaches are useful. The initial verification experiments of the two welding technologies considered are suggested to proceed by experimental plans that can be accomplished with only four complete lid welds each. Similar experimental arrangements can be used to evaluate process 'robustness' and optimisation of the process window. Two series of twenty demonstration trials each, mimicking assembly-line production, are suggested as a final evaluation before the selection of welding technology. This demonstration is also expected to provide a data base suitable for a baseline estimate of future performance. This estimate can

  12. Strategy for verification and demonstration of the sealing process for canisters for spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, Christina [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany); Oeberg, Tomas [Tomas Oeberg Konsult AB, Lyckeby (Sweden)

    2004-08-01

    Electron beam welding and friction stir welding are the two processes now being considered for sealing copper canisters with Sweden's radioactive waste. This report outlines a strategy for verification and demonstration of the encapsulation process which here is considered to consist of the sealing of the canister by welding followed by quality control of the weld by non-destructive testing. Statistical methodology provides a firm basis for modern quality technology and design of experiments has been successful part of it. Factorial and fractional factorial designs can be used to evaluate main process factors and their interactions. Response surface methodology with multilevel designs enables further optimisation. Empirical polynomial models can through Taylor series expansions approximate the true underlying relationships sufficiently well. The fitting of response measurements is based on ordinary least squares regression or generalised linear methods. Unusual events, like failures in the lid welds, are best described with extreme value statistics and the extreme value paradigm give a rationale for extrapolation. Models based on block maxima (the generalised extreme value distribution) and peaks over threshold (the generalised Pareto distribution) are considered. Experiences from other fields of the materials sciences suggest that both of these approaches are useful. The initial verification experiments of the two welding technologies considered are suggested to proceed by experimental plans that can be accomplished with only four complete lid welds each. Similar experimental arrangements can be used to evaluate process 'robustness' and optimisation of the process window. Two series of twenty demonstration trials each, mimicking assembly-line production, are suggested as a final evaluation before the selection of welding technology. This demonstration is also expected to provide a data base suitable for a baseline estimate of future performance

  13. Strategy for verification and demonstration of the sealing process for canisters for spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, Christina [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany); Oeberg, Tomas [Tomas Oeberg Konsult AB, Lyckeby (Sweden)

    2004-08-01

    Electron beam welding and friction stir welding are the two processes now being considered for sealing copper canisters with Sweden's radioactive waste. This report outlines a strategy for verification and demonstration of the encapsulation process which here is considered to consist of the sealing of the canister by welding followed by quality control of the weld by non-destructive testing. Statistical methodology provides a firm basis for modern quality technology and design of experiments has been successful part of it. Factorial and fractional factorial designs can be used to evaluate main process factors and their interactions. Response surface methodology with multilevel designs enables further optimisation. Empirical polynomial models can through Taylor series expansions approximate the true underlying relationships sufficiently well. The fitting of response measurements is based on ordinary least squares regression or generalised linear methods. Unusual events, like failures in the lid welds, are best described with extreme value statistics and the extreme value paradigm give a rationale for extrapolation. Models based on block maxima (the generalised extreme value distribution) and peaks over threshold (the generalised Pareto distribution) are considered. Experiences from other fields of the materials sciences suggest that both of these approaches are useful. The initial verification experiments of the two welding technologies considered are suggested to proceed by experimental plans that can be accomplished with only four complete lid welds each. Similar experimental arrangements can be used to evaluate process 'robustness' and optimisation of the process window. Two series of twenty demonstration trials each, mimicking assembly-line production, are suggested as a final evaluation before the selection of welding technology. This demonstration is also expected to provide a data base suitable for a baseline estimate of future performance. This estimate can

  14. State of the art of the welding method for sealing spent nuclear fuel canister made of copper. Part 2 - EBW

    International Nuclear Information System (INIS)

    Salonen, T.

    2014-05-01

    This report consist the results of the development of the electron beam welding (EBW) method for sealing spent nuclear fuel (SNF) disposal canister. This report has been used as background material for selection of the sealing method for the SNF canister. Report contains the state of the art knowledge of the EBW method and research and development (R and D) results done by Posiva. Relevant R and D results of EB-welds done by SKB are also reviewed in this report. Requirements set for the welding and weld are present. These requirements are based on the long term safety and also some part of requirements are set by other processes like non-destructive testing (NDT) and manufacturing processes of components. Initial state of the weld is described in this report. Initial state has significant effect on the long term safety issues like corrosion resistance and creep ductility. Also short and long term mechanical properties as well as corrosion properties are described. Microstructure and residual stresses of the weld is represented in this report. Report consists also imperfections of the weld and statistical analysis of the evaluation of the probability of the largest defect size on the weld. Results of corrosion and creep tests of EB-welds are reviewed in this report. EBW process and machine are described. Preliminary designing of the EBW-machine has been done including component handling equipments. Preliminary welding procedure specification (pWPS) has drawn up and qualification of the personnel is described briefly. In-line process and quality control system including seam tracking system is implemented in modern EBW machine. Also NDT methods for inspection of the weld are described in this report. Concerning the results from the research and development work it can be concluded that EB welding method is suitable method for sealing SNF canister. Weld material fulfils requirements set by the long term safety. The welding system is robust and reliable and it is based

  15. Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

    CERN Document Server

    International Atomic Energ Agency. Vienna

    2003-01-01

    Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a ...

  16. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    Energy Technology Data Exchange (ETDEWEB)

    Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  17. Order of 25 March 1981 concerning the approval of special form radioactive materials in sealed sources

    International Nuclear Information System (INIS)

    1981-01-01

    This order determines the models of sealed sources which constitute special form radioactive materials within the meaning of the Order of 24 November 1977 concerning the characteristics of such materials. (NEA) [fr

  18. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    International Nuclear Information System (INIS)

    Haffner, D.R.; Villelgas, A.J.

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities

  19. Source and special nuclear material sealing and labeling requirements

    International Nuclear Information System (INIS)

    Jordan, K.N.

    1978-04-01

    Purpose of this document is to define requirements for the use of tamper-indicating seals and identifying labels on SS Material containers at Rockwell Hanford Operations. The requirements defined in this document are applicable to all Rockwell Hanford Operation employees involved in handling, processing, packaging, transferring, shipping, receiving or storing SS Material

  20. Sealed source and device design safety testing. Volume 4: Technical report on the findings of Task 4, Investigation of sealed source for paper mill digester

    International Nuclear Information System (INIS)

    Benac, D.J.; Iddings, F.A.

    1995-10-01

    This report covers the Task 4 activities for the Sealed Source and Device Safety testing program. SwRI was contracted to investigate a suspected leaking radioactive source that was installed in a gauge that was on a paper mill digester. The actual source that was leaking was not available, therefore, SwRI examined another source. SwRI concluded that the encapsulated source examined by SwRI was not leaking. However, the presence of Cs-137 on the interior and exterior of the outer encapsulation and hending tube suggests that contamination probably occurred when the source was first manufactured, then installed in the handling tube

  1. Diagnosis of Catalyst Cooler and Riser in RFCC using Sealed gamma-ray Source

    International Nuclear Information System (INIS)

    Kim, Jin Seop; Kim, Jong Bum; Jung, Sung Hee; Kim, Jae Ho

    2005-12-01

    With a quantitative growth of the petroleum industry, a lot of budget are spent for the maintenance and repairs of facilities related to the process annually. Among them, the RFCC(residual fluid catalytic cracking) is a highly value-added unit which converts gas oil and heavier streams to lighter, more valuable products such as propylene, gasoline by an injection of atmospheric residue into the fluided catalyst. In this study, field experiments were performed to analyze the reasons of an abnormal operation in the catalyst cooler and the catalyst riser belonged to the RFCC unit respectively and to estimate the amount of seriousness using sealed gamma-ray source( 60 Co). The catalyst cooler functions cooling for the regeneration of a catalyst, which will be used to a new media in the RFCC unit. The catalyst riser, while, plays an important part in transporting to next cyclotron steps by mixing of an oil, steam and a catalyst mechanically. The purposes of this study is what was the condition of catalyst flow pattern and whether the coke was produced in an inside process or not. Gamma radiation counts were measured by the detector(NaI) positioned outside the pipe-wall diametrically opposite to the gamma source with a regular space. From the results, the section different from the distribution pattern of nearby catalyst in a facility was found. And this became the definitive information to a process operator. Diagnosis technique using gamma radiation source is proved to be the effective and reliable method in providing information on the media distribution in a facility

  2. Spent yeast as natural source of functional food additives

    Science.gov (United States)

    Rakowska, Rita; Sadowska, Anna; Dybkowska, Ewa; Świderski, Franciszek

    Spent yeasts are by-products arising from beer and wine production which over many years have been chiefly used as feed additives for livestock. They contain many valuable and bioactive substances which has thereby generated much interest in their exploitation. Up till now, the main products obtained from beer-brewing yeasts are β-glucans and yeast extracts. Other like foodstuffs include dried brewer’s yeast, where this is dried and the bitterness removed to be fit for human consumption as well as mannan-oligosaccharides hitherto used in the feed industry. β-glucans constitute the building blocks of yeast cell walls and can thus be used in human nutrition as dietary supplements or serving as food additives in functional foods. β-glucans products obtained via post-fermentation of beer also exhibit a high and multi-faceted biological activity where they improve the blood’s lipid profile, enhance immunological status and have both prebiotic and anti-oxidant properties. Yeast extracts are currently being used more and more to enhance flavour in foodstuffs, particularly for meat and its products. Depending on how autolysis is carried out, it is possible to design extracts of various meat flavours characteristic of specific meats. Many different flavour profiles can be created which may be additionally increased in combination with vegetable extracts. Within the food market, yeast extracts can appear in various guises such as liquids, pastes or powders. They all contain significant amounts of glutamic acid, 5’-GMP and 5’-IMP nucleotides together with various amino acids and peptides that act synergistically for enhancing the flavour of foodstuff products. Recent studies have demonstrated additional benefits of yeast extracts as valuable sources of amino acids and peptides which can be used in functional foods and dietary supplements. These products possess GRAS status (Generally Recognised As Safe) which thereby also adds further as to why they should be used

  3. Conditioning of disused sealed sources in countries without disposal facility: Short term gain - long term pain

    International Nuclear Information System (INIS)

    Benitez-Navarro, J.C.; Salgado-Mojena, M.

    2002-01-01

    Owing to the considerable development in managing disused sealed radioactive sources (DSRS), the limited availability of disposal practices for them, and the new recommendations for the use of borehole disposal concept, it was felt that a paper reviewing the existing recommendations could be a starting point of discussion on the retrievability of the sources. Even when no international consensus exists as to an acceptable solution for the challenge of disposal of disused sealed sources, the 'Best Available Technology' for managing most of them, recommended for developing countries, included the cementation of the sources. The waste packages prepared in such a way do not allow any flexibility to accommodate possible future disposal requirements. Therefore, the 'Wait and See' approach could be also recommended for managing not only the sources with long-live radionuclides and high activity, but probably for all kind of existing disused sealed sources. The general aim of the current paper is to identify and review the current recommendations for managing disused sealed sources and to meditate on the most convenient management schemes for disused sealed radioactive sources in Member States without disposal capacities (Latin America, Africa). The risk that cemented DSRS could be incompatible with future disposal requirements was taken into account. (author)

  4. Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

    Energy Technology Data Exchange (ETDEWEB)

    Fradin, J.; Hayoun, C. [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

  5. Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

    Energy Technology Data Exchange (ETDEWEB)

    Fradin, J; Hayoun, C [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

  6. Radiation protection rules for handling of sealed radioactive sources in medicine

    International Nuclear Information System (INIS)

    1985-02-01

    The rules presented here relate to the use of sealed radioactive sources in medical therapy, with the radioactive sources being temporarily or permanently incorporated into body cavities or body tissues, or fixed to the body surface. They also relate to radioactive sources with dimensions below 5 mm (as e.g. seeds). (orig./HP) [de

  7. Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

    International Nuclear Information System (INIS)

    2003-08-01

    Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a high potential risk to workers and to the public. The IAEA has received numerous requests for assistance from Member States faced with the problem of safely managing disused sealed sources. The requests have related to both technical and safety aspects. Particularly urgent requests have involved emergency situations arising from unsafe storage conditions and lost sources. There is therefore an important requirement for the development of safe and cost-effective final disposal solutions. Consequently, a number of activities have been initiated by the IAEA to assist Member States in the management of disused sealed sources. The objective of this report is to address safety issues relevant to the disposal of disused sealed sources, and other limited amounts of radioactive waste, in borehole facilities. It is the first in a series of reports aiming to provide an indication of the present issues related to the use of borehole disposal facilities to safely disposal

  8. Safety assessment of the disposal of sealed radiation sources in boreholes

    International Nuclear Information System (INIS)

    Oliveira, Rosana Lagua de; Vicente, Roberto; Hiromoto, Goro

    2009-01-01

    The Radioactive Waste Management Laboratory (RNML) at the Nuclear Energy Research Institute (NERI) in Sao Paulo, Brazil, is developing the concept of a repository for disused sealed radiation sources in a deep borehole. Several thousands disused sealed radiation sources are stored at NERI awaiting the decision on final disposal and tens of thousands are still under the possession of the licensees. A significant fraction of these sources are long-lived and will require final disposal in a geological repository. The purpose of this paper is to identify and discuss suitable safety assessment strategies for the repository concept and to illustrate a rational approach for a long-term safety assessment methodology. (author)

  9. Experience and problems of the automated measuring and sorting of sealed radiation sources

    International Nuclear Information System (INIS)

    Shmidt, G.

    1979-01-01

    It has been shown that with the help of a serial device for samples changing and a mini-computer with a suitable software it is possible to organize the radioactivity measuring and sorting of sealed gamma-sources with activity in the microcuri region. Application of the computer permits to rise accuracy of the data on the radiation sources radioactivity, sorted according to the preset activity level groups and, in the casa of necessity, to perform the activity measurements with lower error. The method listed, gives the working-time economy of nearly 4 hours in measuring and sorting of some 500 sealed radiation sources [ru

  10. Guide for the preparation of applications for licenses for the use of sealed sources in portable gauging devices

    International Nuclear Information System (INIS)

    1985-01-01

    The purpose of this regulatory guide is to provide assistance to applicants and licensees in preparing applications for new licenses, license amendments, and license renewals for the use of sealed sources in portable gauging devices. An example of a portable gauging device is a moisture-density gauge that contains a gamma-emitting sealed source, cesium-137, and a sealed neutron source, americium-242-beryllium

  11. SOURCE OF BURNUP VALUES FOR COMMERCIAL SPENT NUCLEAR FUEL ASSEMBLIES

    International Nuclear Information System (INIS)

    BSC

    2004-01-01

    Waste packages are loaded with commercial spent nuclear fuel (SNF) that satisfies the minimum burnup requirements of a criticality loading curve. The burnup value assigned by the originating nuclear utility to each SNF assembly (assigned burnup) is used to load waste packages in compliance with a criticality loading curve. The burnup provided by a nuclear utility has uncertainties, so conservative calculation methods are used to characterize those uncertainties for incorporation into the criticality loading curves. Procedural safety controls ensure that the correct assembly is loaded into each waste package to prevent a misload that could create a condition affecting the safety margins. Probabilistic analyses show that procedural safety controls can minimize the chance of a misload but can not completely eliminate the possibility. Physical measurements of burnup with instrumentation in the surface facility are not necessary due to the conservative calculation methods used to produce the criticality loading curves. The reactor records assigned burnup of a commercial SNF assembly contains about two percent uncertainty, which is increased to five-percent to ensure conservatism. This five-percent uncertainty is accommodated by adjusting the criticality loading curve. Also, the record keeping methods of nuclear utilities are not uniform and the level of detail required by the NRC has varied over the last several decades. Thus, some SNF assemblies may have assigned burnups that are averages for a batch of assemblies with similar characteristics. Utilities typically have access to more detailed core-follow records that allow the batch average burnup to be changed to an assembly specific burnup. Alternatively, an additional safety margin is incorporated into the criticality loading curve to accommodate SNF assemblies with batch average burnups or greater uncertainties due to the methodology used by the nuclear utility. The utility records provide the assembly identifier

  12. Safety assessment of borehole disposal of unwanted radioactive sealed sources in Egypt using Goldsim

    International Nuclear Information System (INIS)

    Cochran, John Russell; Mattie, Patrick D.

    2004-01-01

    A radioactive sealed source is any radioactive material that is encased in a capsule designed to prevent leakage or escape of the radioactive material. Radioactive sealed sources are used for a wide variety of applications at hospitals, in manufacturing and research. Typical uses are in portable gauges to measure soil compaction and moisture or to determine physical properties of rocks units in boreholes (well logging). Hospitals and clinics use radioactive sealed sources for teletherapy and brachytherapy. Oil exploration and medicine are the largest users. Accidental mismanagement of radioactive sealed sources each year results in a large number of people receiving very high or even fatal does of ionizing radiation. Deliberate mismanagement is a growing international concern. Sealed sources must be managed and disposed effectively in order to protect human health and the environment. Effective national safety and management infrastructures are prerequisites for efficient and safe transportation, treatment, storage, and disposal. The Integrated Management Program for Radioactive Sealed Sources in Egypt (IMPRSS) is a cooperative development agreement between the Egyptian Atomic Energy Authority (EAEA), Egyptian Ministry of Health (MOH), Sandia National Laboratories (SNL), the University of New Mexico (UNM), and Agriculture Cooperative Development International (ACDI/VOCA). The EAEA, teaming with SNL, is conducting a Preliminary Safety Assessment (PSA) of an intermediate-depth borehole disposal in thick arid alluvium in Egypt based on experience with the U.S. Greater Confinement Disposal (GCD). Goldsim has been selected for the preliminary disposal system assessment for the Egyptian GCD Study. The results of the PSA will then be used to decide if Egypt desires to implement such a disposal system

  13. Storage of low-level radioactive waste and regulatory control of sealed sources in Finland

    International Nuclear Information System (INIS)

    Rahola, T.; Markkanen, M.

    2006-01-01

    This paper is concentrated on the non nuclear low-level radioactive waste. The cornerstone for maintaining radioactive sources under control in Finland is that all practices involving sources are subject to authorization and all licensing information, including information on each individual source, are entered into a register which is continuously updated based on applications and notifications received from the licenses. Experiences during the past twenty years have shown that source-specific records of sources combined with regular inspections at the places of use have prevented efficiency losing control over sealed radioactive sources. The current capacity in the interim storage for State owned waste is not adequate for all used sealed sources and other small user waste which are currently kept in the possession of the licensees. Thus, expansion of the storage capacity and other options for taking care of the small user waste is under consideration. (N.C.)

  14. Safety Problems of Disposal of Disused Sealed Sources in the Baldone Near Surface Repository

    International Nuclear Information System (INIS)

    Dreimanis, A.

    2003-01-01

    Current Latvian regulations encourage re-export of DSS, however, up to now in the repository has been disposed a lot of DSS. Baldone repository has received RW (mainly DSS) from ∼ 300 Latvia objects and from Kaliningrad region (from 1964 to 1973). DSS cause the major part of activity of the repository - from the total activity in facility ∼ 400 TBq more than 300 TBq is due to DSS. A long term Safety Assessment (SA) of the Baldone Radon-type near surface disposal facility has been performed by the consortium CASSIOPEE and recommendations are given. The waste disposal system consists of: vaults 1-6 (closed, as permanent disposal site), vault 7 (as a long-term retrievable storage site); 2 main components of the engineered barriers: the capping system and the vaults. Vaults 1 and 3-6 (of re-fabricated concrete elements, closed with reinforced concrete slabs, covered with hydro isolating layer completed by a sand/ soil layer). The vault No.7 (ten 130 m 3 underground concrete walled storage cells, protected from the weather by the building. These 10 underground storage cells are adjacent (2x5) with additional concrete walls in some of them. The cells are covered by 40 cm concrete slabs placed side to side. The assessment context and development of scenarios are presented in the paper. The results from the SA are presented. For the waste pathway scenarios - the resulting doses - ∼ 4 mSv/y at 30 y in the current status without cover, justify the implantation of a cover for the closure period of the repository. For air pathway scenarios - the basic dose target 1 mSv/y (for public) is not satisfied for all scenarios; the resulting effective dose for the on-site 'Western' residential scenario for the vaults with highest content of DSS: vault 3 - 303 mSv/y; vault 7 - 204 mSv/y. The main recommendations from the SA are: General Advice - to dispose sources with half-lives < 5,3 y; for the spent sources - to build a new long-term storage; 2. To move DSS from Vault 7 to the

  15. Safety considerations of disposal of disused sealed sources in Puspokszilagy Repository, Hungary

    International Nuclear Information System (INIS)

    2003-01-01

    The report presents the management of radioactive waste in Hungary Puspokszilagy Repository (RWTDF) including waste acceptance criteria, safety assessments, Action Plan for the safety improvement and present projects. The Puspokszilagy Repository is a typical near-surface repository, sink into the ground 6 m depth. The facility is a shallow land disposal type, appropriated for disposal of short and medium lived LILW, acceptable for temporary storage of long lived LILW. It consists of vaults containing cells for solidified drummed waste, wells for spent sealed sources, work building for treatment and interim storage and office building for environmental measurements. Two safety assessments have been performed in 2000 and 2002. The new safety assessment confirms the main statements of SA 2000, according to which several waste types can cause serious problems in the distant future: Until the finish of passive control the safety of the environment is guaranteed. After that time it is possible to arise events leading to exceeding of dose restricts (more then 10 mSv/yr but less then 100 mSv/yr), because of disposal of long lived radionuclides (mainly C-14,Tc-99, Ra-226, Th-232, U-234) and significant activities of Cs-137 sources.There are uncertainties in radionuclide amounts and distributions, as well as in the physical and chemical characteristics of the wastes that determine radionuclide mobility and toxicity. The recommendations to improve the safety include: Long lived SSRS in the 'B' and 'D' wells should be removed before the closure of repository. Large Cs-137 sources and long lived sources in the 'A' vaults should be recovered (if its feasible); All vaults should be backfilled to provide chemical conditioning; The waste packaged in plastic bags should be repackaged and compacted into drums or containers; The inventory should be revise. Waste acceptance requirements in the future are: The disposal of long lived radionuclides is no permitted. The long lived waste

  16. Industrial applications of radiotracer and sealed source technology promoted by IAEA

    International Nuclear Information System (INIS)

    Joon-Ha Jin; Thereska, J.

    2004-01-01

    Great technical and economical benefits can be obtained by applying radioisotope technologies to various industries. The International Atomic Energy Agency (IAEA) has contributed to the development of radiotracer and sealed source technology as applied to industry and environment through coordinated research projects (CRPs). The mature and competitive techniques have been transferred and implemented to developing countries through the Agency's technical co-operation (TC) projects. The paper presents the main achievements in radiotracer and sealed source technology promoted by IAEA as well as the perspective of the technology transfer to developing countries. (author)

  17. Disposal of disused sealed sources and approach for safety assessment of near surface disposal facilities (national practice of Ukraine)

    International Nuclear Information System (INIS)

    Alekseeva, Z.; Letuchy, A.; Tkachenko, N.V.

    2003-01-01

    The main sources of wastes are 13 units of nuclear power plants under operation at 4 NPP sites (operational wastes and spent sealed sources), uranium-mining industry, area of Chernobyl exclusion zone contaminated as a result of ChNPP accident, and over 8000 small users of sources of ionising radiation in different fields of scientific, medical and industrial applications. The management of spent sources is carried out basing on the technology from the early sixties. In accordance with this scheme accepted sources are disposed of either in the near surface concrete vaults or in borehole facilities of typical design. Radioisotope devices and gamma units are placed into near surface vaults and sealed sources in capsules into borehole repositories respectively. Isotope content of radwaste in the repositories is multifarious including Co-60, Cs-137, Sr-90, Ir-192, Tl-204, Po-210, Ra-226, Pu-239, Am-241, H-3, Cf-252. A new programme for waste management has been adopted. It envisions the modifying of the 'Radon' facilities for long-term storage safety assessment and relocation of respective types of waste in 'Vector' repositories.Vector Complex will be built in the site which is located within the exclusion zone 10Km SW of the Chernobyl NPP. In Vector Complex two types of disposal facilities are designed to be in operation: 1) Near surface repositories for short lived LLRW and ILRW disposal in reinforced concrete containers. Repositories will be provided with multi layer waterproofing barriers - concrete slab on layer composed of mixture of sand and clay. Every layer of radwaste is supposed to be filled with 1cm clay layer following disposal; 2) Repositories for disposal of bulky radioactive waste without cans into concrete vaults. Approaches to safety assessment are discussed. Safety criteria for waste disposal in near surface repositories are established in Radiation Protection Standards (NRBU-97) and Addendum 'Radiation protection against sources of potential exposure

  18. Quality control of concretes for conditioning of spent radioactive sources; Control de calidad de concretos para acondicionamiento de fuentes radiactivas gastadas

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez N, M.

    2015-07-01

    The spent sealed radioactive sources are considered as a specific type of radioactive wastes and should be properly stored to ensure their integrity and prevent or limit the release of radionuclides in the geosphere. For this, these sources can be put up in concrete matrices. This research presents the evaluation and characterization of five concretes prepared with 4 brands of commercial cements: CPC Extra RS, CPC 30R Impercem of Cemex, Cruz Azul CPC 30R and CPC 30R of Apasco; three sizes of coarse aggregate (<30 mm, 29-11 mm and <10 mm) and fine aggregate (0.0797 mm) used as matrices for conditioning of spent sealed radioactive sources, in order to verify if these specific concretes accredit the standard NOM-019-Nucl-1995. After hardening for 28 days the concrete specimens were subjected to the tests: compressive strength; thermal cycles, irradiation, leaching and permeability, later to be characterized by: 1) X-ray diffraction in order to meet their crystalline phases; 2) scanning electron microscopy, to determine changes in morphology; 3) infrared spectroscopy, to determine the structural changes of concrete from its functional groups; 4) Raman spectroscopy to determine their structural changes and 5) Moessbauer spectroscopy, which determines changes in the oxidation state of iron in the concrete. According to the results and the changes presented by each concrete after applying the tests set by NOM-019-Nucl-1995, is concluded that the concrete made with cement Cemex brand (CPC 30-RS Extra), gravel of particle size 11-29 mm and sieved sand (0.0797 mm) can be used as matrices of spent sealed sources conditioning. Is remarkable a morphological and structural change of the concrete due to gamma irradiation and heat treatment. (Author)

  19. Mechanical seals

    CERN Document Server

    Mayer, E

    1977-01-01

    Mechanical Seals, Third Edition is a source of practical information on the design and use of mechanical seals. Topics range from design fundamentals and test rigs to leakage, wear, friction and power, reliability, and special designs. This text is comprised of nine chapters; the first of which gives a general overview of seals, including various types of seals and their applications. Attention then turns to the fundamentals of seal design, with emphasis on six requirements that must be considered: sealing effectiveness, length of life, reliability, power consumption, space requirements, and c

  20. Radiation protection problems with sealed Pu radiation sources

    International Nuclear Information System (INIS)

    Naumann, M.; Wels, C.

    1982-01-01

    A brief outline of the production methods and most important properties of Pu-238 and Pu-239 is given, followed by an overview of possibilities for utilizing the different types of radiation emitted, a description of problems involved in the safe handling of Pu radiation sources, and an assessment of the design principles for Pu-containing alpha, photon, neutron and energy sources from the radiation protection point of view. (author)

  1. Spent coffee grounds as a versatile source of green energy.

    Science.gov (United States)

    Kondamudi, Narasimharao; Mohapatra, Susanta K; Misra, Mano

    2008-12-24

    The production of energy from renewable and waste materials is an attractive alternative to the conventional agricultural feed stocks such as corn and soybean. This paper describes an approach to extract oil from spent coffee grounds and to further transesterify the processed oil to convert it into biodiesel. This process yields 10-15% oil depending on the coffee species (Arabica or Robusta). The biodiesel derived from the coffee grounds (100% conversion of oil to biodiesel) was found to be stable for more than 1 month under ambient conditions. It is projected that 340 million gallons of biodiesel can be produced from the waste coffee grounds around the world. The coffee grounds after oil extraction are ideal materials for garden fertilizer, feedstock for ethanol, and as fuel pellets.

  2. FRG sealed isotopic heat sources project (C-229) project management plan

    International Nuclear Information System (INIS)

    Metcalf, I.L.

    1997-01-01

    This Project Management Plan defines the cost, scope, schedule, organizational responsibilities, and work breakdown structure for the removal of the Federal Republic of Germany (FRG) Sealed Isotopic Heat Sources from the 324 Building and placed in interim storage at the Central Waste Complex (CWC)

  3. 10 CFR 34.67 - Records of leak testing of sealed sources and devices containing depleted uranium.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Records of leak testing of sealed sources and devices containing depleted uranium. 34.67 Section 34.67 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL... Requirements § 34.67 Records of leak testing of sealed sources and devices containing depleted uranium. Each...

  4. Factors affecting the repeatability of gamma camera calibration for quantitative imaging applications using a sealed source

    International Nuclear Information System (INIS)

    Anizan, N; Wahl, R L; Frey, E C; Wang, H; Zhou, X C

    2015-01-01

    Several applications in nuclear medicine require absolute activity quantification of single photon emission computed tomography images. Obtaining a repeatable calibration factor that converts voxel values to activity units is essential for these applications. Because source preparation and measurement of the source activity using a radionuclide activity meter are potential sources of variability, this work investigated instrumentation and acquisition factors affecting repeatability using planar acquisition of sealed sources. The calibration factor was calculated for different acquisition and geometry conditions to evaluate the effect of the source size, lateral position of the source in the camera field-of-view (FOV), source-to-camera distance (SCD), and variability over time using sealed Ba-133 sources. A small region of interest (ROI) based on the source dimensions and collimator resolution was investigated to decrease the background effect. A statistical analysis with a mixed-effects model was used to evaluate quantitatively the effect of each variable on the global calibration factor variability. A variation of 1 cm in the measurement of the SCD from the assumed distance of 17 cm led to a variation of 1–2% in the calibration factor measurement using a small disc source (0.4 cm diameter) and less than 1% with a larger rod source (2.9 cm diameter). The lateral position of the source in the FOV and the variability over time had small impacts on calibration factor variability. The residual error component was well estimated by Poisson noise. Repeatability of better than 1% in a calibration factor measurement using a planar acquisition of a sealed source can be reasonably achieved. The best reproducibility was obtained with the largest source with a count rate much higher than the average background in the ROI, and when the SCD was positioned within 5 mm of the desired position. In this case, calibration source variability was limited by the quantum

  5. Comparison of General Purpose Heat Source testing with the ANSI N43.6-1977 (R 1989) sealed source standard

    International Nuclear Information System (INIS)

    Grigsby, C.O.

    1998-01-01

    This analysis provides a comparison of the testing of Radioisotope Thermoelectric Generators (RTGs) and RTG components with the testing requirements of ANSI N43.6-1977 (R1989) ''Sealed Radioactive Sources, Categorization''. The purpose of this comparison is to demonstrate that the RTGs meet or exceed the requirements of the ANSI standard, and thus can be excluded from the radioactive inventory of the Chemistry and Metallurgy Research (CMR) building in Los Alamos per Attachment 1 of DOE STD 1027-92. The approach used in this analysis is as follows: (1) describe the ANSI sealed source classification methodology; (2) develop sealed source performance requirements for the RTG and/or RTG components based on criteria from the accident analysis for CMR; (3) compare the existing RTG or RTG component test data to the CMR requirements; and (4) determine the appropriate ANSI classification for the RTG and/or RTG components based on CMR performance requirements. The CMR requirements for treating RTGs as sealed sources are derived from the radiotoxicity of the isotope ( 238 P7) and amount (13 kg) of radioactive material contained in the RTG. The accident analysis for the CMR BIO identifies the bounding accidents as wing-wide fire, explosion and earthquake. These accident scenarios set the requirements for RTGs or RTG components stored within the CMR

  6. UHV seal studies for the advanced photon source storage ring vacuum system

    International Nuclear Information System (INIS)

    Gonczy, J.D.; Ferry, R.J.; Niemann, R.C.; Roop, B.

    1991-01-01

    The Advanced Photon Source (APS) Storage Ring Vacuum Chambers (SRVC) are constructed of aluminum. The chamber design incorporates aluminum alloy 2219-T87 Conflat flanges welded to an aluminum alloy 6063-T5 extruded chamber body. Vacuum connections to the aluminum Conflat chamber flanges are by means of 304 stainless steel Conflat flanges. To evaluate the Conflat seal assemblies relative to vacuum bake cycles, a Conflat Bake Test Assembly (CBTA) was constructed, and thermal cycling tests were performed between room temperature and 150 degrees C on both stainless steel to aluminum Conflat assemblies and aluminum to aluminum Conflat assemblies. A Helicoflex Bake Test Assembly (HBTA) was similarly constructed to evaluate Helicoflex seals. Both Conflat and Helicoflex seals were studied in a SRVC Sector String Test arrangement of five SRVC sections. The CBTA, HBTA and SRVC tests and their results are reported. 3 refs., 2 figs., 2 tabs

  7. Sealed radioactive sources and method of their production

    International Nuclear Information System (INIS)

    Benadik, A.; Tympl, M.; Stopek, K.

    1985-01-01

    The active layer of the proposed sources consists of an inorganic sorbent activated with a radioactive component in form of gel, xerogel or glass. The active particles of the inorganic sorbent have the shape of spheres 2 to 2000 μm in diameter. The sources have a tubular, cylindrical or needle shape and are compact with low leachability. They feature minimal radionuclide leakage, they are reliable and safe. Their production technology is proposed. The inorganic sorbent is put in contact with the sollution of the radioactive compound, then separated from the liquid phase, filled into containers, dried, calcined or sintered or otherwise heat-processed into glass at temperatures of 250 -1800 degC. (M.D.)

  8. Seal performance of thermal aged metal gasket of dual purpose metal cask for interim spent fuel storage after external impact load

    International Nuclear Information System (INIS)

    Takeshi Yokoyama; Masami Kato; Satoshi Itooka

    2005-01-01

    As for interim storage for spent nuclear fuels using dual purpose dry metal cask in Japan, we recognize one of the important technical issues that there is a possibility for the cask with degraded metal gasket during storage to apply to transportation. In our study until 2003 focused on degradation of important components for the cask safety performance during storage and application to transportation, for metal gasket, we conducted property tests for degradation and influence of lid movement on seal performance, and furthermore verification tests. From the results, we developed the method to evaluate leak rate from lid with degraded metal gasket at accidents during transportation and in addition, we found as follows: Lid would hardly move and leak rate would not increase seriously during fire event. Leak rate from lid with degraded metal gasket could be evaluated by using results of leak rate trend depending on horizontal displacement of lid by external impact load. So, with regard to influence of lid movement on seal performance, we conducted additional test for extending horizontal displacement in lid moving in 2004. In addition, seal performance was discussed from the results, both previous and latest test. (authors)

  9. Applications of sealed sources in chemical engineering. I

    International Nuclear Information System (INIS)

    Thyn, J.; Pokorny, J.; Cabrnoch, J.

    1977-01-01

    The vertical and horizontal distribution of the concentration of milling balls was observed radiometrically ( 241 Am) on a model (1:4) of the vertical mill of the MOLINEX type. The basic relations are derived for the calculation of the distribution of the density of solid particles and relations for the estimation of errors in measurement. A description is given of the model equipment, of the configuration of the radiation source, of the detector and of the experimental conditions. The results are discussed of measurements for three configurations on the shaft of the excentrically mounted mixing discs (4, 6 and 9 pieces) at 10 rev.s -1 for one revolution direction. The effect of the number of revolutions and of the revolution direction was observed for 6 mixing elements. (B.S.)

  10. Structural and Shielding Safety of a Transport Package for Radioisotope Sealed Source Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Kiseog; Cho, Ilje; Kim, Donghak [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    As some kinds of radioisotope (RI) sealed source are produced by HANARO research reactor, a demand of RI transport package is increasing gradually. Foreign countries, which produce the various RIs, have the intrinsic model of the RI transport package. It is necessary to develop a RI and its transport package simultaneously. It is difficult to design a shielding part for this transport package because the passage for this source assembly should be provided from the center of shielding part to the outside of the package. In order to endure the accident conditions such as a 9 m drop and puncture, this transport package consists of the guide tubes, a gamma shield and a shock absorber. This paper describe that a shielding and structural safety of RI sealed source transport package are evaluated under the accident conditions.

  11. Structural and Shielding Safety of a Transport Package for Radioisotope Sealed Source Assembly

    International Nuclear Information System (INIS)

    Seo, Kiseog; Cho, Ilje; Kim, Donghak

    2006-01-01

    As some kinds of radioisotope (RI) sealed source are produced by HANARO research reactor, a demand of RI transport package is increasing gradually. Foreign countries, which produce the various RIs, have the intrinsic model of the RI transport package. It is necessary to develop a RI and its transport package simultaneously. It is difficult to design a shielding part for this transport package because the passage for this source assembly should be provided from the center of shielding part to the outside of the package. In order to endure the accident conditions such as a 9 m drop and puncture, this transport package consists of the guide tubes, a gamma shield and a shock absorber. This paper describe that a shielding and structural safety of RI sealed source transport package are evaluated under the accident conditions

  12. Code of practice for the use of sealed radioactive sources in borehole logging (1998)

    International Nuclear Information System (INIS)

    1989-12-01

    The purpose of this code is to establish working practices, procedures and protective measures which will aid in keeping doses, arising from the use of borehole logging equipment containing sealed radioactive sources, to as low as reasonably achievable and to ensure that the dose-equivalent limits specified in the National Health and Medical Research Council s radiation protection standards, are not exceeded. This code applies to all situations and practices where a sealed radioactive source or sources are used through wireline logging for investigating the physical properties of the geological sequence, or any fluids contained in the geological sequence, or the properties of the borehole itself, whether casing, mudcake or borehole fluids. The radiation protection standards specify dose-equivalent limits for two categories: radiation workers and members of the public. 3 refs., tabs., ills

  13. Lesson Learned from Conditioning of Disused Sealed Radioactive Sources (DSRS) in Malaysia

    International Nuclear Information System (INIS)

    Nik Marzukee Nik Ibrahim; Mohd Abdul Wahab Yusof; Norasalwa Zakaria

    2016-01-01

    This paper presents the conditioning of disused sealed radioactive source (DSRS) in Malaysia. In Malaysia, sealed radioactive sources (SRS) are widely used in Malaysia especially in industry, medicine and research. Once SRS are no longer in use, they are declared disused and managed as radioactive waste. In order to reduce the risk associated with disused sealed radioactive sources (DSRS), the first priority would be to bring them under appropriate controls. This paper describes the experience developed and activities performed by Nuclear Malaysia throughout the period in conditioning of DSRS as well as future programme to further enhancing the infrastructure. Collaborative efforts with the various relevant groups such as Loji and Prototaip Development Centre (PDC) and Industrial Technology Division (BTI) provide an effective avenue in ensuring successful implementation of the programme. Currently, until August 2015, Malaysia has in possession about 12,154 unit of DSRS categories 3-5 and 4 units of DSRS category 2 sources which being stored at the interim storage facility Nuclear Malaysia. A national activity was implemented for the on-the-job training of personnel tasked with the conditioning of DSRS, at the Waste Technology Development Centre (WasTeC) facilities. This is part of -cradle-to-grave- control of radioactive sources to protect the workers and public from the hazards of ionizing radiation. (author)

  14. A study on the safety of spent fuel management. Radioactive source term modelling

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Kwan Sik; Lee, Hoo Keun; Park, Keun Il; Hwoang, Jung Ki; Chung, Choong Hwan [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

    1992-02-01

    The types and probabilities of events which may occur during the process of reception, transfer and storage of spent fuels in an away-from-reactor (AFR) spent fuel storage facility were analyzed in order to calculate the amount of radioactive material released to operation area and atmosphere, and the basic model for predicting the radioactive source-term under normal and abnormal operations were developed. Also, oxidation and dissolution of U0{sub 2} pellet was investigated to estimate the amount of radioactive materials released from spent fuel and the release characteristics of radionuclides from defected spent fuel rods was analyzed. Basic information using FIRAC code to analyze the ventilation system during fire accident was prepared and FIRIN was detached from FIRAC modified to simulate the compartment fire by personal computer. (Author).

  15. Development of a sealed source radiation detector system for gamma ray scanning of petroleum distillation columns

    International Nuclear Information System (INIS)

    Vasquez Salvador, Pablo Antonio

    2004-01-01

    Gamma Ray Scanning is an online technique to 'view' the hydraulic performance of an operating column, with no disruption to operating processes conditions (pressure and temperature), as a cost-effective solution. The principle of this methodology consists of a small suitably sealed gamma radiation source and a radiation detector experimentally positioned to the column, moving concurrently in small increments on opposite sides and the quantity of gamma transmitted. The source-detector system consists of: a sealed ''6 0 Co radioactive source in a panoramic lead radiator, a scintillator detector coupled to a ratemeter / analyzer and a mobile system. In this work, a gamma scanning sealed source-detector system for distillation columns, was developed, comparing two scintillator detectors: NaI(Tl) (commercial) and CsI(Tl) (IPEN). In order to project the system, a simulated model of a tray-type distillation column was used. The equipment developed was tested in an industrial column for water treatment (6.5 m diameter and 40 m height). The required activities of 6 ''0Co, laboratory (11.1 MBq) and industrial works (1.48 TBq) were calculated by simulation software. Both, the NaI(Tl) and the CsI(Tl) detectors showed good proprieties for gamma scanning applications, determining the position and presence or absence of trays. (author)

  16. Capabilities of a DT tokamak fusion neutron source for driving a spent nuclear fuel transmutation reactor

    International Nuclear Information System (INIS)

    Stacey, W.M.

    2001-01-01

    The capabilities of a DT fusion neutron source for driving a spent nuclear fuel transmutation reactor are characterized by identifying limits on transmutation rates that would be imposed by tokamak physics and engineering limitations on fusion neutron source performance. The need for spent nuclear fuel transmutation and the need for a neutron source to drive subcritical fission transmutation reactors are reviewed. The likely parameter ranges for tokamak neutron sources that could produce an interesting transmutation rate of 100s to 1000s of kg/FPY (where FPY stands for full power year) are identified (P fus ∼ 10-100 MW, β N ∼ 2-3, Q p ∼ 2-5, R ∼ 3-5 m, I ∼ 6-10 MA). The electrical and thermal power characteristics of transmutation reactors driven by fusion and accelerator spallation neutron sources are compared. The status of fusion development vis-a-vis a neutron source is reviewed. (author)

  17. Recovery of spent high intensity neutron sources in Atalante Facility

    International Nuclear Information System (INIS)

    Bros, P.; Boyer Deslys, V.; Millet, A.; Solinhac, I.; Donnet, L.; Maillard, C.; Paillard, S.; Ranchoux, M.

    2005-01-01

    The Atalante facility is required by law to recover both neutron and gamma sources with activity levels exceeding 300 mCi. Most of the neutron sources consist of mixtures of alpha-emitters (238Pu, 239Pu, 241Am or 244Cm) and beryllium. Several processes now under consideration are based on routine chemical separation techniques (selective precipitation, extraction chromatography, ion exchange). The treatment produces an actinide oxide (which is used later for R and D studies) and solid beryllium nitrate, which is considered as a waste and transferred to a surface interim storage site if the overall activity of the package after 300 years is less than 50 MBq (ANDRA specifications). The Material Analysis and Metrology Laboratory of Atalante validate the residual alpha activity in the waste. The techniques used include alpha spectrometry and L-line X-ray fluorescence for alpha emitters, and plasma torch measurements (ICP-AES and ICP-MS) for beryllium analysis. Specific equipment for transport (B type cask), storage and treatment (hot shielded cells) are used for this activity. (Author)

  18. Standard review plan for applications for sealed source and device evaluations and registrations

    International Nuclear Information System (INIS)

    1996-11-01

    The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission's policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required

  19. Standard review plan for applications for sealed source and device evaluations and registrations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission`s policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission`s regulations and compliance with them is not required.

  20. Identification of radioisotopes in bulks with disused sealed sources using a high performance portable spectrometer

    International Nuclear Information System (INIS)

    Zapata, Luis; Mallaupoma, Mario

    2013-01-01

    Sealed radioactive sources are widely used in many industrial applications, and after completing its useful life must be managed as radioactive wastes. One of the most common problems of disused sealed radioactive sources is that many times they lack proper identification and their certificates of manufacture. In that context, it is necessary to identify them, prior to any other management step. There are a number of techniques which can be used; however they are sometimes complex. This technical paper shows a simple way for its identification using the InSpector 1000 monitor which allows to know their energy spectra. These modern instruments and detectors have been obtained thanks to the Project Global Threat Reduction Initiative (Programa de Reduccion de Amenazas) between IPEN and the US DOE. (authors).

  1. Development of sealed sheet sources for calibration of whole-body counters

    International Nuclear Information System (INIS)

    Miyamoto, Mai; Ishigure, Nobuhito; Ogata, Yoshimune; Narita, Norihiko; Kawaura, Chiyo; Nakano, Takashi

    2009-01-01

    Whole body counters are usually calibrated with the aid of a whole body phantom assembled with simply-shaped plastic vessels that are filled with an aqueous solution of the relevant radioisotopes. Most vessel-type phantoms represent only a human body in which radioisotopes are homogeneously distributed, whereas the radioisotopes in vivo are sometimes localized to specific organs. Each set of the vessels is usually applicable only to a specific combination of radioisotopes, because the replacement of radioisotopes requires troublesome procedures. Possible leakage of the solution is another disadvantage of the vessel-type phantom. The authors are developing a new-type calibration phantom that is free from these disadvantages, in which sealed sheet sources are sandwiched between sections of a sliced anthropomorphic phantom. This paper describes a method to prepare sealed sheet sources for this calibration phantom. Instead of γ-ray emitters a pure β-ray emitter 32 P was used. This isotope is suitable for autoradiography and is easy to handle as its half-life is relatively short. An ink-jet printer was used to spread the solution of 32 P mixed with ink on a sheet of paper. The surface concentration of radioactivity was regulated by the function of color density adjustment of an image processing software. The radioisotope-printed paper was laminated for sealing. Through the measurement of surface concentration of radioactivity with a liquid scintillation counter, the autoradiographical investigation of the pattern of the radioactivity distributed on the sheet sources, the immersion test of the sealed sheet sources and the monitoring of the concentration of 32 P in air during the printing, it was demonstrated that sealed sheet sources for the calibration phantom can be prepared safely by the method described in this paper. Furthermore, by using sheet sources of 99m Tc prepared as a trial it was confirmed that discrete arrangement of sheet sources in a phantom at a

  2. Systematic management of sealed source and nucleonic counting system in field service

    International Nuclear Information System (INIS)

    Mahadi Mustapha; Mohd Fitri Abdul Rahman; Jaafar Abdullah

    2005-01-01

    PAT group have received a lot of service from the oil and gas plant. All the services use sealed source and nucleonic counting system. This paper described the detail of management before going to the field service. This management is important to make sure the job is smoothly done and safe to the radiation worker and public. Furthermore this management in line with the regulation from LPTA. (Author)

  3. Collaboration and Commitment to Sealed Source Safety, Security, and Disposition - 13627

    International Nuclear Information System (INIS)

    Jennison, Meaghan; Martin, David W.

    2013-01-01

    EnergySolutions, the Division of Radiation Control at the Utah Department of Environmental Quality (UDEQ), the Conference of Radiation Control Program Directors (CRCPD), and the Department of Energy's Global Threat Reduction Initiative (GTRI) are collaborating on a truly innovative effort to expand opportunities for cost-effective sealed source disposal. These entities have developed a first-of-its-kind initiative to dispose of certain sealed sources at the EnergySolutions disposal facility near Clive, Utah, which normally cannot accept sealed sources of any type. This creative and collaborative effort to improve radiation health, safety, and security exemplifies the spirit and commitment represented by the Richard S. Hodes, M.D. Honor Lecture Award, which is presented annually at the Waste Management Symposia by the Southeast Compact Commission to encourage environmental professionals and political leaders to develop innovative approaches to waste management in the United States. The participants in the collaborative initiative are honored to receive special recognition for their efforts thus far. They also recognize that the hard work remains to be done. (authors)

  4. Strategic planning as a competitive differential: A case study of the Sealed Sources Production Laboratory

    International Nuclear Information System (INIS)

    Vieira, Imário; Nascimento, Fernando C.; Calvo, Wilson A. Parejo

    2017-01-01

    Strategic planning has always been and continues to be one of the most important management tools for decision making. Amidst the uncertainties of the 21"s"t century, public, private and third sector organizations are steadily struggling to improve their strategic plans by using more effective results management tools such as BSC-Balanced Scorecard. Nuclear research institutes and research centers around the world have been using more and more these types of tools in their strategic planning and management. The objective of this article was to recommend the use the BSC as a strategic tool for decision making for the Sealed Sources Production Laboratory located in the Radiation Technology Center, at Nuclear and Energy Research Institute (IPEN/CNEN-SP), in Sao Paulo, Brazil. The methodology used in this academic article was a case study, which considered the object of the study, the Sealed Sources Production Laboratory, from January 2014 to August 2016. Among the main results obtained with this study can be cited: the improvement of the information flow, the visualization and proposition to change the periodicity of analysis of the results, among others. In view of the expected results, it was possible to conclude that this study may be of value to the Sealed Sources Production Laboratory for Industrial Radiography and Industrial Process Control and also to other research centers, as it will allow and contribute with an additional management support tool. (author)

  5. Strategic planning as a competitive differential: A case study of the Sealed Sources Production Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, Imário; Nascimento, Fernando C.; Calvo, Wilson A. Parejo, E-mail: imariovieira@yahoo.com, E-mail: wapcalvo@ipen.br, E-mail: fcodelo@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Faculdade SENAI de Tecnologia Ambiental, Sao Bernardo do Campo, SP (Brazil)

    2017-11-01

    Strategic planning has always been and continues to be one of the most important management tools for decision making. Amidst the uncertainties of the 21{sup st} century, public, private and third sector organizations are steadily struggling to improve their strategic plans by using more effective results management tools such as BSC-Balanced Scorecard. Nuclear research institutes and research centers around the world have been using more and more these types of tools in their strategic planning and management. The objective of this article was to recommend the use the BSC as a strategic tool for decision making for the Sealed Sources Production Laboratory located in the Radiation Technology Center, at Nuclear and Energy Research Institute (IPEN/CNEN-SP), in Sao Paulo, Brazil. The methodology used in this academic article was a case study, which considered the object of the study, the Sealed Sources Production Laboratory, from January 2014 to August 2016. Among the main results obtained with this study can be cited: the improvement of the information flow, the visualization and proposition to change the periodicity of analysis of the results, among others. In view of the expected results, it was possible to conclude that this study may be of value to the Sealed Sources Production Laboratory for Industrial Radiography and Industrial Process Control and also to other research centers, as it will allow and contribute with an additional management support tool. (author)

  6. Validating criticality calculations for spent fuel with 252Cf-source-driven noise measurements

    International Nuclear Information System (INIS)

    Mihalczo, J.T.; Krass, A.W.; Valentine, T.E.

    1992-01-01

    The 252 Cf-Source-driven noise analysis method can be used for measuring the subcritical neutron multiplication factor k of arrays of spent light water reactor (LWR) fuel. This type of measurement provides a parameter that is directly related to the criticality state of arrays of LWR fuel. Measurements of this parameter can verify the criticality safety margins of spent LWR fuel configurations and thus could be a means of obtaining the information to justify burnup credit for spent LWR transportation/storage casks. The practicality of a measurement depends on the ability to install the hardware required to perform the measurement. Source chambers containing the 252 Cf at the required source intensity for this application have been constructed and have operated successfully for ∼10 years and can be fabricated to fit into control rod guide tubes of PWR fuel elements. Fission counters especially developed for spent-fuel measurements are available that would allow measurements of a special 3 x 3 spent fuel array and a typical burnup credit rail cask with spent fuel in unborated water. Adding a moderator around these fission counters would allow measurements with the typical burnup credit rail cask with borated water and the special 3 x 3 array with borated water. The recent work of Ficaro on modifying the KENO Va code to calculate by the Monte Carlo method the time sequences of pulses at two detectors near a fissile assembly from the fission chain multiplication process, initiated by a 252 Cf source in the assembly allows a direct computer calculation of the noise analysis data from this measurement method

  7. Soil Monitor: an open source web application for real-time soil sealing monitoring and assessment

    Science.gov (United States)

    Langella, Giuliano; Basile, Angelo; Giannecchini, Simone; Iamarino, Michela; Munafò, Michele; Terribile, Fabio

    2016-04-01

    Soil sealing is one of the most important causes of land degradation and desertification. In Europe, soil covered by impermeable materials has increased by about 80% from the Second World War till nowadays, while population has only grown by one third. There is an increasing concern at the high political levels about the need to attenuate imperviousness itself and its effects on soil functions. European Commission promulgated a roadmap (COM(2011) 571) by which the net land take would be zero by 2050. Furthermore, European Commission also published a report in 2011 providing best practices and guidelines for limiting soil sealing and imperviousness. In this scenario, we developed an open source and an open source based Soil Sealing Geospatial Cyber Infrastructure (SS-GCI) named as "Soil Monitor". This tool merges a webGIS with parallel geospatial computation in a fast and dynamic fashion in order to provide real-time assessments of soil sealing at high spatial resolution (20 meters and below) over the whole Italy. Common open source webGIS packages are used to implement both the data management and visualization infrastructures, such as GeoServer and MapStore. The high-speed geospatial computation is ensured by a GPU parallelism using the CUDA (Computing Unified Device Architecture) framework by NVIDIA®. This kind of parallelism required the writing - from scratch - all codes needed to fulfil the geospatial computation built behind the soil sealing toolbox. The combination of GPU computing with webGIS infrastructures is relatively novel and required particular attention at the Java-CUDA programming interface. As a result, Soil Monitor is smart because it can perform very high time-consuming calculations (querying for instance an Italian administrative region as area of interest) in less than one minute. The web application is embedded in a web browser and nothing must be installed before using it. Potentially everybody can use it, but the main targets are the

  8. Radioactive air emissions notice of construction for Canister Storage Building (revised sealing configuration for spent nuclear fuel) - Project W-379

    International Nuclear Information System (INIS)

    Kamberg, L.D.

    1998-01-01

    The purpose of this Notice of Construction (NOC) is to provide a rewritten NOC for obtaining regulatory approval for changes to the previous Canister Storage Building (CSB) NOCs (WDOH, 1996 and EPA, 1996) as were approved by the Washington State Department of Health (WDOH, 1996a) and US Environmental Protection Agency (EPA, 1996a). These changes are because of a revised sealing configuration of the multi-canister overpacks (MCOS) that are used to store the SNF. A flow schematic of the SNF Project is provided in Figure 1-1. A separate notification of startup will be provided apart from this NOC

  9. Assessment of ventilation system for centralized storage of spent radiation sources

    International Nuclear Information System (INIS)

    Soroka, Yu.N.; Udod, E.V.

    2014-01-01

    The hazards associated with treatment spent radiation sources in the centralized storage facility under construction in the Chernobyl exclusion zone are analysis. Models are proposed to calculate possible situations of contamination with radionuclides in centralized storage rooms. The required ventilation rate is calculated for areas where sources containing 60 Co; 90 Sr, 137 Cs, 226 Ra, 238 Pu, 239 Pu and 241 Am radionuclides are supposed to be treated

  10. Radioactivity determination of sealed pure beta-sources by surface dose measurements and Monte Carlo simulations

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang Heon [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Jung, Seongmoon [Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Choi, Kanghyuk; Son, Kwang-Jae; Lee, Jun Sig [Hanaro Applications Research, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ye, Sung-Joon, E-mail: sye@snu.ac.kr [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Center for Convergence Research on Robotics, Advance Institutes of Convergence Technology, Seoul National University, Suwon (Korea, Republic of)

    2016-04-21

    This study aims to determine the activity of a sealed pure beta-source by measuring the surface dose rate using an extrapolation chamber. A conversion factor (cGy s{sup −1} Bq{sup −1}), which was defined as the ratio of surface dose rate to activity, can be calculated by Monte Carlo simulations of the extrapolation chamber measurement. To validate this hypothesis the certified activities of two standard pure beta-sources of Sr/Y-90 and Si/P-32 were compared with those determined by this method. In addition, a sealed test source of Sr/Y-90 was manufactured by the HANARO reactor group of KAERI (Korea Atomic Energy Research Institute) and used to further validate this method. The measured surface dose rates of the Sr/Y-90 and Si/P-32 standard sources were 4.615×10{sup −5} cGy s{sup −1} and 2.259×10{sup −5} cGy s{sup −1}, respectively. The calculated conversion factors of the two sources were 1.213×10{sup −8} cGy s{sup −1} Bq{sup −1} and 1.071×10{sup −8} cGy s{sup −1} Bq{sup −1}, respectively. Therefore, the activity of the standard Sr/Y-90 source was determined to be 3.995 kBq, which was 2.0% less than the certified value (4.077 kBq). For Si/P-32 the determined activity was 2.102 kBq, which was 6.6% larger than the certified activity (1.971 kBq). The activity of the Sr/Y-90 test source was determined to be 4.166 kBq, while the apparent activity reported by KAERI was 5.803 kBq. This large difference might be due to evaporation and diffusion of the source liquid during preparation and uncertainty in the amount of weighed aliquot of source liquid. The overall uncertainty involved in this method was determined to be 7.3%. We demonstrated that the activity of a sealed pure beta-source could be conveniently determined by complementary combination of measuring the surface dose rate and Monte Carlo simulations.

  11. Safe management of sealed radioactive sources at Karachi nuclear power complex

    International Nuclear Information System (INIS)

    Tahir, T.B.; Qamar, A.

    2000-01-01

    This paper describes the conditioning of sealed radioactive sources, carried out at the Karachi Nuclear Power Complex (KNPC) in co-operation with the IAEA. The radioactive sources were radium needles of various size, used by various radiotherapy units in different hospitals throughout the country. For some time the use of radium needles had been abandoned and they were stored in hospitals awaiting proper disposal. Since their storage conditions were not ideal and there was a potential of leakage of radioactive material into the environment, it was decided to condition and store them safely. A significant logistic effort was required to identify these sources, bring them to a central facility and condition them according to current international standards. Various steps were involved in conditioning the sources: place it in a stainless steel capsule, weld the capsule, test it for a leak, place the capsule in a lead shielded package, put and seal the shielded package in a concrete-lined steel drum and finally store it at the waste storage facility. A total amount of about 1500 mg of Radium needles were conditioned. Radiation exposure during the entire operation was within acceptable limits. (author)

  12. Techniques for long term conditioning and storage of radium sources

    International Nuclear Information System (INIS)

    Dogaru, Gheorghe; Dragolici, Felicia; Nicu, Mihaela

    2008-01-01

    The Horia Hulubei National Institute of Research and Development for Physics and Nuclear Engineering developed its own technology for conditioning the radium spent sealed radioactive sources. The laboratory dedicated to radiological characterization, identification of radium sources as well as the encapsulation of spent sealed radioactive sources was equipped with a local ventilation system, welding devices, tightness test devices as well as radiometric portable devices. Two types of capsules have been designed for conditioning of radium spent sealed radioactive sources. For these kinds of capsules different types of storage packaging were developed. Data on the radium inventory will be presented in the paper. The paper contains the description of the process of conditioning of spent sealed radioactive sources as well as the description of the capsules and packaging. The paper describes the equipment used for the conditioning of the radium spent sealed sources. (authors)

  13. Projected Source Terms for Potential Sabotage Events Related to Spent Fuel Shipments

    International Nuclear Information System (INIS)

    Luna, R.E.; Neuhauser, K.S.; Vigil, M.G.

    1999-01-01

    Two major studies, one sponsored by the U.S. Department of Energy and the other by the U.S. Nuclear Regulatory Commission, were conducted in the late 1970s and early 1980s to provide information and source terms for an optimally successful act of sabotage on spent fuel casks typical of those available for use. This report applies the results of those studies and additional analysis to derive potential source terms for certain classes of sabotage events on spent fuel casks and spent fuel typical of those which could be shipped in the early decades of the 21st century. In addition to updating the cask and spent fuel characteristics used in the analysis, two release mechanisms not included in the earlier works were identified and evaluated. As would be expected, inclusion of these additional release mechanisms resulted in a somewhat higher total release from the postulated sabotage events. Although health effects from estimated releases were addressed in the earlier study conducted for U.S. Department of Energy, they have not been addressed in this report. The results from this report maybe used to estimate health effects

  14. Current approaches on the management of disused sealed sources in Bulgaria

    International Nuclear Information System (INIS)

    Benitez-Navarro, J. C.; Canizares, J.; Asuar, O.; Tapia, J.; Demireva, E.; Yordanova, O.; Stefanova, I.; Karadzhov, S.

    2005-01-01

    The main options for the safe management of existing Disused Sealed Radioactive Sources (DSRS) in Bulgaria are discussed. The specific installations for handling and conditioning of all type of DSRS are being designed. The necessary equipment and materials for all conditioning operations have been defined. As the final disposal route for the radioactive wastes in Bulgaria is not defined yet, the proposed conditioning process for the DSRS ensures that end-point disposal of DSRS is not jeopardized by actions taken at present. All the DSRS would be packaged in secure, safe, monitorable and retrievable manner for interim storage

  15. Global threat reduction initiative efforts to address transportation challenges associated with the recovery of disused radioactive sealed sources - 10460

    International Nuclear Information System (INIS)

    Whitworth, Julie; Abeyta, Cristy L.; Griffin, Justin M.; Matzke, James L.; Pearson, Michael W.; Cuthbertson, Abigail; Rawl, Richard; Singley, Paul

    2010-01-01

    Proper disposition of disused radioactive sources is essential for their safe and secure management and necessary to preclude their use in malicious activities. Without affordable, timely transportation options, disused sealed sources remain in storage at hundreds of sites throughout the country and around the world. While secure storage is a temporary measure, the longer sources remain disused or unwanted the chances increase that they will become unsecured or abandoned. The Global Threat Reduction Initiative's Off-Site Source Recovery Project (GTRIlOSRP), recovers thousands of disused and unwanted sealed sources annually as part of GTRl's larger mission to reduce and protect high risk nuclear and radiological materials located at civilian sites worldwide. Faced with decreasing availability of certified transportation containers to support movement of disused and unwanted neutron- and beta/gamma-emitting radioactive sealed sources, GTRIlOSRP has initiated actions to ensure the continued success of the project in timely recovery and management of sealed radioactive sources. Efforts described in this paper to enhance transportation capabilities include: (sm b ullet) Addition of authorized content to existing and planned Type B containers to support the movement of non-special form and other Type B-quantity sealed sources; (sm b ullet) Procurement of vendor services for the design, development, testing and certification of a new Type B container to support transportation of irradiators, teletherapy heads or sources removed from these devices using remote handling capabilities such as the IAEA portable hot cell facility; (sm b ullet) Expansion of shielded Type A container inventory for transportation of gamma-emitting sources in activity ranges requiring use of shielding for conformity with transportation requirements; (sm b ullet) Approval of the S300 Type A fissile container for transport of Pu-239 sealed sources internationally; (sm b ullet) Technology transfer of

  16. Nuclear Forensics Attributing the Source of Spent Fuel Used in an RDD Event

    International Nuclear Information System (INIS)

    Scott, M.R.

    2005-01-01

    An RDD attack against the U.S. is something America needs to prepare against. If such an event occurs the ability to quickly identify the source of the radiological material used in an RDD would aid investigators in identifying the perpetrators. Spent fuel is one of the most dangerous possible radiological sources for an RDD. In this work, a forensics methodology was developed and implemented to attribute spent fuel to a source reactor. The specific attributes determined are the spent fuel burnup, age from discharge, reactor type, and initial fuel enrichment. It is shown that by analyzing the post-event material, these attributes can be determined with enough accuracy to be useful for investigators. The burnup can be found within a 5% accuracy, enrichment with a 2% accuracy, and age with a 10% accuracy. Reactor type can be determined if specific nuclides are measured. The methodology developed was implemented into a code call NEMASYS. NEMASYS is easy to use and it takes a minimum amount of time to learn its basic functions. It will process data within a few minutes and provide detailed information about the results and conclusions

  17. Generation projection of solid and liquid radioactive wastes and spent radioactive sources in Mexico

    International Nuclear Information System (INIS)

    Garcia A, E.; Hernandez F, I. Y.; Fernandez R, E.; Monroy G, F.; Lizcano C, D.

    2014-10-01

    This work is focused to project the volumes of radioactive aqueous liquid wastes and spent radioactive sources that will be generated in our country in next 15 years, solids compaction and radioactive organic liquids in 10 years starting from the 2014; with the purpose of knowing the technological needs that will be required for their administration. The methodology involves six aspects to develop: the definition of general objectives, to specify the temporary horizon of projection, data collection, selection of the prospecting model and the model application. This approach was applied to the inventory of aqueous liquid wastes, as well as radioactive compaction organic and solids generated in Mexico by non energy applications from the 2001 to 2014, and of the year 1997 at 2014 for spent sources. The applied projection models were: Double exponential smoothing associating the tendency, Simple Smoothing and Lineal Regression. For this study was elected the first forecast model and its application suggests that: the volume of the compaction solid wastes, aqueous liquids and spent radioactive sources will increase respectively in 152%, 49.8% and 55.7%, while the radioactive organic liquid wastes will diminish in 13.15%. (Author)

  18. Nuclear Forensics Attributing the Source of Spent Fuel Used in an RDD Event

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Mark Robert [Texas A & M Univ., College Station, TX (United States)

    2005-05-01

    An RDD attack against the U.S. is something America needs to prepare against. If such an event occurs the ability to quickly identify the source of the radiological material used in an RDD would aid investigators in identifying the perpetrators. Spent fuel is one of the most dangerous possible radiological sources for an RDD. In this work, a forensics methodology was developed and implemented to attribute spent fuel to a source reactor. The specific attributes determined are the spent fuel burnup, age from discharge, reactor type, and initial fuel enrichment. It is shown that by analyzing the post-event material, these attributes can be determined with enough accuracy to be useful for investigators. The burnup can be found within a 5% accuracy, enrichment with a 2% accuracy, and age with a 10% accuracy. Reactor type can be determined if specific nuclides are measured. The methodology developed was implemented into a code call NEMASYS. NEMASYS is easy to use and it takes a minimum amount of time to learn its basic functions. It will process data within a few minutes and provide detailed information about the results and conclusions.

  19. Source Term Characterization for Structural Components in 17 x 17 KOFA Spent Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Dong Keun; Kook, Dong Hak; Choi, Heui Joo; Choi, Jong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-12-15

    Source terms of metal waste comprising a spent fuel assembly are relatively important when the spent fuel is pyroprocessed, because cesium, strontium, and transuranics are not a concern any more in the aspect of source term of permanent disposal. In this study, characteristics of radiation source terms for each structural component in spent fuel assembly was analyzed by using ORIGEN-S with a assumption that 10 metric tons of uranium is pyroprocessed. At first, mass and volume for each structural component of the fuel assembly were calculated in detail. Activation cross section library was generated by using KENO-VI/ORIGEN-S module for top-end piece and bottom-end piece, because those are located at outer core with different neutron spectrum compared to that of inner core. As a result, values of radioactivity, decay heat, and hazard index were reveled to be 1.40 x 10{sup 15} Bequerels, 236 Watts, 4.34 x 10{sup 9} m{sup 3}-water, respectively, at 10 years after discharge. Those values correspond to 0.7 %, 1.1 %, 0.1 %, respectively, compared to that of spent fuel. Inconel 718 grid plate was shown to be the most important component in the all aspects of radioactivity, decay heat, and hazard index although the mass occupies only 1 % of the total. It was also shown that if the Inconel 718 grid plate is managed separately, the radioactivity and hazard index of metal waste could be decreased to 20 {approx} 45 % and 30 {approx} 45 %, respectively. As a whole, decay heat of metal waste was shown to be negligible in the aspect of disposal system design, while the radioactivity and hazard index are important.

  20. Source Term Characteristics Analysis for Structural Components in PWR spent fuel assembly

    Energy Technology Data Exchange (ETDEWEB)

    Kook, Dong Hak; Choi, Heui Joo; Cho, Dong Keun [KAERI, Daejeon (Korea, Republic of)

    2010-12-15

    Source terms of metal waste comprising a spent fuel assembly are relatively important when the spent fuel is pyroprocessed, because cesium, strontium, and transuranics are not a concern any more in the aspect of source term of permanent disposal. In this study, characteristics of radiation source terms for each structural component in spent fuel assembly was analyzed by using ORIGEN-S with a assumption that 10 metric tons of uranium is pyroprocessed. At first, mass and volume for each structural component of the fuel assembly were calculated in detail. Activation cross section library was generated by using KENO-VI/ORIGEN-S module for top-end piece and bottom-end piece, because those are located at outer core under different neutron spectrum compared to that of inner core. As a result, values of radioactivity, decay heat, and hazard index were reveled to be 1.32x1015 Bequerels, 238 Watts, 4.32x109 m3 water, respectively, at 10 years after discharge. Those values correspond to 0.6 %, 1.1 %, 0.1 %, respectively, compared to that of spent fuel. Inconel 718 grid plate was shown to be the most important component in the all aspects of radioactivity, decay heat, and hazard index although the mass occupies only 1 % of the total. It was also shown that if the Inconel 718 grid plate is managed separately, the radioactivity and hazard index of metal waste could be decreased to 25{approx}50 % and 35{approx}40 %, respectively. As a whole, decay heat of metal waste was shown to be negligible in the aspect of disposal system design, while the radioactivity and hazard index are important

  1. Study of classification and disposed method for disused sealed radioactive source in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Suk Hoon; Kim, Ju Youl; Lee, Seung Hee [FNC Technology Co., Ltd.,Yongin (Korea, Republic of)

    2016-09-15

    In accordance with the classification system of radioactive waste in Korea, all the disused sealed radioactive sources (DSRSs) fall under the category of EW, VLLW or LILW, and should be managed in compliance with the restrictions for the disposal method. In this study, the management and disposal method are drawn in consideration of half-life of radionuclides contained in the source and A/D value (i.e. the activity A of the source dividing by the D value for the relevant radionuclide, which is used to provide an initial ranking of relative risk for sources) in addition to the domestic classification scheme and disposal method, based on the characteristic analysis and review results of the management practices in IAEA and foreign countries. For all the DSRSs that are being stored (as of March 2015) in the centralized temporary disposal facility for radioisotope wastes, applicability of the derivation result is confirmed through performing the characteristic analysis and case studies for assessing quantity and volume of DSRSs to be managed by each method. However, the methodology derived from this study is not applicable to the following sources; i) DSRSs without information on the radioactivity, ii) DSRSs that are not possible to calculate the specific activity and/or the source-specific A/D value. Accordingly, it is essential to identify the inherent characteristics for each of DSRSs prior to implementation of this management and disposal method.

  2. Proposal of conditioning of the not-in-use sealed sources which are stored in the Radioactive Wastes Treatment Facility

    International Nuclear Information System (INIS)

    Jova, L.; Garcia, N.; Benitez, J.C.; Salgado, M.; Hernandez, A.

    1996-01-01

    There is a considerable number of sealed sources which are no longer in use at the radioactive wastes treatment facility. In the present work a methodology is proposed for the final conditioning of these sources, based on their immobilization in a cement matrix. This cementation is accomplished within a 200-liter tank

  3. Assessment of the properties of disused sealed radioactive sources for disposal in a borehole facility

    International Nuclear Information System (INIS)

    Adjepong, K.

    2015-01-01

    Radioactive wastes arise from applications in which radioactive materials are used. Medicine, industries and agriculture are examples of areas where radioactive materials are used. Most of the radioactive materials used in nuclear applications are in the form of sealed radioactive sources (SRS). After a number of usages, the SRS may no longer be useful enough for its original purpose and will be considered as a disused sealed radioactive source (DSRS). DSRS are potentially dangerous to human health and the environment, and therefore important to manage them safely. Currently in Ghana, DSRS are collected and stored awaiting a final disposal option. There are ongoing plans to implement the Borehole Disposal of Disused Sealed Sources (BOSS) system in Ghana as a final disposal option. There are, however, concerns about the number of DSRS disposal packages that can safely be disposed in a narrow borehole underground in a long term without posing any harm to people and the environment. It is therefore necessary to assess the properties of DSRS that need to be placed into the borehole to determine the safety of this disposal option. For this study, 160 DSRS were selected from the DSRS inventory. The present activity, volume, A/D ratio and thermal output of all the DSRS were determined. The SIMBOD database tool was used to determine the number of capsules and disposal packages that will be required with respect to the DSRS registered into it. Also, verification measurements to confirm the DSRS inventory data were conducted. The assessment have shown that DSRS used in this study would require a total of seven (7) capsules. The estimated total activity of the disposal packages were below the waste acceptance criteria and the thermal output for each disposal package were also below the 50W limit. One borehole with an estimated length of 57 m will be safe to dispose the DSRS used in this study. The verification measurements confirmed the confirmed the DSRS inventory data. It

  4. Radiological Risk Assessment and Cask Materials Qualification for Disposed Sealed Radioactive Sources Transport

    International Nuclear Information System (INIS)

    Margeanu, C.A.; Olteanu, G.; Bujoreanu, D.

    2009-01-01

    The hazardous waste problem imposes to respect national and international agreed regulations regarding their transport, taking into account both for maintaining humans, goods and environment exposure under specified limits, during transport and specific additional operations, and also to reduce impact on the environment. The paper follows to estimate the radiological risk and cask materials qualification according to the design specifications for disposed sealed radioactive sources normal transport situation. The shielding analysis has been performed by using Oak Ridge National Laboratory's SCALE 5 programs package. For thermal analysis and cask materials qualification ANSYS computer code has been used. Results have been obtained under the framework of Advanced system for monitoring of hazardous waste transport on the Romanian territory Research Project which main objective consists in implementation of a complex dual system for on-line monitoring both for transport special vehicle and hazardous waste packages, with data automatic transmission to a national monitoring center

  5. Seals and sealing handbook

    CERN Document Server

    Flitney, Robert K

    2014-01-01

    Seals and Sealing Handbook, 6th Edition provides comprehensive coverage of sealing technology, bringing together information on all aspects of this area to enable you to make the right sealing choice. This includes detailed coverage on the seals applicable to static, rotary and reciprocating applications, the best materials to use in your sealing systems, and the legislature and regulations that may impact your sealing choices. Updated in line with current trends this updated reference provides the theory necessary for you to select the most appropriate seals for the job and with its 'Failur

  6. Development of the doubly sealed Ir192 sources for industrial applications

    International Nuclear Information System (INIS)

    Munoz, C.; Sabio Calvett, Manuel; Bianchi, Daniel R.; Banchik, Abraham D.; Mender, Alberto; Gonzalez, Alfredo J.

    2003-01-01

    A Program for Developing Double Sealed Irradiation Sources for industrial and medical applications is in progress at the Argentine Atomic Energy Commission. The present work describes the mechanical and metallurgical procedures for designing and welding dummy capsules of the two types that are required for making double sealed Ir 192 industrial sources with the designation ISO/98/C43515 according to ISO 2919 and leak tight according to ISO/98/9978 standards. That is part of a Project with INVAP company. Four different models, including the typical international model, were designed, machined and TIG-welded. Both the internal and external capsules and the end caps were made from AISI 316L stainless steel. Two types of welding station were made. In the first one the 'end cap' was welded to the capsule keeping the torch and the capsule fixed (stationary process), while in the second type the capsule rotates around its own axes during the process (out of cell dynamic semiautomatic controlled process). The welding parameters for the second welding process were selected from the different parameters used to process 120 'international type' capsules. All the processed units were subject to a visual inspection, 85% of them were considered acceptable, while the rest were rejected because of having, at naked eyes and/or under magnification glasses, different types of welding defects. Metallographic examination of the microstructure at the welding seam and the matrix were made in welded unit selected at random from different lots of all processed units in order to determine the penetration of the weld and the microstructure of the weld seam. Present results are encouraging enough to consider to start with the next step, where the capsules are process inside a 'hot cell' and with a Ir 192 foil inside the inner capsule to reproduce actual fabrication conditions. (author)

  7. Spent fuel storage and isolation

    International Nuclear Information System (INIS)

    Bensky, M.S.; Kurzeka, W.J.; Bauer, A.A.; Carr, J.A.; Matthews, S.C.

    1979-02-01

    The principal spent fuel activities conducted within the commercial waste and spent fuel within the Commercial Waste and Spent Fuel Packaging Program are: simulated near-surface (drywell) storage demonstrations at Hanford and the Nevada Test Site; surface (sealed storage cask) and drywell demonstrations at the Nevada Test Site; and spent fuel receiving and packaging facility conceptual design. These investigations are described

  8. Characterization of sealed radioactive sources. Uncertainty analysis to improve detection methods

    International Nuclear Information System (INIS)

    Cummings, D.G.; Sommers, J.D.; Adamic, M.L.; Jimenez, M.; Giglio, J.J.; Carney, K.P.

    2009-01-01

    A radioactive 137 Cs source has been analyzed for the radioactive parent 137 Cs and stable decay daughter 137 Ba. The ratio of the daughter to parent atoms is used to estimate the date when Cs was purified prior to source encapsulation (an 'age' since purification). The isotopes were analyzed by inductively coupled plasma mass spectrometry (ICP-MS) after chemical separation. In addition, Ba was analyzed by isotope dilution ICP-MS (ID-ICP-MS). A detailed error analysis of the mass spectrometric work has been undertaken to identify areas of improvement, as well as quantifying the effect the errors have on the 'age' determined. This paper reports an uncertainty analysis to identifying areas of improvement and alternative techniques that may reduce the uncertainties. In particular, work on isotope dilution using ICP-MS for the 'age' determination of sealed sources is presented. The results will be compared to the original work done using external standards to calibrate the ICP-MS instrument. (author)

  9. Resistance to radiation and concretes thermal cycles for conditioning of spent radioactive sources

    International Nuclear Information System (INIS)

    Gonzalez N, M.; Monroy G, F.; Gonzalez D, R. C.; Corona P, I. J.; Ortiz A, G.

    2014-10-01

    In order to know the concrete type most suitable for use as a matrix of conditioning of spent radioactive sources, concrete test tubes using 4 different types of cement were prepared: CPC 30-Rs Extra, CPC 30-R Impercem, CPC 30-R Rs and CPC 30-R with two gravel sizes >30 mm and <10 mm. The concrete test tubes were subjected to testing compressive strength after 28 days of hardening and after being irradiated and subjected to thermal cycles. Subsequently they were characterized by X-ray diffraction and scanning electron microscopy, in order to evaluate whether these concretes accredited the tests set by the NOM-019-Nucl-1995. The results show that the compressive strength of the hardened concretes to 28 days presents values between 36 and 25 MPa; applying irradiation the resistance may decrease to 30% of its original strength; and if subjected to high and low temperatures the ettringite formation also causes a decrease in resistance. The results show that concretes made from cement Impercem, Cruz Azul with gravel <10 mm comply with the provisions of standard and they can be used for conditioning of spent radioactive sources. (Author)

  10. Evaluation of source term parameters for spent fuel disposal in foreign countries. (1) Instant release fraction from spent fuel matrices and composition materials for fuel assemblies

    International Nuclear Information System (INIS)

    Nagata, Masanobu; Chikazawa, Takahiro; Kitamura, Akira; Tachi, Yukio; Akahori, Kuniaki

    2016-01-01

    Although spent nuclear fuel is planned to be disposed after reprocessing and vitrification of high-level radioactive waste (HLW), feasibility study on direct disposal of spent nuclear fuel (SF) has been started as one of the alternative disposal options to flexibly apply change of future energy situation in Japan. Radionuclide inventories and their release behavior after breaching spent fuel container should be assessed to confirm safety of the SF disposal. Especially, instant release fractions (IRFs), which are fractions of radionuclide released relatively faster than those released with congruent dissolution with SF and construction materials after breaching spent fuel container, may have an impact on safety assessment of the direct disposal of SF. However, detailed studies on evaluation / estimation of IRF have not been performed in Japan. Therefore, we investigated some foreign safety assessment reports on direct disposal of SF by focusing on IRF for the safety assessment of Japanese SF disposal system. As a result of comparison between the safety assessment reports in foreign countries, although some fundamental data have been referred to the reports in common, the final source term dataset was seen differences between countries in the result of taking into account the national circumstances (reactor types and burnups, etc.). We also found the difference of assignment of uncertainties among the investigated reports; a report selected pessimistic values and another report selected mean values and their deviations. It is expected that these findings are useful as fundamental information for the safety assessment of Japanese SF disposal system. (author)

  11. U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution

    International Nuclear Information System (INIS)

    2002-01-01

    Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro

  12. Carbon sources and trophic relationships of ice seals during recent environmental shifts in the Bering Sea.

    Science.gov (United States)

    Wang, Shiway W; Springer, Alan M; Budge, Suzanne M; Horstmann, Lara; Quakenbush, Lori T; Wooller, Matthew J

    2016-04-01

    Dramatic multiyear fluctuations in water temperature and seasonal sea ice extent and duration across the Bering-Chukchi continental shelf have occurred in this century, raising a pressing ecological question: Do such environmental changes alter marine production processes linking primary producers to upper trophic-level predators? We examined this question by comparing the blubber fatty acid (FA) composition and stable carbon isotope ratios of individual FA (δ¹³CFA) of adult ringed seals (Pusa hispida), bearded seals (Erignathus barbatus), spotted seals (Phoca largha), and ribbon seals (Histriophoca fasciata), collectively known as "ice seals," sampled during an anomalously warm, low sea ice period in 2002-2005 in the Bering Sea and a subsequent cold, high sea ice period in 2007-2010. δ¹³C(FA) values, used to estimate the contribution to seals of carbon derived from sea ice algae (sympagic production) relative to that derived from water column phytoplankton (pelagic production), indicated that during the cold period, sympagic production accounted for 62-80% of the FA in the blubber of bearded seals, 51-62% in spotted seals, and 21-60% in ringed seals. Moreover, the δ¹³CFA values of bearded seals indicated a greater incorporation of sympagic FAs during the cold period than the warm period. This result provides the first empirical evidence of an ecosystem-scale effect of a putative change in sympagic production in the Western Arctic. The FA composition of ice seals showed clear evidence of resource partitioning among ringed, bearded, and spotted seals, and little niche separation between spotted and ribbon seals, which is consistent with previous studies. Despite interannual variability, the FA composition of ringed and bearded seals showed little evidence of differences in diet between the warm and cold periods. The findings that sympagic production contributes significantly to food webs supporting ice seals, and that the contribution apparently is less in

  13. Radiotracer and sealed source techniques for sediment management. Report of the consultants meeting

    International Nuclear Information System (INIS)

    2008-01-01

    Radioisotopes as tracers and sealed sources have been a useful and often irreplaceable tool for sediment transport studies. Gamma scattering and transmission gauges are used for sediment monitoring. Computational fluid dynamics (CFD) modelling is now an essential tool for the management of the natural systems and are increasingly used to study the fate and behaviour of particulates and contaminants. Radiotracer techniques are often employed to validate CFD models to enhance confidence in the predictive value of the models. Experimental tracing and numerical modelling are complementary methods of studying complex systems. During the last few decades, many radiotracer studies for the investigation of sediment transport in natural systems have been conducted worldwide, and various techniques for tracing and monitoring sediment have been developed by individual tracer groups. However, the developed techniques and methods for sediment tracing have not been compiled yet as a technical document, which is essential for the preservation of the knowledge and transfer of the technology to developing countries. Standard procedures or guidelines for the tracer experiments, which are vital for the reliability of the experiments and the acceptance of end-users, have not been established by the international tracer community either. The use of radiotracers in sediment transport studies demands the additional attention of the community to further develop these techniques and to ensure their transfer to developing countries. The Consultants' Meeting on 'Radiotracer and sealed source techniques for sediment management' was convened at the headquarters of the International Atomic Energy Agency (IAEA) in Vienna, Austria, from 21 to 25 April 2008. Experts from Argentina, Brazil, France, India, Republic of Korea and United Kingdom have been invited to discuss the current status of the tracer and nucleonic gauge technologies as applied for sediment transport investigations and to evaluate

  14. Radiotracer and sealed source techniques for sediment management. Report of the consultants meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Radioisotopes as tracers and sealed sources have been a useful and often irreplaceable tool for sediment transport studies. Gamma scattering and transmission gauges are used for sediment monitoring. Computational fluid dynamics (CFD) modelling is now an essential tool for the management of the natural systems and are increasingly used to study the fate and behaviour of particulates and contaminants. Radiotracer techniques are often employed to validate CFD models to enhance confidence in the predictive value of the models. Experimental tracing and numerical modelling are complementary methods of studying complex systems. During the last few decades, many radiotracer studies for the investigation of sediment transport in natural systems have been conducted worldwide, and various techniques for tracing and monitoring sediment have been developed by individual tracer groups. However, the developed techniques and methods for sediment tracing have not been compiled yet as a technical document, which is essential for the preservation of the knowledge and transfer of the technology to developing countries. Standard procedures or guidelines for the tracer experiments, which are vital for the reliability of the experiments and the acceptance of end-users, have not been established by the international tracer community either. The use of radiotracers in sediment transport studies demands the additional attention of the community to further develop these techniques and to ensure their transfer to developing countries. The Consultants' Meeting on 'Radiotracer and sealed source techniques for sediment management' was convened at the headquarters of the International Atomic Energy Agency (IAEA) in Vienna, Austria, from 21 to 25 April 2008. Experts from Argentina, Brazil, France, India, Republic of Korea and United Kingdom have been invited to discuss the current status of the tracer and nucleonic gauge technologies as applied for sediment transport investigations and to evaluate

  15. ORIGAMI Automator Primer. Automated ORIGEN Source Terms and Spent Fuel Storage Pool Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Wieselquist, William A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Thompson, Adam B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bowman, Stephen M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peterson, Joshua L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    Source terms and spent nuclear fuel (SNF) storage pool decay heat load analyses for operating nuclear power plants require a large number of Oak Ridge Isotope Generation and Depletion (ORIGEN) calculations. SNF source term calculations also require a significant amount of bookkeeping to track quantities such as core and assembly operating histories, spent fuel pool (SFP) residence times, heavy metal masses, and enrichments. The ORIGEN Assembly Isotopics (ORIGAMI) module in the SCALE code system provides a simple scheme for entering these data. However, given the large scope of the analysis, extensive scripting is necessary to convert formats and process data to create thousands of ORIGAMI input files (one per assembly) and to process the results into formats readily usable by follow-on analysis tools. This primer describes a project within the SCALE Fulcrum graphical user interface (GUI) called ORIGAMI Automator that was developed to automate the scripting and bookkeeping in large-scale source term analyses. The ORIGAMI Automator enables the analyst to (1) easily create, view, and edit the reactor site and assembly information, (2) automatically create and run ORIGAMI inputs, and (3) analyze the results from ORIGAMI. ORIGAMI Automator uses the standard ORIGEN binary concentrations files produced by ORIGAMI, with concentrations available at all time points in each assembly’s life. The GUI plots results such as mass, concentration, activity, and decay heat using a powerful new ORIGEN Post-Processing Utility for SCALE (OPUS) GUI component. This document includes a description and user guide for the GUI, a step-by-step tutorial for a simplified scenario, and appendices that document the file structures used.

  16. The production of Co-60 sealed sources at the National Atomic Energy Commission

    International Nuclear Information System (INIS)

    Freijo, Jose L.

    2002-01-01

    The production and sale of Cobalt 60 by CNEA is in a key momentum for its consolidation, after passing through situations dose to un viability. The sealed sources demand is assured for the next six years and strongly concentrated in the exportation, mainly to the United States and Europe. The project is economically viable even keeping in mind the necessary investments to assure the growing and sustentability of the business. Therefore, it is possible to have realistic and optimists expectation of growing in the medium and long term. To this respect it results fundamental to confront these activities with a medium and long term vision in order to avoid future uncertainties in the project and, at the same time, to guide and motivate the personnel involved in the efforts that necessarily must be performed to achieve the proposed target. The fundamental steps to be concreted are the construction of new production cells and the transformation of the activities into a private development frame through the creation of a commercial society. (author)

  17. Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

    International Nuclear Information System (INIS)

    Lee, D.W.; Shingleton, K.L.

    1996-01-01

    Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated

  18. Automation system for quality control in manufacture of iodine-125 sealed sources used in brachytherapy

    International Nuclear Information System (INIS)

    Somessari, Samir L.; Feher, Anselmo; Sprenger, Francisco E.; Rostellato, Maria E.C.M.; Moura, Joao A.; Costa, Osvaldo L.; Calvo, Wilson A.P.

    2011-01-01

    The objective of this work is to develop an automation system for Quality Control in the production of Iodine-125 sealed sources, after undergoing the process of laser beam welding. These sources, also known as Iodine-125 seeds are used, successfully, in the treatment of cancer by brachytherapy, with low-dose rates. Each small seed is composed of a welded titanium capsule with 0.8 mm diameter and 4.5 mm in length, containing Iodine-125 adsorbed on an internal silver wire. The seeds are implanted in the human prostate to irradiate the tumor and treat the cancerous cells. The technology to automate the quality control system in the manufacture of Iodine-125 seeds consists in developing and associate mechanical parts, electronic components and pneumatic circuits to control machines and processes. The automation technology for Iodine-125 seed production developed in this work employs programmable logic controller, step motors, drivers of control, electrical-electronic interfaces, photoelectric sensors, interfaces of communication and software development. Industrial automation plays an important role in the production of Iodine-125 seeds, with higher productivity and high standard of quality, facilitating the implementation and operation of processes with good manufacturing practices. Nowadays, the Radiation Technology Center at IPEN-CNEN/SP imports and distributes 36,000 Iodine-125 seeds per year for clinics and hospitals in the whole country. However, the Brazilian potential market is of 8,000 Iodine-125 seeds per month. Therefore, the local production of these radioactive seeds has become a priority for the Institute, aiming to reduce the price and increase the supply to the population in Brazil. (author)

  19. Automation system for quality control in manufacture of iodine-125 sealed sources used in brachytherapy

    Energy Technology Data Exchange (ETDEWEB)

    Somessari, Samir L.; Feher, Anselmo; Sprenger, Francisco E.; Rostellato, Maria E.C.M.; Moura, Joao A.; Costa, Osvaldo L.; Calvo, Wilson A.P., E-mail: somessar@ipen.b, E-mail: afeher@ipen.b, E-mail: sprenger@ipen.b, E-mail: elisaros@ipen.b, E-mail: olcosta@ipen.b, E-mail: wapcalvo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The objective of this work is to develop an automation system for Quality Control in the production of Iodine-125 sealed sources, after undergoing the process of laser beam welding. These sources, also known as Iodine-125 seeds are used, successfully, in the treatment of cancer by brachytherapy, with low-dose rates. Each small seed is composed of a welded titanium capsule with 0.8 mm diameter and 4.5 mm in length, containing Iodine-125 adsorbed on an internal silver wire. The seeds are implanted in the human prostate to irradiate the tumor and treat the cancerous cells. The technology to automate the quality control system in the manufacture of Iodine-125 seeds consists in developing and associate mechanical parts, electronic components and pneumatic circuits to control machines and processes. The automation technology for Iodine-125 seed production developed in this work employs programmable logic controller, step motors, drivers of control, electrical-electronic interfaces, photoelectric sensors, interfaces of communication and software development. Industrial automation plays an important role in the production of Iodine-125 seeds, with higher productivity and high standard of quality, facilitating the implementation and operation of processes with good manufacturing practices. Nowadays, the Radiation Technology Center at IPEN-CNEN/SP imports and distributes 36,000 Iodine-125 seeds per year for clinics and hospitals in the whole country. However, the Brazilian potential market is of 8,000 Iodine-125 seeds per month. Therefore, the local production of these radioactive seeds has become a priority for the Institute, aiming to reduce the price and increase the supply to the population in Brazil. (author)

  20. Characterization and packaging of disused sealed radioactive sources; Caracterizacion y acondicionamiento de fuentes radiactivas selladas en desuso

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar, S.L. [Instituto Boliviano de Ciencia y Tecnologia Nuclear (IBTEN), La Paz (Bolivia, Plurinational State of)

    2013-07-01

    In Bolivia are generated disused sealed sources and radioactive waste resulting from the use of radioactive materials in industrial, research and medicine. The last includes the diagnosis and treatment. Whereas exposure to ionizing radiation is a potential hazard to personnel who applies it, to those who benefit from its use or for the community at large, it is necessary to control the activities in this field. The Instituto Boliviano de Ciencia y Tecnologia Nuclear - IBTEN is working on a regional project from International Atomic Energy Agency - IAEA, RLA/09/062 Project - TSA 4, Strengthening the National Infrastructure and Regulatory Framework for the Safe Management of Radioactive waste in Latin America. This Project has strengthened the regulatory framework regarding the safe management of radioactive waste. The aim of this work was focused primarily on the security aspects in the safe management of disused sealed sources. The tasks are listed below: 1. Characterization of disused sealed sources 2. Preparation for transport to temporary storage 3. Control of all disused radioactive sources. (author)

  1. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Feldman, Alexander [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-04-24

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

  2. Collective processing device for spent fuel

    International Nuclear Information System (INIS)

    Irie, Hiroaki; Taniguchi, Noboru.

    1996-01-01

    The device of the present invention comprises a sealing vessel, a transporting device for transporting spent fuels to the sealing vessel, a laser beam cutting device for cutting the transported spent fuels, a dissolving device for dissolving the cut spent fuels, and a recovering device for recovering radioactive materials from the spent fuels during processing. Reprocessing treatments comprising each processing of dismantling, shearing and dissolving are conducted in the sealing vessel can ensure a sealing barrier for the radioactive materials (fissionable products and heavy nuclides). Then, since spent fuels can be processed in a state of assemblies, and the spent fuels are easily placed in the sealing vessel, operation efficiency is improved, as well as operation cost is saved. Further, since the spent fuels can be cut by a remote laser beam operation, there can be prevented operator's exposure due to radioactive materials released from the spent fuels during cutting operation. (T.M.)

  3. Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine

    International Nuclear Information System (INIS)

    Tiezzi, Rodrigo

    2016-01-01

    The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and

  4. Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Tiezzi, Rodrigo; Rostelato, Maria Elisa C.M.; Nagatomi, Helio R.; Zeituni, Calos A.; Benega, Marcos A.G.; Souza, Daiane B. de; Costa, Osvaldo L. da; Souza, Carla D.; Rodrigues, Bruna T.; Souza, Anderson S. de; Peleias Junior, Fernando S.; Santos, Rafael Melo dos; Melo, Emerson Ronaldo de, E-mail: rktiezzi@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Karan Junior, Dib [Universidade de Sao Paulo (USP), Sao Paulo, SP (Brazil)

    2015-07-01

    The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133, Cesium-137 and Cobalt-57,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum solubility of the resin in water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical

  5. Special Analysis for the Disposal of the Materials and Energy Corporation Sealed Sources at the Area 5 Radioactive Waste Management Site

    Energy Technology Data Exchange (ETDEWEB)

    Shott, Gregory [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

    2017-05-15

    This special analysis (SA) evaluates whether the Materials and Energy Corporation (M&EC) Sealed Source waste stream (PERM000000036, Revision 0) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the M&EC Sealed Source waste meets all U.S. Department of Energy (DOE) Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives (DOE 1999). The M&EC Sealed Source waste stream is recommended for acceptance without conditions.

  6. Use of reports on accidents with sealed sources to conceive scenarios of human intrusion into waste repositories

    International Nuclear Information System (INIS)

    Leite, Eliana Rodrigues; Oliveira, Rosana Lagua de; Vicente, Roberto

    2011-01-01

    The Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN) develops the concept of a repository for disposal of disused sealed radioactive sources (SRS) in a deep borehole. In this concept, the estimated few hundred thousand SRS of the Brazilian inventory will be packaged in lead containers stacked in an encased and cemented borehole, drilled to a depth of a few hundred meters, in a crystalline bedrock geological setting. A generic safety analysis for this concept of repository must achieve two goals: to be acceptable by regulatory bodies and be simple enough so that the engineering of licensing a facility has technical and economical feasibility. It must be kept in mind that the disposition of the SRS must be paid by the users of the sources, and thal the costs of applying the existing methods for the performance and safety assessment of a geological repository dedicated exclusively for sealed sources may be exceedingly high. In this respect, the disposal concept development work includes the search for methodologies that could be applied to the disposal facility for demonstrating safety without unduly increasing the project costs. One line of research is to identify and characterize human intrusion scenarios that could result in significant radiation exposures. Results of a survey on the published literature and on databases of reported accidents involving sealed sources are being used to construct a number of model accident scenarios with which the time evolution of the exposure risks can be assessed for each radioisotope inventory and each relevant disposed of source. Among the 252 accident descriptions recovered in the survey, the 1954 Russian accident report with Po-210 is the oldest, and that of the 2010 accident in Mayapuri, India, with a Co-60 source is the latest. The results of this assessment will be used as a safety indicator of the disposal concept. (author)

  7. Seals and sealing handbook

    CERN Document Server

    Flitney, Robert K

    2007-01-01

    Wherever machinery operates there will be seals of some kind ensuring that the machine remains lubricated, the fluid being pumped does not leak, or the gas does not enter the atmosphere. Seals are ubiquitous, in industry, the home, transport and many other places. This 5th edition of a long-established title covers all types of seal by application: static, rotary, reciprocating etc. The book bears little resemblance to its predecessors, and Robert Flitney has re-planned and re-written every aspect of the subject. No engineer, designer or manufacturer of seals can afford to be without this uniq

  8. Comparative Study on Radiological Impact Due To Direct Exposure to a Radiological Dispersal Device Using A Sealed Radiation Source

    International Nuclear Information System (INIS)

    Margeanu, C.A.

    2011-01-01

    Nowadays, one of the most serious terrorist threats implies radiological dispersal devices (RDDs), the so-called dirty bombs, that combine a conventional explosive surrounded by an inflammatory material (like thermit) with radioactive material. The paper objective is to evaluate the radiological impact due to direct exposure to a RDD using a sealed radiation source (used for medical and industrial applications) as radioactive material. The simulations were performed for 60Co, 137Cs and 192Ir radiation sources. In order to model the contamination potential level and radiation exposure due to radioactive material spreading from RDD, Lawrence Livermore National Laboratory's HOTSPOT 2.07 computer code was used. The worst case scenario has been considered, calculations being performed for two radioactive material dispersion models, namely General radioactive Plume and General Explosion. Following parameters evolution with distance from the radiation source was investigated: total effective dose equivalent, time-integrated air concentration, ground surface deposition and ground shine dose rates. Comparisons between considered radiation sources and radioactive material dispersion models have been performed. The most drastic effects on population and the environment characterize 60Co sealed radiation source use in RDD.

  9. A vacuum-sealed, gigawatt-class, repetitively pulsed high-power microwave source

    Science.gov (United States)

    Xun, Tao; Fan, Yu-wei; Yang, Han-wu; Zhang, Zi-cheng; Chen, Dong-qun; Zhang, Jian-de

    2017-06-01

    A compact L-band sealed-tube magnetically insulated transmission line oscillator (MILO) has been developed that does not require bulky external vacuum pump for repetitive operations. This device with a ceramic insulated vacuum interface, a carbon fiber array cathode, and non-evaporable getters has a base vacuum pressure in the low 10-6 Pa range. A dynamic 3-D Monte-Carlo model for the molecular flow movement and collision was setup for the MILO chamber. The pulse desorption, gas evolution, and pressure distribution were exactly simulated. In the 5 Hz repetition rate experiments, using a 600 kV diode voltage and 48 kA beam current, the average radiated microwave power for 25 shots is about 3.4 GW in 45 ns pulse duration. The maximum equilibrium pressure is below 4.0 × 10-2 Pa, and no pulse shortening limitations are observed during the repetitive test in the sealed-tube condition.

  10. Food source and residual efficacy of chlorfenapyr on sealed and unsealed concrete

    Science.gov (United States)

    Adult Tribolium castaneum (Herbst), the red flour beetle, were exposed at 1 day, and 2, 4, and 6 weeks post-treatment on sealed and unsealed concrete arenas treated with chlorfenapyr at rates of 2.8, 6.9, 13.5, 20.6, 27.5 mg active ingredient/m2. Beetles were held either with or without flour, and a...

  11. MODIFIED APPROACH FOR SITE SELECTION OF UNWANTED RADIOACTIVE SEALED SOURCES DISPOSAL IN ARID COUNTRIES (CASE STUDY - EGYPT)

    International Nuclear Information System (INIS)

    ABDEL AZIZ, M.A.H.; COCHRAN, J.R.

    2008-01-01

    The aim of this study is to present a systematic methodology for siting of radioactive sealed sources disposal in arid countries and demonstrate the use of this methodology in Egypt. Availing from the experience gained from the greater confinement disposal (GCD) boreholes in Nevada, USA, the IAEA's approach for siting of near disposal was modified to fit the siting of the borehole disposal which suits the unwanted radioactive sealed sources. The modifications are represented by dividing the surveyed area into three phases; the exclusion phase in which the areas that meet exclusion criteria should be excluded, the site selection phase in which some potential sites that meet the primary criteria should be candidate and the preference stage in which the preference between the potential candidate sites should be carried out based on secondary criteria to select one or two sites at most. In Egypt, a considerable amount of unwanted radioactive sealed sources wastes have accumulated due to the peaceful uses of radio-isotopes.Taking into account the regional aspects and combining of the proposed developed methodology with geographic information system (GIS), the Nile Delta and its valley, the Sinai Peninsula and areas of historical heritage value are excluded from our concern as potential areas for radioactive waste disposal. Using the primary search criteria, some potential sites south Kharga, the Great Sand Sea, Gilf El-Kebear and the central part of the eastern desert have been identified as candidate areas meeting the primary criteria of site selection. More detailed studies should be conducted taking into account the secondary criteria to prefer among the above sites and select one or two sites at most

  12. Standard operational radiation protection instructions for process instrumentation and control engineering applying radiometric equipment containing sealed sources

    International Nuclear Information System (INIS)

    1989-01-01

    According to article 16(3) of the Ordinance on the Implementation of Atomic Safety and Radiation Protection of 11 October 1984, operational radiation protection instructions have to be worked out for each type of nuclear energy application. Based on the valid legal provisions of the GDR and on experience and knowledge gained in practice, the most important operational instructions and procedures for the operation of radiometric equipment containing sealed sources were compiled. The example should enable the management to make the instructions directly applicable and, if necessary, to modify or supplement them

  13. THE PROBLEMS OF USING EXEMPTION ACTIVITY VALUES FOR REGULATING THE MANAGEMENT OF SEALED RADIONUCLIDE SOURCES OF GAMMA-RADIATION

    Directory of Open Access Journals (Sweden)

    A. N. Barkovsky

    2017-01-01

    Full Text Available The article focuses on the procedure for exemption of the sealed and unsealed radionuclide sources of gamma radiation from regulatory control. The contradictory nature of the existing set of exemption criteria has been noted, leading, in some cases, to paradoxical situations. It is shown that the exempt activity values determined in NRB-99/2009 and in the international basic safety standards of the IAEA are significantly overestimated (in comparison with the activity values of a point source creating the ambient dose equivalent rate of 1 μSv / h at a distance of 0.1 m for a number of the most widely used gamma-emitting radionuclides, including 22Na, 54Mn, 75Se, 152Eu and 154Eu. It is proposed to revise the current values of exempt activity, bringing them in line with the dose rate criterion for the exempt of sealed radionuclide sources of gamma radiation, and to present them with one significant digit. The corrected values of exempt activity for  seven selected radionuclides are proposed for further use in the process of revision of the national radiation safety standards.

  14. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    International Nuclear Information System (INIS)

    Lee, Seunghee; Kim, Juyoul

    2017-01-01

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • 14 C, 226 Ra, 241 Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing 14 C, 226 Ra and 241 Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10 −7 mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1 mSv/yr. However, in the

  15. Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seunghee; Kim, Juyoul, E-mail: gracemi@fnctech.com

    2017-03-15

    Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • {sup 14}C, {sup 226}Ra, {sup 241}Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing {sup 14}C, {sup 226}Ra and {sup 241}Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10{sup −7} mSv/yr, for both disposal options and satisfied the regulatory limit

  16. S.I. No 17 of 1972, Factories Ionising Radiations (Sealed Sources) Regulations, 1972

    International Nuclear Information System (INIS)

    1972-03-01

    The purpose of the Regulations in general is to prescribe measures which must be taken to ensure the adequate protection of persons employed in factories and other places to which the Factories Act 1955 applies, against ionizing radiations arising from radioactive substances sealed in a container and from any machine or apparatus including irradiating apparatus that is intended to produce ionizing radiations in which charged particles are accelerated by a voltage of not less than 5 kilovolts. The Schedule lays down the maximum permissible doses of radiation for the different categories of workers. The Regulations entered into force on 1 March 1972 [fr

  17. The development of a mobile hot cell facility for the conditioning of spent high activity radioactive sources

    International Nuclear Information System (INIS)

    Liebenberg, G.R.; Al-Mughrabi, M.

    2010-01-01

    The International Atomic Energy Agency (IAEA) Waste Technology Section with additional support from the U.S. National Nuclear Security Administration (NNSA) through the IAEA Nuclear Security Fund has funded the design, fabrication, evaluation, and testing of a portable hot cell intended to address the problem of disused Spent High Activity Radioactive Sources (SHARS) in obsolete irradiation devices such as teletherapy heads and dry irradiators. The project is initially targeting the African continent but expected soon to expand to Latin America and Asia. This hot cell allows source removal, characterization, consolidation, repackaging in modern storage shields, and secure storage of high risk SHARS at national radioactive waste storage facilities. (authors)

  18. Proposed approach to derivation of acceptance criteria for disposal of disused sealed sources mixed with other accepted wastes in near-surface repository

    International Nuclear Information System (INIS)

    Salzer, P.; Stefula, V.; Homola, J.

    2003-01-01

    The Mochovce repository is described in the report. It is vault type near surface repository with 80 concrete vaults (2x2x20), 90 FRC containers (3.1 m 3 ) in one vault (3x10x3), compacted clay bath-tub around double row. 300 years of institutional control are envisioned.The following scenarios are examined: Normal evolution scenario; Alternative evolution scenarios (perforated clay barrier; well in close proximity); Intruder scenarios (construction of simple dwelling; construction of multi-storey building; construction of road; residence scenario). It is being proposed that the DSSs are disposed of in the containers together with normal operational waste. Long-lived alpha emitters - excluded a priori (e.g. 226 Ra); Short-lived (T 1/2 = 10 2 days) radionuclides - interim stored until decayed down to clearance level 60 Co - no activity limit, with due consideration of operational safety. The DSSs disposal issue is thus reduced to the disposal of 137 Cs. No limit has been imposed on total activity. Existing limits for operational waste: 3.13.10 13 Bq / container in the upper layer; 3.41.10 13 Bq / container in the bottom or intermediate layer. The acceptance criteria are assessed according to the risk. Two are models set up in MicroShield ver. 5.0. Homogenous source of 137 Cs in cubic concrete container and point source (hot spot) of the same activity. The result is - dose from the point source is 16.6 times higher than the one from the cube. As a result the following new restrictions arise for disposal of the 137 Cs spent industrial sources: disposal of DSSs is forbidden in the upper layer of the containers; maximum activity of the 137 Cs disused industrial source emplaced into the FRC container is 3.41x10 13 / 16.6 = 2.05x10 12 Bq in case of FRC filling by non-radioactive cement mortar; if the cemented radioactive waste is to be used for filling of FRC, decrease of the limit for the disused sealed source is equivalent to the radioactivity of the cement mixture

  19. The Analytical Repository Source-Term (AREST) model: Analysis of spent fuel as a nuclear waste form

    International Nuclear Information System (INIS)

    Apted, M.J.; Liebetrau, A.M.; Engel, D.W.

    1989-02-01

    The purpose of this report is to assess the performance of spent fuel as a final waste form. The release of radionuclides from spent nuclear fuel has been simulated for the three repository sites that were nominated for site characterization in accordance with the Nuclear Waste Policy Act of 1982. The simulation is based on waste package designs that were presented in the environmental assessments prepared for each site. Five distinct distributions for containment failure have been considered, and the release for nuclides from the UO 2 matrix, gap (including grain boundary), crud/surface layer, and cladding has been calculated with the Analytic Repository Source-Term (AREST) code. Separate scenarios involving incongruent and congruent release from the UO 2 matrix have also been examined using the AREST code. Congruent release is defined here as the condition in which the relative mass release rates of a given nuclide and uranium from the UO 2 matrix are equal to their mass ratios in the matrix. Incongruent release refers to release of a given nuclide from the UO 2 matrix controlled by its own solubility-limiting solid phase. Release of nuclides from other sources within the spent fuel (e.g., cladding, fuel/cladding gap) is evaluated separately from either incongruent or congruent matrix release. 51 refs., 200 figs., 9 tabs

  20. Safety quality classification test of the sealed neutron sources used in start-up neutron source rods for Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yao Chunbing; Guo Gang; Chao Jinglan; Duan Liming

    1992-01-01

    According to the regulations listed in the GB4075, the safety quality classification tests have been carried out for the neutron sources. The test items include temperature, external pressure, impact, vibration and puncture, Two dummy sealed sources are used for each test item. The testing equipment used have been examined and verified to be qualified by the measuring department which is admitted by the National standard Bureau. The leak rate of each tested sample is measured by UL-100 Helium Leak Detector (its minimum detectable leak rate is 1 x 10 -10 Pa·m 3 ·s -1 ). The samples with leak rate less than 1.33 x 10 -8 Pa·m 3 ·s -1 are considered up to the standard. The test results show the safety quality classification class of the neutron sources have reached the class of GB/E66545 which exceeds the preset class

  1. Study and methodology development for quality control in the production process of iodine-125 radioactive sealed sources applied to brachytherapy

    International Nuclear Information System (INIS)

    Moura, Joao Augusto

    2009-01-01

    Today cancer is the second cause of death by disease in several countries, including Brazil. Excluding skin cancer, prostate cancer is the most incident in the population. Prostate tumor can be treated by several ways, including brachytherapy, which consists in introducing sealed radioactive sources (Iodine - 125 seeds) inside the tumor. The target region of treatment receives a high radiation dose, but healthy neighbor tissues receive a significantly reduced radiation dose. The seed is made of a welding sealed titanium capsule, 0.8 mm external diameter and 4.5 mm length, enclosing a 0.5 mm diameter silver wire with Iodine-125 adsorbed. After welded, the seeds have to be submitted to a leak test to prevent any radioactive material release. The aims of this work were: (a) the study of the different leakage test methods applied to radioactive seeds and recommended by the ISO 997820, (b) the choice of the appropriate method and (c) the flowchart determination of the process to be used during the seeds production. The essays exceeded the standards with the use of ultra-sound during immersion and the corresponding benefits to leakage detection. Best results were obtained with the immersion in distilled water at 20 degree C for 24 hours and distilled water at 70 degree C for 30 minutes. These methods will be used during seed production. The process flowchart has all the phases of the leakage tests according to the sequence determined in the experiments. (author)

  2. Procedure to carry out leakage test in beta radiation sealed sources emitters of 90Sr/90Y

    International Nuclear Information System (INIS)

    Alvarez R, J. T.

    2010-09-01

    In the alpha-beta room of the Secondary Laboratory of Dosimetric Calibration of the Metrology Department of Ionizing Radiations ophthalmic applicators are calibrated in absorbed dose terms in water D w ; these applicators, basically are emitter sealed sources of pure beta radiation of 90 Sr / 90 Y. Concretely, the laboratory quality system indicates to use the established procedure for the calibration of these sources, which establishes the requirement of to carry out a leakage test, before to calibrate the source. However, in the Laboratory leakage test certificates sent by specialized companies in radiological protection services have been received, in which are used gamma spectrometry equipment s for beta radiation leakage tests, since it is not reliable to detect pure beta radiation with a scintillating detector with NaI crystal, (because it could detect the braking radiation produced in the detector). Therefore the Laboratory has had to verify the results of the tests with a correct technique, with the purpose of determining the presence of sources with their altered integrity and radioactive material leakage. The objective of this work is to describe a technique for beta activity measurement - of the standard ISO 7503, part 1 (1988) - and its application with a detector Gm plane (type pankage) in the realization of leakage tests in emitter sources of pure beta radiation, inside the mark of quality assurance indicated by the report ICRU 76. (Author)

  3. Structural evaluation of spent nuclear fuel storage facilities under aircraft crash impact. Numerical study on evaluation of sealing performance of metal cask subjected to impact force

    International Nuclear Information System (INIS)

    Namba, Kosuke; Shirai, Koji; Saegusa, Toshiari

    2008-01-01

    A lot of safety evaluations on the important nuclear facilities against the aircraft crash have been reported in other countries. But the condition and the evaluation method to define impact force of aircraft crash have not been described clearly in the reports. In Japan, public concern with the safety evaluation against aircraft crash is increasing. It is important to make clear the behavior of the storage facilities installing the metal casks on impact loading due to aircraft crash. In this study, concerning crash between commercial aircraft and storage facility, impact analysis using dynamic analysis code LS-DYNA has been executed. The results showed that the storage facility was not completely destroyed. But the rigid aircraft engine may penetrate into the storage facility with local failure. Thus, we assumed the engine hit a metal cask in the storage facility and evaluated sealing performance of the metal cask under the impact loading. If the engine with 90m/s crashed the storage facility having concrete wall of 85cm in thickness, the remaining velocity became 60m/s after penetration. We calculated impact force of the engine with 60m/s crashing into the metal cask. Concerning the metal cask loaded the impact force, impact analysis was executed. We assumed two directions of impact force. One is vertical load and another is horizontal load against the cask. The result showed that plastic strain was not generated on flanges of the 1st lid and the sealing performance of the cask was maintained in each impact case. (author)

  4. Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-08-31

    The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

  5. Cradle to Grave: Managing Disused Sealed Radioactive Sources in the Mediterranean Region

    International Nuclear Information System (INIS)

    Henriques, Sasha

    2014-01-01

    Some countries in the Mediterranean region lack appropriate facilities for the safe management or disposal of radioactive waste such as disused radioactive sources. Disused radioactive sources could be lost, stolen or abandoned and thus fall outside the regulatory control. Such loss of control over disused sources presents a significant risk to the public and the environment

  6. Glass sealing

    Energy Technology Data Exchange (ETDEWEB)

    Brow, R.K.; Kovacic, L.; Chambers, R.S. [Sandia National Labs., Albuquerque, NM (United States)

    1996-04-01

    Hernetic glass sealing technologies developed for weapons component applications can be utilized for the design and manufacture of fuel cells. Design and processing of of a seal are optimized through an integrated approach based on glass composition research, finite element analysis, and sealing process definition. Glass sealing procedures are selected to accommodate the limits imposed by glass composition and predicted calculations.

  7. Feasibility of sealed D-T neutron generator as neutron source for liver BNCT and its beam shaping assembly.

    Science.gov (United States)

    Liu, Zheng; Li, Gang; Liu, Linmao

    2014-04-01

    This paper involves the feasibility of boron neutron capture therapy (BNCT) for liver tumor with four sealed neutron generators as neutron source. Two generators are placed on each side of the liver. The high energy of these emitted neutrons should be reduced by designing a beam shaping assembly (BSA) to make them useable for BNCT. However, the neutron flux decreases as neutrons pass through different materials of BSA. Therefore, it is essential to find ways to increase the neutron flux. In this paper, the feasibility of using low enrichment uranium as a neutron multiplier is investigated to increase the number of neutrons emitted from D-T neutron generators. The neutron spectrum related to our system has a proper epithermal flux, and the fast and thermal neutron fluxes comply with the IAEA recommended values. Copyright © 2014 Elsevier Ltd. All rights reserved.

  8. Mössbauer and Raman spectroscopy characterization of concretes used in the conditioning of spent radioactive sources

    Energy Technology Data Exchange (ETDEWEB)

    Monroy-Guzman, F., E-mail: fabiola.monroy@inin.gob.mx; González-Neri, M.; González-Díaz, R. C.; Ortíz-Arcivar, G.; Corona-Pérez, I. J. [Instituto Nacional de Investigaciones Nucleares. Carretera México-Toluca s/n, La Marquesa, Ocoyoacac (Mexico); Nava, N. [Instituto Mexicano del Petroleo (Mexico); Cabral-Prieto, A.; Escobar-Alarcón, L. [Instituto Nacional de Investigaciones Nucleares. Carretera México-Toluca s/n, La Marquesa, Ocoyoacac (Mexico)

    2015-06-15

    Spent radioactive sources are considered a type of radioactive waste which must be stored properly. These sources are usually conditioned in concrete that functions as shield and physical barrier to prevent the potential migration of radionuclides, and must have suitable properties: mechanical, thermal or irradiation resistance. Concretes used in the conditioning of spent radioactive source in Mexico were tested, preparing concrete test specimens with Portland cement CPC 30RS EXTRA CEMEX and aggregates, and subjected to compression strength, γ-ray-irradiation and thermal resistance assays and subsequently analyzed by Mössbauer and Raman Spectroscopies as well as by Scanning Electron Microscopy, in order to correlate the radiation and temperature effects on the compressive strengths, the oxidation states of iron and the structural features of the concrete. Iron was found in the concrete in Fe {sup 2+} and Fe {sup 3+} in the tetrahedral (T) and two octahedral positions (O1, O2). Radiolysis of water causes the dehydratation (200-600 kGy) and rehydratation (1000-10000 kGy) of calcium silicate hydrates (C-S-H) and ferric hydrate phases in concretes and structural distortion around the iron sites in concretes. The compressive strength of concretes are not significantly affected by γ-radiation or heat.

  9. Pre-Columbian mycobacterial genomes reveal seals as a source of New World human tuberculosis

    Science.gov (United States)

    Bos, Kirsten I.; Harkins, Kelly M.; Herbig, Alexander; Coscolla, Mireia; Weber, Nico; Comas, Iñaki; Forrest, Stephen A.; Bryant, Josephine M.; Harris, Simon R.; Schuenemann, Verena J.; Campbell, Tessa J.; Majander, Kerrtu; Wilbur, Alicia K.; Guichon, Ricardo A.; Wolfe Steadman, Dawnie L.; Cook, Della Collins; Niemann, Stefan; Behr, Marcel A.; Zumarraga, Martin; Bastida, Ricardo; Huson, Daniel; Nieselt, Kay; Young, Douglas; Parkhill, Julian; Buikstra, Jane E.; Gagneux, Sebastien; Stone, Anne C.; Krause, Johannes

    2015-01-01

    Modern strains of Mycobacterium tuberculosis from the Americas are closely related to those from Europe, supporting the assumption that human tuberculosis was introduced post-contact1. This notion, however, is incompatible with archaeological evidence of pre-contact tuberculosis in the New World2. Comparative genomics of modern isolates suggests that M. tuberculosis attained its worldwide distribution following human dispersals out of Africa during the Pleistocene epoch3, although this has yet to be confirmed with ancient calibration points. Here we present three 1,000-year-old mycobacterial genomes from Peruvian human skeletons, revealing that a member of the M. tuberculosis complex caused human disease before contact. The ancient strains are distinct from known human-adapted forms and are most closely related to those adapted to seals and sea lions. Two independent dating approaches suggest a most recent common ancestor for the M. tuberculosis complex less than 6,000 years ago, which supports a Holocene dispersal of the disease. Our results implicate sea mammals as having played a role in transmitting the disease to humans across the ocean. PMID:25141181

  10. Sealing device

    Science.gov (United States)

    Garcia-Crespo, Andres Jose

    2013-12-10

    A sealing device for sealing a gap between a dovetail of a bucket assembly and a rotor wheel is disclosed. The sealing device includes a cover plate configured to cover the gap and a retention member protruding from the cover plate and configured to engage the dovetail. The sealing device provides a seal against the gap when the bucket assemply is subjected to a centrifugal force.

  11. Development of unfolding method to obtain pin-wise source strength distribution from PWR spent fuel assembly measurement

    International Nuclear Information System (INIS)

    Sitompul, Yos Panagaman; Shin, Hee-Sung; Park, Se-Hwan; Oh, Jong Myeong; Seo, Hee; Kim, Ho Dong

    2013-01-01

    An unfolding method has been developed to obtain a pin-wise source strength distribution of a 14 × 14 pressurized water reactor (PWR) spent fuel assembly. Sixteen measured gamma dose rates at 16 control rod guide tubes of an assembly are unfolded to 179 pin-wise source strengths of the assembly. The method calculates and optimizes five coefficients of the quadratic fitting function for X-Y source strength distribution, iteratively. The pin-wise source strengths are obtained at the sixth iteration, with a maximum difference between two sequential iterations of about 0.2%. The relative distribution of pin-wise source strength from the unfolding is checked using a comparison with the design code (Westinghouse APA code). The result shows that the relative distribution from the unfolding and design code is consistent within a 5% difference. The absolute value of the pin-wise source strength is also checked by reproducing the dose rates at the measurement points. The result shows that the pin-wise source strengths from the unfolding reproduce the dose rates within a 2% difference. (author)

  12. Spent 99Mo/99mTc generator as an economical source of 99Mo

    International Nuclear Information System (INIS)

    El-Kolaly, M.T.

    1990-01-01

    An improved method for utilization and purification of 99 Mo from spent 90 Mo/ 99m Tc generators has been described. After washing the generator with saline to remove the generated 99m Tc, followed by 2 mL 5 M NaOH containing a few drops of H 2 O 2 , the 99 Mo was quantitatively eluted from the generator with 5 mL 5 M NaOH. The alkaline eluate containing 99 Mo was contaminated with partially dissolved alumina. In the present method, an anion-exchange resin Dowex 1 x 8 column was used for purification of 99 Mo from the contaminating alumina. The resultant 99 Mo was of high purity and contained 3+ /mL 99 Mo solution, as estimated by atomic absorption. (author)

  13. Production of the sealed gamma-radiation sources of with iridium-192 radionuclide at the WWR-K research reactor

    International Nuclear Information System (INIS)

    Petukhov, V.K.; Chernayev, V.P.; Chabeyev, N.T.; Ermakov, E.L.; Chakrov, P.V.

    2005-01-01

    Full text: Conversion orientation of the WWR-K research reactor activity was established after renewal of its operation in 1997. A priority in reactor works was determined in the decision of tasks of practical use of nuclear technologies in a national economy in the next directions: in an industry, public health services and agriculture. The items of prime tasks: development and introduction of radiation technologies and manufacturing of radioisotopes for industry. This task included both scientific and technical program in the list of works of the Republican goals. At the WWR-K reactor within the framework of the this task solution the works on pilot production of the sealed sources of radioactive radiations (SSRR) with Ir-192 radionuclide for an industry of Republic of Kazakhstan were made. Organizational questions related to the Kazakhstan authority body and the regulating documentation were solved the first of all. The second stage was the development of the techniques of creating of devices providing an samples irradiation in reactor, control of sources sealing, measurements of the equivalent radiation doze from sources and high-quality support of SSRR manufacture over all technological way. At the third stage was made a little quantity SSRR with Ir-192 radionuclide, such as GIID-A1 (G6), for 'TEKOPS-660' Gammaray Projectors. This work served as experimental check of the decisions correctness, and has allowed to remove those lacks, to find out which it was possible only during direct manufacturing of radioactive sources. During performance of all these works the following was carried out: development and release of the documents and specifications regulating work on SSRR manufacture at the Institute of Nuclear Physics; personnel preparation and certification; preparation and equipment providing of reactor hot chambers by additional devices for work with irradiated iridium samples; development and manufacturing of the devices for iridium samples irradiation in

  14. Industrial meters with sealed sources: an overview of the situation in Argentina

    International Nuclear Information System (INIS)

    Cateriano, Miguel A.; Truppa, Walter A.

    2003-01-01

    During 2002 the Argentine Nuclear Regulatory Authority decided that it should audit all the owners of licenses to operate industrial meters to verify the sources declared by the users and to evaluate the radiological safety of the installations within the regulatory framework as well as the safety of the sources. This audit has taken place at a national level and included all users that own industrial meters. Almost 380 facilities were inspected in 60 days. An ad-hoc committee was created to achieve this goal; it was made up of 5 groups of three inspectors each who were distributed along different areas of the country where the facilities operate. The knowledge of the situation is an important tool that allows a better planning of the source control policy in order to prevent radiological emergency situations in which radioactive sources might be involved. In this paper the satisfactory results of the audits are presented. No orphan sources were detected. The anomalies found and all the actions taken to early correct these anomalies are described. Additionally, an updated description of the situation concerning all the users of industrial meters is presented. Their distribution per province, an inventory of sources and equipment as well as the number of licenses and individual authorizations are also shown in this paper. (author)

  15. Radiation protection: data sheets for use of 11C, 18F, 22Na, 24Na, 33P, 35S, 36Cl, 45Ca in non sealed sources

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    These data sheets give the essential datas for the use of non sealed radioactive sources They are made for users in view of their radiation protection and give the administrative procedures, the radiation protection procedures and equipments to be used in function of the activity

  16. Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Stewart, L.; Tonkay, D.

    2004-01-01

    This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste

  17. Reclamation of greater than Class C sealed sources at the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Behrens, R.G.; Jones, S.W.

    1995-01-01

    One of the important overriding themes of the Los Alamos National Laboratory as a world-class scientific institution is to utilize its expertise in enhancing the long-term welfare of society by minimizing negative side effects of nuclear technology over the past five decades. The Los Alamos National Laboratory is therefore committed to the use of its technical competencies and nuclear facilities, developed through programs in the areas of defense and civilian nuclear research, to support activities which will benefit the United States as a whole. As such, this paper discusses the organizational details and requirements of the Neutron Source Reclamation Program at Los Alamos. This program has as its mission the retrieval, interim storage, and chemical reprocessing of 238 PuBe, 239 PuBe and 24l AmBe neutron sources residing in the hands of private companies and industries, academic institutions, and various state and Federal government agencies

  18. Security seal

    Science.gov (United States)

    Gobeli, Garth W.

    1985-01-01

    Security for a package or verifying seal in plastic material is provided by a print seal with unique thermally produced imprints in the plastic. If tampering is attempted, the material is irreparably damaged and thus detectable. The pattern of the imprints, similar to "fingerprints" are recorded as a positive identification for the seal, and corresponding recordings made to allow comparison. The integrity of the seal is proved by the comparison of imprint identification records made by laser beam projection.

  19. Seal arrangement

    International Nuclear Information System (INIS)

    Dempsey, J.D.

    1978-01-01

    A hydraulically balanced face type shaft seal is provided in which the opening and closing seal face areas retain concentricity with each other in the event of lateral shaft displacement. The seal arrangement is for a vertical high pressure pump, indented for use in the cooling system of a nuclear reactor. (Auth.)

  20. Environmental radiation control and quality management system in design and operation of sealed radioactive sources

    International Nuclear Information System (INIS)

    Hussein, A.Z.

    2007-01-01

    New environmental regulations and radiation safety standards are being implemented almost daily to ensure radiation safety, in particular for practices causing exposures to undue radiation doses. A particular emphasis of real challenge for organizations and users of radiation sources has to be for proper radiological safety assessment and is becoming cost effectively to be prepared for auditing. Special concern for the environment is of global . nature, and hence environmental auditing has been and will continue to be an essential practice for improving the environment and for meeting the relevant regulations and standards. In general, most facilities that deal with radioactive sources undertake strict safety measures in terms of personnel radiation protection, handling procedures and security. Hence, those measures should comply with the requirements of the environmental protection standards. Accordingly, a successful quality management system must balance realities of organization and personnel in achieving quality objectives. Organizational principles are found in the technical aspects of' quality management, such as, charting, requirements, measurements, procedures, ... , etc. Human principles are found in the communication side of quality management (e.g. meetings, ,decision making, ,teams, ... , etc). The quality management must understand and balance skills needed to blend them together. Large gamma irradiators present a high potential radiation hazard to the surrounding environment, since the amount of radioactivity is of the order of (P Bq) and a very high dose rates are produced during irradiation. Application of environmental radiation control deemed by regulatory authority and a proper quality management system by the utility would serve public health and safety

  1. Data Bank of Nuclear and Radiological Regulatory Authority, Part 2 . Software Package of Statistical Data of Sealed Sources

    International Nuclear Information System (INIS)

    Lashin, R.M.A.; Mahmoud, N.S.; Lashin, M.M.A.

    2012-01-01

    Protection of human, property and the environment is the main concern considered as a principal goal to form the Egyptian Nuclear and Radiological Regulatory Authority. That requires a lot of work, efforts, knowledge and aids for right and quick decision making. Internationally, the International Atomic Energy Agency (IAEA) developed a protection system for control and accounts the radioactive materials for the safe use and transport. Moreover, the protection system can prevent the theft of these materials or their use in terrorism. Here in, all radioactive sources shall be subjected to instructions, serious regulations and laws. In order to exercise these functions, it is necessary to accurately establish the appropriate information system to the regulatory body. This system must depend on using a modern technology to perform the work in most accurate and fullest manner in a Data Bank [1, 2]. The present work is the second part performed for the data bank, which consists of two parts: first part is concern about the open sources which executed before [3]. Second part is deal with the sealed sources. Describing here consolidated guidance help materials licenses. It also provides reviewers of such requests with the information and materials necessary to determine that the products are acceptable for licensing purposes. It provides the applicants and reviewers with information concerning how to file a request, a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, administrative procedures to be followed, information on how to perform the evaluation and write a registration certificate, and the responsibilities of the registration certificate holder.

  2. General information on licensing process in Bulgaria and disused sealed sources

    International Nuclear Information System (INIS)

    Nizamska, M.

    2003-01-01

    The basic legal framework for radiation protection and the safety of radiation sources is given in the report. The authorisation process is described. Actual data for the system of authorisation about SIR during 2002/2003 are given. The planned activities related to RAW management are:commissioning of the complex for treatment, conditioning and storage of RAW in Kozloduy NPP - by the end of 2003; investigation of Gabra site for construction of institutional waste disposal facility - by the end of 2004; implementation of program for reconstruction and modernisation of Novi Han Repository - by the end of 2007; site selection for the national RAW disposal facility - by the end of 2008. The Nuclear Energy Act defines the following future activities: establishment of the State Enterprise 'RAW' in 2004; development of new secondary legislation for safe management of SF and RAW until July 2004; update of the National Strategy for Safe Management of SF and RAW until the end of 2003

  3. Calculation of source term in spent PWR fuel assemblies for dry storage and shipping cask design

    International Nuclear Information System (INIS)

    Fernandez, J. L.; Lopez, J.

    1986-01-01

    Using the ORIGEN-2 Coda, the decay heat and neutron and photon sources for an irradiated PWR fuel element have been calculated. Also, parametric studies on the behaviour of the magnitudes with the burn-up, linear heat power and irradiation and cooling times were performed. Finally, a comparison between our results and other design calculations shows a good agreement and confirms the validity of the used method. (Author) 6 refs

  4. Nozzle seal

    International Nuclear Information System (INIS)

    Herman, R.F.

    1977-01-01

    In an illustrative embodiment of the invention, a nuclear reactor pressure vessel, having an internal hoop from which the heated coolant emerges from the reactor core and passes through to the reactor outlet nozzles, is provided with sealing members operatively disposed between the outlet nozzle and the hoop. The sealing members are biased against the pressure vessel and the hoop and are connected by a leak restraining member establishing a leak-proof condition between the inlet and outlet coolants in the region about the outlet nozzle. Furthermore, the flexible responsiveness of the seal assures that the seal will not structurally couple the hoop to the pressure vessel

  5. Nozzle seal

    International Nuclear Information System (INIS)

    Walling, G.A.

    1977-01-01

    In an illustrative embodiment of the invention, a nuclear reactor pressure vessel, having an internal hoop from which the heated coolant emerges from the reactor core and passes through to the reactor outlet nozzles, is provided with sealing rings operatively disposed between the outlet nozzles and the hoop. The sealing rings connected by flexible members are biased against the pressure vessel and the hoop, establishing a leak-proof condition between the inlet and outlet coolants in the region about the outlet nozzle. Furthermore, the flexible responsiveness of the seal assures that the seal will not structurally couple the hoop to the pressure vessel. 4 claims, 2 figures

  6. Ceramic Seal.

    Energy Technology Data Exchange (ETDEWEB)

    Smartt, Heidi A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Romero, Juan A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Custer, Joyce Olsen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hymel, Ross W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Krementz, Dan [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Gobin, Derek [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Harpring, Larry [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Martinez-Rodriguez, Michael [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Varble, Don [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); DiMaio, Jeff [Tetramer Technologies, Pendleton, SC (United States); Hudson, Stephen [Tetramer Technologies, Pendleton, SC (United States)

    2016-11-01

    Containment/Surveillance (C/S) measures are critical to any verification regime in order to maintain Continuity of Knowledge (CoK). The Ceramic Seal project is research into the next generation technologies to advance C/S, in particular improving security and efficiency. The Ceramic Seal is a small form factor loop seal with improved tamper-indication including a frangible seal body, tamper planes, external coatings, and electronic monitoring of the seal body integrity. It improves efficiency through a self-securing wire and in-situ verification with a handheld reader. Sandia National Laboratories (SNL) and Savannah River National Laboratory (SRNL), under sponsorship from the U.S. National Nuclear Security Administration (NNSA) Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D), have previously designed and have now fabricated and tested Ceramic Seals. Tests have occurred at both SNL and SRNL, with different types of tests occurring at each facility. This interim report will describe the Ceramic Seal prototype, the design and development of a handheld standalone reader and an interface to a data acquisition system, fabrication of the seals, and results of initial testing.

  7. Ceramic Seal

    International Nuclear Information System (INIS)

    Smartt, Heidi A.; Romero, Juan A.; Custer, Joyce Olsen; Hymel, Ross W.; Krementz, Dan; Gobin, Derek; Harpring, Larry; Martinez-Rodriguez, Michael; Varble, Don; DiMaio, Jeff; Hudson, Stephen

    2016-01-01

    Containment/Surveillance (C/S) measures are critical to any verification regime in order to maintain Continuity of Knowledge (CoK). The Ceramic Seal project is research into the next generation technologies to advance C/S, in particular improving security and efficiency. The Ceramic Seal is a small form factor loop seal with improved tamper-indication including a frangible seal body, tamper planes, external coatings, and electronic monitoring of the seal body integrity. It improves efficiency through a self-securing wire and in-situ verification with a handheld reader. Sandia National Laboratories (SNL) and Savannah River National Laboratory (SRNL), under sponsorship from the U.S. National Nuclear Security Administration (NNSA) Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D), have previously designed and have now fabricated and tested Ceramic Seals. Tests have occurred at both SNL and SRNL, with different types of tests occurring at each facility. This interim report will describe the Ceramic Seal prototype, the design and development of a handheld standalone reader and an interface to a data acquisition system, fabrication of the seals, and results of initial testing.

  8. Electronic seal

    International Nuclear Information System (INIS)

    Musyck, E.

    1981-01-01

    An electronic seal is presented for a volume such as container for fissile materials. The seal encloses a lock for barring the space as well as a device for the detection and the recording of the intervention of the lock. (AF)

  9. Ferrules seals

    Science.gov (United States)

    Smith, J.L.

    1984-07-10

    A device is provided for sealing an inner tube and an outer tube without excessively deforming the tubes. The device includes two ferrules which cooperate to form a vacuum-tight seal between the inner tube and outer tube and having mating surfaces such that overtightening is not possible. 3 figs.

  10. An Investigation into Spent Coffee Waste as a Renewable Source of Bioactive Compounds and Industrially Important Sugars

    Directory of Open Access Journals (Sweden)

    Damhan S. Scully

    2016-11-01

    Full Text Available Conventional coffee brewing techniques generate vast quantities of spent espresso grounds (SEGs rich in lignocellulose and valuable bioactives. These bioactive compounds can be exploited as a nutraceutical or used in a range of food products, while breakdown of lignocellulose generates metabolizable sugars that can be used for the production of various high-value products such as biofuels, amino acids and enzymes. Response surface methodology (RSM was used to optimize the enzymatic saccharification of lignocellulose in SEGs following a hydrothermal pretreatment. A maximum reducing sugar yield was obtained at the following optimized hydrolysis conditions: 4.97 g of pretreated SEGs, 120 h reaction time, and 1246 and 250 µL of cellulase and hemicellulase, respectively. Industrially important sugars (glucose, galactose and mannose were identified as the principal hydrolysis products under the studied conditions. Total flavonoids (p = 0.0002, total polyphenols (p = 0.03 and DPPH free-radical scavenging activity (p = 0.004 increased significantly after processing. A 14-fold increase in caffeine levels was also observed. This study provides insight into SEGs as a promising source of industrially important sugars and polyphenols.

  11. Sealing devices

    International Nuclear Information System (INIS)

    Coulson, R.A.

    1980-01-01

    A sealing device for minimising the leakage of toxic or radioactive contaminated environments through a biological shield along an opening through which a flexible component moves that penetrates the shield. The sealing device comprises an outer tubular member which extends over a length not less than the maximum longitudinal movement of the component along the opening. An inner sealing block is located intermediate the length of the component by connectors and is positioned in the bore of the outer tubular member to slide in the bore and effect a seal over the entire longitudinal movement of the component. The cross-section of the device may be circular and the block may be of polytetrafluoroethylene or of nylon impregnated with molybdenum or may be metallic. A number of the sealing devices may be combined into an assembly for a plurality of adjacent longitudinally movable components, each adapted to sustain a tensile load, providing the various drives of a master-slave manipulator. (author)

  12. Evaluation of source term parameters for spent fuel disposal in foreign countries. (2) Dissolution rates of spent fuel matrices and construction materials for fuel assemblies

    International Nuclear Information System (INIS)

    Kitamura, Akira; Chikazawa, Takahiro; Tachi, Yukio; Akahori, Kuniaki

    2016-01-01

    The Japanese geological disposal program has started researching disposal of spent nuclear fuel (SF) in deep geological strata (hereafter 'direct disposal of SF') as an alternative management option other reprocessing followed by vitrification and geological disposal of high-level radioactive waste. We conducted literature survey of dissolution rate of SF matrix and constructing materials (e.g. zircaloy cladding and control rods) selected in safety assessment reports for direct disposal of SF in Europe and United States. We also investigated basis of release rate determination and assignment of uncertainties in the safety assessment reports. Furthermore, we summarized major conclusions proposed by some European projects governed by European Commission. It was found that determined release rates are fairly similar to each other due to use of similar literature data in all countries of interest. It was also found that the determined release rates were including conservativeness because it was difficult to assign uncertainties quantitatively. It is expected that these findings are useful as fundamental information for determination of the release rates for the safety assessment of Japanese SF disposal system. (author)

  13. The development of a mobile hot cell facility for the conditioning of spent high activity radioactive sources (SHARS)

    International Nuclear Information System (INIS)

    Liebenberg, G.R.; Al-Mughrabi, M.

    2008-01-01

    The International Atomic Energy Agency (IAEA) Waste Technology Section with additional support from the U.S. National Nuclear Security Agency (NNSA) through the IAEA Nuclear Security Fund has funded the design, fabrication, evaluation, and testing of a portable hot cell intended to address the problem of disused SHARS in obsolete irradiation devices such as teletherapy heads and dry irradiators. The project is initially targeting the African continent but expected soon to expand to Latin America and Asia. This hot cell would allow source removal, characterization, consolidation, repackaging in modern storage shields, and secure storage of high risk SHARS at single sites in each IAEA Member State. The mobile hot cell and related equipment is transported in two shipping containers to a specific country where the following process takes place: 1-) Assembly of hot cell; 2-) Removal of SHARS from working shields, encapsulation into a stainless steel capsule and placement into a long term storage shield; 3-) Conditioning of any other spent sources the country may require; 4-) Dismantling of the hot cell; 5-) Shipping equipment out of country. The operation in a specific country is planned to be executed over a three week period. This presentation will discuss the development of the mobile hot cell facility as well as the demonstration of the state of readiness of the system for manipulation of SHARS and the planned execution of the conditioning operations. As a result of this project, excess SHARS could be managed safely and securely and possibly be more easily repatriated to their country of origin for appropriate final disposition. (author)

  14. 30 CFR 75.337 - Construction and repair of seals.

    Science.gov (United States)

    2010-07-01

    ... sealed areas. (b) Prior to sealing, the mine operator shall— (1) Remove insulated cables, batteries, and other potential electric ignition sources from the area to be sealed when constructing seals, unless it... after April 18, 2008, the seal at the lowest elevation shall have a corrosion-resistant, non-metallic...

  15. Conditioning of low level radioactive wastes, spent radiation sources and their transport at the interim storage building of the Institute of Nuclear Physics in Albania

    International Nuclear Information System (INIS)

    Qafmolla, L.

    2000-01-01

    Aspects of treatment and management of radioactive wastes resulting from the use of radiation sources and radioisotopes in research, medicine and industry, are described. The methods applied for the conditioning of low-level radioactive wastes and spent radiation sources are simple. Solid radioactive wastes with low-level activity, after accumulation, minimization, segregation and measurement, are burned or compressed in a simple compactor of the PGS type. Spent radiation sources are placed into 200 l drums, are cemented and conditioned. Conditioned drums from the Radiation Protection Division of the Institute of Nuclear Physics (INP), which is the responsible Institution for the treatment and management of radioactive wastes in Albania, are transported to the interim storage building of the Institute of Nuclear Physics in Tirana. Work to construct a new building for treatment and management of radioactive wastes and spent radiation sources within the territory of INP is underway. Funds have been allocated accordingly: based on the Law No. 8025 of 25.11.1995, it is the Albanian Government's responsibility to finance activities concerned with the treatment and management of radioactive wastes generating from the use of ionizing radiation in science, medicine and industry in the country. (author)

  16. Generation projection of solid and liquid radioactive wastes and spent radioactive sources in Mexico; Proyeccion de generacion de desechos radiactivos solidos, liquidos y fuentes radiactivas gastadas en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Garcia A, E.; Hernandez F, I. Y.; Fernandez R, E. [Universidad Politecnica del Valle de Toluca, Km 5.7 Carretera Almoloya de Juarez, Estado de Mexico (Mexico); Monroy G, F.; Lizcano C, D., E-mail: fabiola.monroy@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    This work is focused to project the volumes of radioactive aqueous liquid wastes and spent radioactive sources that will be generated in our country in next 15 years, solids compaction and radioactive organic liquids in 10 years starting from the 2014; with the purpose of knowing the technological needs that will be required for their administration. The methodology involves six aspects to develop: the definition of general objectives, to specify the temporary horizon of projection, data collection, selection of the prospecting model and the model application. This approach was applied to the inventory of aqueous liquid wastes, as well as radioactive compaction organic and solids generated in Mexico by non energy applications from the 2001 to 2014, and of the year 1997 at 2014 for spent sources. The applied projection models were: Double exponential smoothing associating the tendency, Simple Smoothing and Lineal Regression. For this study was elected the first forecast model and its application suggests that: the volume of the compaction solid wastes, aqueous liquids and spent radioactive sources will increase respectively in 152%, 49.8% and 55.7%, while the radioactive organic liquid wastes will diminish in 13.15%. (Author)

  17. Upgrading inflatable door seals

    International Nuclear Information System (INIS)

    Sykes, T.M.; Metcalfe, R.; Welch, L.A.; Josefowich, J.M.

    1997-01-01

    Inflatable door seals are used for airlocks in CANDU stations. They have been a significant source of unreliability and maintenance cost. A program is underway to improve their performance and reliability, backed by environmental qualification testing. Only commercial products and suppliers existed in 1993. For historical reasons, these 'existing products' did not use the most durable material then available. In hindsight, neither had they been adapted nor optimized to combat conditions often experienced in the plants-sagging doors, damaged sealing surfaces, and many thousands of openings and closings per year. Initial attempts to involve the two existing suppliers in efforts to upgrade these seals were unsuccessful. Another suitable supplier had therefore to be found, and a 'new,' COG-owned seal developed; this was completed in 1997. This paper summarizes its testing, along with that of the two existing products. Resistance to aging has been improved significantly. Testing has shown that an accident can be safely withstood after 10 years of service or 40,000 openings-closings, whichever comes first. AECL's Fluid Sealing Technology Unit (FSTU) has invested in the special moulds, test fixtures and other necessary tooling and documentation required to begin commercial manufacture of this new quality product. Accordingly, as with FSTU's other nuclear products such as pump seals, the long-term supply of door seals to CANDU plants is now protected from many external uncertainties-e.g., commercial products being discontinued, materials being changed, companies going out of business. Manufacturing to AECL's detailed specifications is being subcontracted to the new supplier. FSTU is performing the quality surveillance, inspection, testing, and customer service activities concomitant with direct responsibility for supply to the plants. (author)

  18. Neutron Generators for Spent Fuel Assay

    International Nuclear Information System (INIS)

    Ludewigt, Bernhard A.

    2010-01-01

    The Next Generation Safeguards Initiative (NGSI) of the U.S. DOE has initiated a multi-lab/university collaboration to quantify the plutonium (Pu) mass in, and detect the diversion of pins from, spent nuclear fuel (SNF) assemblies with non-destructive assay (NDA). The 14 NDA techniques being studied include several that require an external neutron source: Delayed Neutrons (DN), Differential Die-Away (DDA), Delayed Gammas (DG), and Lead Slowing-Down Spectroscopy (LSDS). This report provides a survey of currently available neutron sources and their underlying technology that may be suitable for NDA of SNF assemblies. The neutron sources considered here fall into two broad categories. The term 'neutron generator' is commonly used for sealed devices that operate at relatively low acceleration voltages of less than 150 kV. Systems that employ an acceleration structure to produce ion beam energies from hundreds of keV to several MeV, and that are pumped down to vacuum during operation, rather than being sealed units, are usually referred to as 'accelerator-driven neutron sources.' Currently available neutron sources and future options are evaluated within the parameter space of the neutron generator/source requirements as currently understood and summarized in section 2. Applicable neutron source technologies are described in section 3. Commercially available neutron generators and other source options that could be made available in the near future with some further development and customization are discussed in sections 4 and 5, respectively. The pros and cons of the various options and possible ways forward are discussed in section 6. Selection of the best approach must take a number of parameters into account including cost, size, lifetime, and power consumption, as well as neutron flux, neutron energy spectrum, and pulse structure that satisfy the requirements of the NDA instrument to be built.

  19. Treatment of spent ion-exchange resins in shaft-type reactor with fuel-plasma source of heating

    International Nuclear Information System (INIS)

    Dmitriev, S. A.; Knyazev, I. A.; Lifanov, F. A.; Polkanov, M. A.; Shvetsov, S. Yu; Savkin, A. E.

    1999-01-01

    The method of high-temperature conditioning the spent radioactive ion-exchange resins in combination with other combustible and incombustible radioactive waste in the plasma shaft furnace with obtaining a crystalline glass-like matrix as a final product has been developed. The method was tested on the pilot plant consisted of ceramic plasma melter, steel water-cooled shaft furnace, lined by fire-resistant concrete, and system of gas purification. The capacity of the furnace was within the limits from 10 to 15 kg/h. The volume and mass reduction factors of treated waste were 36 and 7.6, accordingly. The content of gaseous products of thermal decomposition of a waste at an output of the shaft furnace and properties of obtained slag compound were determined. Based on test results the proposals on creation of compact plasma plant for treatment of mixed radioactive waste including spent ion exchange resins were developed. (author). 3 refs., 2 tabs., 2 figs

  20. Source study for a concept of spent nuclear fuel and radioactive waste management in the Czech Republic

    International Nuclear Information System (INIS)

    Vokal, A.; Trtilek, R.; Tarasova, J.; Popelova, E.; Podlaha, J.; Krmela, J.; Vojtechova, H.; Uhlir, J.

    2013-02-01

    The sections of the study are as follows: Purpose of the study; Basic principles of peaceful uses of nuclear energy and spent nuclear fuel and radioactive waste management; Basic starting facts and assumptions and assessment of the fulfilment of the targets; Low-level and medium-level radioactive waste management; Management of spent nuclear fuels and wastes not admitted to near-surface repositories; Description of / proposal for the methodology of transparency policy and proposal for a method to involve the entities affected, including municipalities and the public; Current financial arrangements (reserves for decommissioning, nuclear account); Refinement/modification of the plans and technical solutions; Proposed schedule and milestones for attaining the targets; Proposal for a research and development programme; Assessment of the costs of implementation of the targets. (P.A.)

  1. Containing method for spent fuel and spent fuel containing vessel

    International Nuclear Information System (INIS)

    Maekawa, Hiromichi; Hanada, Yoshine.

    1996-01-01

    Upon containing spent fuels, a metal vessel main body and a support spacer having fuel containing holes are provided. The support spacer is disposed in the inside of the metal vessel main body, and spent fuel assemblies are loaded in the fuel containing holes. Then, a lid is welded at the opening of the metal vessel main body to provide a sealing state. In this state, heat released from the spent fuel assemblies is transferred to the wall of the metal vessel main body via the support spacer. Since the support spacer has a greater heat conductivity than gases, heat of the spent fuel assemblies tends to be released to the outside, thereby capable of removing heat of the spent fuel assemblies effectively. In addition, since the surfaces of the spent fuel assemblies are in contact with the inner surface of the fuel containing holes of the support spacer, impact-resistance and earthquake-resistance are ensured, and radiation from the spent fuel assemblies is decayed by passing through the layer of the support spacer. (T.M.)

  2. Spent Fuel Dissolution and Source Term Modelling in Safety Assessment. Report from a Workshop. Synthesis and extended abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-05-15

    This report describes a workshop that was organised by the Swedish Nuclear Power Inspectorate (SKI) for assessment of the handling of near-field radionuclide retention processes by the Swedish Nuclear Fuel and Waste Management Company (SKB). The general objective with this type of meeting is to improve the knowledge and awareness of recent developments and to provide preliminary review comments. A number of SKB reports provided the general background for the workshop discussions. One report addresses the release of radionuclides from spent fuel, another the concentration limits related to radionuclide solubility and a third buffer radionuclide sorption and migration parameters. These reports comprise a basis for the handling of the spent fuel, solubility and sorption processes in new complete safety assessment SR-Can. The discussion and analysis of these background reports at the workshop therefore provide an essential element of preparation for the planned review of SR-Can. The review comments provided in this report are nonetheless of a preliminary character since the SR-Can report was not available at the time of the workshop and details about the incorporation of various potential safety features into the entirety of safety assessment were not known. The present report sets out the detailed objectives and format of the workshop in Section 2. Section 3 provides a high-level overview of processes that need to be taken into account. In Section 4, there is a brief discussion about the chemical and physical environment near the engineered barriers. Section 5 gives a more detailed description of spent fuel processes that affect the radionuclide releases. In Section 6, the key issues for radionuclide chemistry and the estimation of concentration limits for various radionuclides are discussed. Section 7 discusses radionuclide sorption and migration in the buffer and Section 8 presents overall conclusions from the workshop.

  3. TMI-2 spent fuel shipping

    International Nuclear Information System (INIS)

    Quinn, G.J.; Burton, H.M.

    1985-01-01

    TMI-2 failed fuel will be shipped to the Idaho National Engineering Laboratory for use in the DOE Core Examination Program. The fuel debris will be loaded into three types of canisters during defueling and dry loaded into a spent fuel shipping cask. The cask design accommodates seven canisters per cask and has two separate containment vessels with ''leaktight'' seals. Shipments are expectd to begin in early 1986

  4. Modular design of processing and storage facilities for small volumes of low and intermediate level radioactive waste including disused sealed sources

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-06-15

    A number of IAEA Member States generate relatively small quantities of radioactive waste and/or disused sealed sources in research or in the application of nuclear techniques in medicine and industry. This publication presents a modular approach to the design of waste processing and storage facilities to address the needs of such Member States with a cost effective and flexible solution that allows easy adjustment to changing needs in terms of capacity and variety of waste streams. The key feature of the publication is the provision of practical guidance to enable the users to determine their waste processing and storage requirements, specify those requirements to allow the procurement of the appropriate processing and storage modules and to install and eventually operate those modules.

  5. Characterization of a sealed Americium-Beryllium (AmBe) source by inductively coupled plasma mass spectrometry

    International Nuclear Information System (INIS)

    Sommers, J.; Jimenez, M.; Adamic, M.; Giglio, J.; Carney, K.

    2009-01-01

    Two Americium-Beryllium neutron sources were dismantled, sampled (sub-sampled) and analyzed via inductively coupled plasma mass spectrometry (ICP-MS). Characteristics such as 'age' since purification, actinide content, trace metal content and inter and intra source composition were determined. The 'age' since purification of the two sources was determined to be 25.0 and 25.4 years, respectively. The systematic uncertainties in the 'age' determination were ±4% 2σ. The amount and isotopic composition of U and Pu varied substantially between the sub-samples of Source 2 (n = 8). This may be due to the physical means of sub-sampling or the way the source was manufactured. Source 1 was much more consistent in terms of content and isotopic composition (n = 3 sub-samples). The Be-Am ratio varied greatly between the two sources. Source 1 had an Am-Be ratio of 6.3 ± 52% (1σ). Source 2 had an Am-Be ratio of 9.81 ± 3.5% (1σ). In addition, the trace element content between the samples varied greatly. Significant differences were determined between Sources 1 and 2 for Sc, Sr, Y, Zr, Mo, Ba and W. (author)

  6. Resistance to radiation and concretes thermal cycles for conditioning of spent radioactive sources; Resistencia a la irradiacion y ciclos termicos de concretos para acondicionamiento de fuentes radiactivas gastadas

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez N, M.; Monroy G, F.; Gonzalez D, R. C.; Corona P, I. J.; Ortiz A, G., E-mail: fabiola.monroy@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    In order to know the concrete type most suitable for use as a matrix of conditioning of spent radioactive sources, concrete test tubes using 4 different types of cement were prepared: CPC 30-Rs Extra, CPC 30-R Impercem, CPC 30-R Rs and CPC 30-R with two gravel sizes >30 mm and <10 mm. The concrete test tubes were subjected to testing compressive strength after 28 days of hardening and after being irradiated and subjected to thermal cycles. Subsequently they were characterized by X-ray diffraction and scanning electron microscopy, in order to evaluate whether these concretes accredited the tests set by the NOM-019-Nucl-1995. The results show that the compressive strength of the hardened concretes to 28 days presents values between 36 and 25 MPa; applying irradiation the resistance may decrease to 30% of its original strength; and if subjected to high and low temperatures the ettringite formation also causes a decrease in resistance. The results show that concretes made from cement Impercem, Cruz Azul with gravel <10 mm comply with the provisions of standard and they can be used for conditioning of spent radioactive sources. (Author)

  7. Spent fuel management

    International Nuclear Information System (INIS)

    2005-01-01

    The production of nuclear electricity results in the generation of spent fuel that requires safe, secure and efficient management. Appropriate management of the resulting spent fuel is a key issue for the steady and sustainable growth of nuclear energy. Currently about 10,000 tonnes heavy metal (HM) of spent fuel are unloaded every year from nuclear power reactors worldwide, of which 8,500 t HM need to be stored (after accounting for reprocessed fuel). This is the largest continuous source of civil radioactive material generated, and needs to be managed appropriately. Member States have referred to storage periods of 100 years and even beyond, and as storage quantities and durations extend, new challenges arise in the institutional as well as in the technical area. The IAEA gives high priority to safe and effective spent fuel management. As an example of continuing efforts, the 2003 International Conference on Storage of Spent Fuel from Power Reactors gathered 125 participants from 35 member states to exchange information on this important subject. With its large number of Member States, the IAEA is well-positioned to gather and share information useful in addressing Member State priorities. IAEA activities on this topic include plans to produce technical documents as resources for a range of priority topics: spent fuel performance assessment and research, burnup credit applications, cask maintenance, cask loading optimization, long term storage requirements including records maintenance, economics, spent fuel treatment, remote technology, and influence of fuel design on spent fuel storage. In addition to broader topics, the IAEA supports coordinated research projects and technical cooperation projects focused on specific needs

  8. Production techniques and quality control of sealed radioactive sources of palladium-103, iodine-125, iridium-192 and ytterbium-169. Final report of a coordinated research project 2001-2005

    International Nuclear Information System (INIS)

    2006-06-01

    Radioisotopes have been used extensively for many years for several medical and industrial applications either in the form of an open source or encapsulated in an appropriate metallic container (sealed source). The design and technology for the preparation of radioactive sealed sources is an area of continuous development to satisfy an ever increasing demand for a larger variety of shapes, sizes, type of radioisotope and levels of radioactivity required for newer and specialized applications. In medicine, sealed sources using the radioisotopes of 125 I, 192 Ir and 103 Pd are commonly used for brachytherapy for the treatment of malignant diseases, and for bone density measurements. In industry, they are widely used for non-destructive testing (NDT), radiation processing, 'on-line' process control systems and on-line elemental analysis of mineral resources. Some well-known examples of such sources are 60 Co for industrial nucleonic gauges, 192 Ir sources for industrial radiography, 241 Am sources for smoke detectors and chemical analysers and, more recently, 169 Yb for NDT measurements of thin metallic tubes and plates. The current challenges in development include the production of miniature size sources with a high level of activity, a high degree of uniformity in the distribution of the radioactivity and the highest degree of safety, requiring stringent quality control methods. The IAEA has been promoting and supporting activities designed to increase the utilization of radiation and radioisotopes in several areas. In particular, in view of the proven benefits of, and an increasing demand for radioactive sealed sources for medical and industrial applications, upon the recommendation of several experts, a Coordinated Research Project (CRP) on Development of Radioactive Sources for Emerging Therapeutic and Industrial Applications was begun in 2002. The aim of the CRP was the optimization and testing of procedures and methods for the fabrication and quality control

  9. Globally sourced mineral commodities used in U.S. Navy SEAL gear—An illustration of U.S. net import reliance

    Science.gov (United States)

    Brainard, Jamie; Nassar, Nedal T.; Gambogi, Joseph; Baker, Michael S.; Jarvis, Michael T.

    2018-01-25

    A U.S. Navy SEAL (an acronym for sea, air, land) carries gear containing at least 23 nonfuel mineral commodities for which the United States is greater than 50 percent net import reliant. The graphics display the leading world producers of selected nonfuel mineral commodities used to manufacture U.S. Navy SEAL gear. SEALs are members of the U.S. Navy's special operations forces.

  10. UY 102 standard use of sealed sources in radiation source implants: approve for the Industry Energy and Mining Ministry 28/6/2002 Resolution

    International Nuclear Information System (INIS)

    2002-01-01

    Establish minimal requires for radiological safety applied to use of the solid radio actives sources with therapeutic purposes in application radiation source implants in surface area and intra cavities

  11. K-Basin isolation barrier seal

    International Nuclear Information System (INIS)

    Ruff, E.S.

    1994-10-01

    This report documents various aspects of the design, analysis, procurement, and fabrication of the hydraulic seal on the isolation barriers to be installed in the 100-K Area spent nuclear fuel basin. The isolation barrier is used to keep water in the basin in the event of an earthquake

  12. U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution; Norma UY 105 uso de fuentes radiactivas no selladas en Medicina Nuclear: Aprobada por Resolucion del Ministro de Industria Energia y Mineria de 28/6/2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-28

    Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro.

  13. 10 CFR 171.16 - Annual fees: Materials licensees, holders of certificates of compliance, holders of sealed source...

    Science.gov (United States)

    2010-01-01

    .... 4 Another license includes licenses for extraction of metals, heavy metals, and rare earths. 5 There..., in-situ recovery, heap-leaching, ore buying stations, ion exchange facilities and in-processing of ores containing source material for extraction of metals other than uranium or thorium, including...

  14. Improved circumferential shaft seal

    Science.gov (United States)

    Ludwig, L. P.; Strom, T. N.

    1974-01-01

    Comparative tests of modified and unmodified carbon ring seals showed that addition of helical grooves to conventional segmented carbon ring seals reduced leakage significantly. Modified seal was insensitive to shaft runout and to flooding by lubricant.

  15. Storage of LWR spent fuel in air. Volume 3, Results from exposure of spent fuel to fluorine-contaminated air

    International Nuclear Information System (INIS)

    Cunningham, M.E.; Thomas, L.E.

    1995-06-01

    The Behavior of Spent Fuel in Storage (BSFS) Project has conducted research to develop data on spent nuclear fuel (irradiated U0 2 ) that could be used to support design, licensing, and operation of dry storage installations. Test Series B conducted by the BSFS Project was designed as a long-term study of the oxidation of spent fuel exposed to air. It was discovered after the exposures were completed in September 1990 that the test specimens had been exposed to an atmosphere of bottled air contaminated with an unknown quantity of fluorine. This exposure resulted in the test specimens reacting with both the oxygen and the fluorine in the oven atmospheres. The apparent source of the fluorine was gamma radiation-induced chemical decomposition of the fluoro-elastomer gaskets used to seal the oven doors. This chemical decomposition apparently released hydrofluoric acid (HF) vapor into the oven atmospheres. Because the Test Series B specimens were exposed to a fluorine-contaminated oven atmosphere and reacted with the fluorine, it is recommended that the Test Series B data not be used to develop time-temperature limits for exposure of spent nuclear fuel to air. This report has been prepared to document Test Series B and present the collected data and observations

  16. Storage of LWR spent fuel in air. Volume 3, Results from exposure of spent fuel to fluorine-contaminated air

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, M.E.; Thomas, L.E.

    1995-06-01

    The Behavior of Spent Fuel in Storage (BSFS) Project has conducted research to develop data on spent nuclear fuel (irradiated U0{sub 2}) that could be used to support design, licensing, and operation of dry storage installations. Test Series B conducted by the BSFS Project was designed as a long-term study of the oxidation of spent fuel exposed to air. It was discovered after the exposures were completed in September 1990 that the test specimens had been exposed to an atmosphere of bottled air contaminated with an unknown quantity of fluorine. This exposure resulted in the test specimens reacting with both the oxygen and the fluorine in the oven atmospheres. The apparent source of the fluorine was gamma radiation-induced chemical decomposition of the fluoro-elastomer gaskets used to seal the oven doors. This chemical decomposition apparently released hydrofluoric acid (HF) vapor into the oven atmospheres. Because the Test Series B specimens were exposed to a fluorine-contaminated oven atmosphere and reacted with the fluorine, it is recommended that the Test Series B data not be used to develop time-temperature limits for exposure of spent nuclear fuel to air. This report has been prepared to document Test Series B and present the collected data and observations.

  17. Sealed operation of a rf driven ion source for a compact neutron generator to be used for associated particle imaging.

    Science.gov (United States)

    Wu, Y; Hurley, J P; Ji, Q; Kwan, J W; Leung, K N

    2010-02-01

    We present the recent development of a prototype compact neutron generator to be used in conjunction with the method of associated particle imaging for the purpose of active neutron interrogation. In this paper, the performance and device specifications of these compact generators that employ rf driven ion sources will be discussed. Initial measurements of the generator performance include a beam spot size of 1 mm in diameter and a neutron yield of 2x10(5) n/s with air cooling.

  18. Feasibility of fissile mass assay of spent nuclear fuel using 252Cf-source-driven frequency-analysis

    International Nuclear Information System (INIS)

    Mattingly, J.K.; Valentine, T.E.; Mihalczo, J.T.

    1996-01-01

    The feasibility was evaluated using MCNP-DSP, an analog Monte Carlo transport cod to simulate source-driven measurements. Models of an isolated Westinghouse 17x17 PWR fuel assembly in a 1500-ppM borated water storage pool were used. In the models, the fuel burnup profile was represented using seven axial burnup zones, each with isotopics estimated by the PDQ code. Four different fuel assemblies with average burnups from fresh to 32 GWd/MTU were modeled and analyzed. Analysis of the fuel assemblies was simulated by inducing fission in the fuel using a 252 Cf source adjacent to the assembly and correlating source fissions with the response of a bank of 3 He detectors adjacent to the assembly opposite the source. This analysis was performed at 7 different axial positions on each of the 4 assemblies, and the source-detector cross-spectrum signature was calculated for each of these 28 simulated measurements. The magnitude of the cross-spectrum signature follows a smooth upward trend with increasing fissile material ( 235 U and 239 Pu) content, and the signature is independent of the concentration of spontaneously fissioning isotopes (e.g., 244 Cm) and (α,n) sources. Furthermore, the cross-spectrum signature is highly sensitive to changes in fissile material content. This feasibility study indicated that the signature would increase ∼100% in response to an increase of only 0.1 g/cm 3 of fissile material

  19. A removable optical sealing system for application to international safeguards

    International Nuclear Information System (INIS)

    Martin, R.E.

    1985-06-01

    A removable, optically verifiable sealing system for CANDU spent fuel storage facilities has been developed. The seal is based on the use of unique crystal patterns formed in a pure metal identity/integrity element and has been designed for easy installation and removal using simple tooling. Since the seal is optically verified, a wide range of commercial instruments, including those in use by the IAEA, can be used to verify it. Futhermore, optical verification allows the level of scrutiny to be matched with the degree of confidence required to be confident that spent fuel has not been diverted

  20. Transport of multiassembly sealed canisters

    International Nuclear Information System (INIS)

    Quinn, R.D.; Lehnert, R.A.; Rosa, J.M.

    1992-01-01

    A significant portion of the commercial spent nuclear fuel in dry storage in the US will be stored in multiassembly sealed canisters before the DOE begins accepting fuel from utilities in 1998. This paper reports that it is desirable from economic and ALARA perspectives to transfer these canisters directly from the plant to the MRS. To this end, it is necessary that the multiassembly sealed canisters, which have been licensed for storage under 10CFR72, be qualified for shipment within a suitable shipping cask under the rules of 10CFR71. Preliminary work performed to date indicates that it is feasible to license a current canister design for transportation, and work is proceeding on obtaining NRC approval

  1. Use of WIMS-E lattice code for prediction of the transuranic source term for spent fuel dose estimation

    International Nuclear Information System (INIS)

    Schwinkendorf, K.N.

    1996-01-01

    A recent source term analysis has shown a discrepancy between ORIGEN2 transuranic isotopic production estimates and those produced with the WIMS-E lattice physics code. Excellent agreement between relevant experimental measurements and WIMS-E was shown, thus exposing an error in the cross section library used by ORIGEN2

  2. Anticipated corrosion in the Vermont Yankee spent fuel pool

    International Nuclear Information System (INIS)

    Weeks, J.R.

    1977-06-01

    The report provides additional information relating to a proposed modification to the spent fuel pool at the Vermont Yankee Nuclear Power Station (VYNPS) and addresses corrosion of spent fuel pool storage materials and zircaloy, and provides an analysis of the effectiveness of the Boral sealing

  3. Multi-Canister overpack sealing configuration

    International Nuclear Information System (INIS)

    SMITH, K.E.

    1998-01-01

    The Spent Nuclear Fuel (SNF) position regarding the Multi-Canister Overpack (MCO) sealing configuration is to initially rely on an American Society of Mechanical Engineers (ASME) Section III Subsection NB code compliant mechanical closure/sealing system to quickly and safely establish and maintain full confinement of radioactive materials prior to and during MCO fuel drying activities. Previous studies have shown the mechanical seal to be the preferred closure method, based on dose, cost, and schedule considerations. The cost and schedule impacts of redesigning the mechanical closure to a welded shield plug do not support changing the closure system. The SNF Project has determined that the combined mechanical/welded closure system meets or exceeds the regulatory requirements to provide redundant seals while accommodating key safety and schedule limitations that are unique to K Basins fuel removal effort

  4. Calibration of the TVO spent BWR reference fuel assembly

    International Nuclear Information System (INIS)

    Tarvainen, M.; Baecklin, A.; Haakanson, A.

    1992-02-01

    In 1989 the Support Programmes of Finland (FSP) and Sweden (SSP) initiated a joint task to cross calibrate the burnup of the IAEA spent BWR reference fuel assembly at the TVO AFR storage facility (TVO KPA-STORE) in Finland. The reference assembly, kept separately under the IAEA seal, is used for verification measurements of spent fuel by GBUV method (SG-NDA-38). The cross calibration was performed by establishing a calibration curve, 244 Cm neutron rate versus burnup, using passive neutron assay (PNA) measurements. The declared burnup of the reference assembly was compared with the burnup value deduced from the calibration curve. A calibration line was also established by using the GBUV method with the aid of high resolution gamma ray spectrometry (HRGS). Normalization between the two different facilities was performed using sealed neutron and gamma calibration sources. The results of the passive neutron assay show consistency, better than 1 %, between the declared mean burnup of the reference assembly and the burnup deduced from the calibration curve. The corresponding consistency is within +-2 % for the HRGS measurements

  5. Thermal neutron imaging with rare-earth-ion-doped LiCaAlF{sub 6} scintillators and a sealed {sup 252}Cf source

    Energy Technology Data Exchange (ETDEWEB)

    Kawaguchi, Noriaki, E-mail: famicom@mail.tagen.tohoku.ac.jp [Tokuyama Corporation, Shibuya 3-chome, Shibuya-ku, Tokyo 150-8383 (Japan); IMRAM, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577 (Japan); Yanagida, Takayuki; Fujimoto, Yutaka; Yokota, Yuui; Kamada, Kei [IMRAM, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577 (Japan); Fukuda, Kentaro; Suyama, Toshihisa [Tokuyama Corporation, Shibuya 3-chome, Shibuya-ku, Tokyo 150-8383 (Japan); Watanabe, Kenichi; Yamazaki, Atsushi [Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603 (Japan); Chani, Valery [IMRAM, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577 (Japan); Yoshikawa, Akira [IMRAM, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577 (Japan); New Industry Creation Hatchery Center, Tohoku University, Sendai 980-8579 (Japan)

    2011-10-01

    Thermal neutron imaging with Ce-doped LiCaAlF{sub 6} crystals has been performed. The prototype of the neutron imager using a Ce-doped LiCaAlF{sub 6} scintillating crystal and a position sensitive photomultiplier tube (PSPMT) which had 64 multi-channel anode was developed. The Ce-doped LiCaAlF{sub 6} single crystal was grown by the Czochralski method. A plate with dimensions of a diameter of 50x2 mm{sup 2} was cut from the grown crystal, polished, and optically coupled to PSPMT by silicone grease. The {sup 252}Cf source (<1 MBq) was sealed with 43 mm of polyethylene for neutron thermalization. Alphabet-shaped Cd pieces with a thickness of 2 mm were used as a mask for the thermal neutrons. After corrections for the pedestals and gain of each pixel, we successfully obtained two-dimensional neutron images using Ce-doped LiCaAlF{sub 6}.

  6. Rotary plug seal

    International Nuclear Information System (INIS)

    Ito, Koji; Abiko, Yoshihiro.

    1981-01-01

    Purpose: To enable fuel exchange even upon failure of regular seals and also to enable safety seal exchange by the detection of the reduction in the contact pressure of a rotary plug seal. Constitution: If one of a pair of regular tube seals for the rotary plug is failed during ordinary operation of a FBR type reactor, the reduction in the contact pressure of the seal to the plug gibbousness is detected by a pressure gauge and a solenoid valve is thereby closed. Thus, a back-up-tube seal provided above or below the tube seal is press-contacted by way of argon gas to the gibbousness to enter into operation state and lubricants are supplied from an oil tank. In such a structure, the back-up-tube seal is operated before the failure of the tube seal to enable to continue the fuel exchange work, as well as safety exchange for the tube seal. (Moriyama, K.)

  7. Seal design alternatives study

    International Nuclear Information System (INIS)

    Van Sambeek, L.L.; Luo, D.D.; Lin, M.S.; Ostrowski, W.; Oyenuga, D.

    1993-06-01

    This report presents the results from a study of various sealing alternatives for the WIPP sealing system. Overall, the sealing system has the purpose of reducing to the extent possible the potential for fluids (either gas or liquid) from entering or leaving the repository. The sealing system is divided into three subsystems: drift and panel seals within the repository horizon, shaft seals in each of the four shafts, and borehole seals. Alternatives to the baseline configuration for the WIPP seal system design included evaluating different geometries and schedules for seal component installations and the use of different materials for seal components. Order-of-magnitude costs for the various alternatives were prepared as part of the study. Firm recommendations are not presented, but the advantages and disadvantages of the alternatives are discussed. Technical information deficiencies are identified and studies are outlined which can provide required information

  8. Mechanical seal assembly

    Science.gov (United States)

    Kotlyar, Oleg M.

    2001-01-01

    An improved mechanical seal assembly is provided for sealing rotating shafts with respect to their shaft housings, wherein the rotating shafts are subject to substantial axial vibrations. The mechanical seal assembly generally includes a rotating sealing ring fixed to the shaft, a non-rotating sealing ring adjacent to and in close contact with the rotating sealing ring for forming an annular seal about the shaft, and a mechanical diode element that applies a biasing force to the non-rotating sealing ring by means of hemispherical joint. The alignment of the mechanical diode with respect to the sealing rings is maintained by a series of linear bearings positioned axially along a desired length of the mechanical diode. Alternative embodiments include mechanical or hydraulic amplification components for amplifying axial displacement of the non-rotating sealing ring and transferring it to the mechanical diode.

  9. Mechanical Seal Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Kotlyar, Oleg M.

    1999-06-18

    An improved mechanical seal assembly is provided for sealing rotating shafts with respect to their shaft housings, wherein the rotating shafts are subject to substantial axial vibrations. The mechanical seal assembly generally includes a rotating sealing ring fixed to the shaft, a non-rotating sealing ring adjacent to and in close contact with the rotating sealing ring for forming an annular seal about the shaft, and a mechanical diode element that applies a biasing force to the non-rotating sealing ring by means of hemispherical joint. The alignment of the mechanical diode with respect to the sealing rings is maintained by a series of linear bearings positioned axially along a desired length of the mechanical diode. Alternative embodiments include mechanical or hydraulic amplification components for amplifying axial displacement of the non-rotating sealing ring and transferring it to the mechanical diode.

  10. Spent fuel storage process equipment development

    International Nuclear Information System (INIS)

    Park, Hyun Soo; Lee, Jae Sol; Yoo, Jae Hyung

    1990-02-01

    Nuclear energy which is a major energy source of national energy supply entails spent fuels. Spent fuels which are high level radioactive meterials, are tricky to manage and need high technology. The objectives of this study are to establish and develop key elements of spent fuel management technologies: handling equipment and maintenance, process automation technology, colling system, and cleanup system. (author)

  11. Mechanical seal program

    International Nuclear Information System (INIS)

    Lowery, G.B.

    1983-01-01

    The experimental plans and timing for completion of the mechanical seal program for both the slurry and transfer pumps are given. The slurry pump seal program will be completed by April 1984 with turnover of two seals in pumps to SRP Tank 15H. Transfer pump seal design will be released for plant use by May 1984. Also included are various other pump and seal related tests

  12. Surveillance instrumentation for spent-fuel safeguards

    International Nuclear Information System (INIS)

    McKenzie, J.M.; Holmes, J.P.; Gillman, L.K.; Schmitz, J.A.; McDaniel, P.J.

    1978-01-01

    The movement, in a facility, of spent reactor fuel may be tracked using simple instrumentation together with a real time unfolding algorithm. Experimental measurements, from multiple radiation monitors and crane weight and position monitors, were obtained during spent fuel movements at the G.E. Morris Spent-Fuel Storage Facility. These data and a preliminary version of an unfolding algorithm were used to estimate the position of the centroid and the magnitude of the spent fuel radiation source. Spatial location was estimated to +-1.5 m and source magnitude to +-10% of their true values. Application of this surveillance instrumentation to spent-fuel safeguards is discussed

  13. Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine; Desenvolvimento de fontes radioativas seladas imobilizadas em resina epoxi para verificacao de detectores utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tiezzi, Rodrigo

    2016-07-01

    The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and

  14. Nuclear reactor sealing system

    International Nuclear Information System (INIS)

    McEdwards, J.A.

    1983-01-01

    A liquid metal-cooled nuclear reactor sealing system is disclosed. The nuclear reactor includes a vessel sealed at its upper end by a closure head. The closure head comprises at least two components, one of which is rotatable; and the two components define an annulus therebetween. The sealing system includes at least a first and second inflatable seal disposed in series in an upper portion of the annulus. The system further includes a dip seal extending into a body of insulation located adjacent a bottom portion of the closure head. The dip seal comprises a trough formed by a lower portion of one of the components, and a seal blade pendently supported from the other component and extending downwardly into the trough. A body of liquid metal is contained in the trough which submerges a portion of the seal blade. The seal blade is provided with at least one aperture located above the body of liquid metal for providing fluid communication between the annulus intermediate the dip seal and the inflatable seals, and a body of cover gas located inside the vessel. There also is provided means for introducing a purge gas into the annulus intermediate the inflatable seals and the seal blade. The purge gas is introduced in an amount sufficient to substantially reduce diffusion of radioactive cover gas or sodium vapor up to the inflatable seals. The purge gas mixes with the cover gas in the reactor vessel where it can be withdrawn from the vessel for treatment and recycle to the vessel

  15. Active Infrared Thermography for Seal Contamination Detection in Heat-Sealed Food Packaging

    Directory of Open Access Journals (Sweden)

    Karlien D’huys

    2016-11-01

    Full Text Available Packaging protects food products from environmental influences, assuring quality and safety throughout shelf life if properly performed. Packaging quality depends on the quality of the packaging material and of the closure or seal. A common problem possibly jeopardizing seal quality is the presence of seal contamination, which can cause a decreased seal strength, an increased packaging failure risk and leak formation. Therefore, early detection and removal of seal contaminated packages from the production chain is crucial. In this work, a pulsed-type active thermography method using the heated seal bars as an excitation source was studied for detecting seal contamination. Thermal image sequences of contaminated seals were recorded shortly after sealing. The detection performances of six thermal image processing methods, based on a single frame, a fit of the cooling profiles, thermal signal reconstruction, pulsed phase thermography, principal component thermography and a matched filter, were compared. High resolution digital images served as a reference to quantify seal contamination, and processed thermal images were mapped to these references. The lowest detection limit (equivalent diameter 0.60 mm was obtained for the method based on a fit of the cooling profiles. Moreover, the detection performance of this method did not depend strongly on the time after sealing at which recording of the thermal images was started, making it a robust and generally applicable method.

  16. Spray sealing: A breakthrough in integral fuel tank sealing technology

    Science.gov (United States)

    Richardson, Martin D.; Zadarnowski, J. H.

    1989-11-01

    In a continuing effort to increase readiness, a new approach to sealing integral fuel tanks is being developed. The technique seals potential leak sources by spraying elastomeric materials inside the tank cavity. Laboratory evaluations project an increase in aircraft supportability and reliability, an improved maintainability, decreasing acquisition and life cycle costs. Increased usable fuel volume and lower weight than conventional bladders improve performance. Concept feasibility was demonstrated on sub-scale aircraft fuel tanks. Materials were selected by testing sprayable elastomers in a fuel tank environment. Chemical stability, mechanical properties, and dynamic durability of the elastomer are being evaluated at the laboratory level and in sub-scale and full scale aircraft component fatigue tests. The self sealing capability of sprayable materials is also under development. Ballistic tests show an improved aircraft survivability, due in part to the elastomer's mechanical properties and its ability to damp vibrations. New application equipment, system removal, and repair methods are being investigated.

  17. Inboard seal mounting

    Science.gov (United States)

    Hayes, John R. (Inventor)

    1983-01-01

    A regenerator assembly for a gas turbine engine has a hot side seal assembly formed in part by a cast metal engine block having a seal recess formed therein that is configured to supportingly receive ceramic support blocks including an inboard face thereon having a regenerator seal face bonded thereto. A pressurized leaf seal is interposed between the ceramic support block and the cast metal engine block to bias the seal wear face into sealing engagement with a hot side surface of a rotary regenerator matrix.

  18. National report of the Slovak Republic - proposal. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Jun 2008

    International Nuclear Information System (INIS)

    Jurina, V.; Viktory, D.; Kobzova, D.; Petrik, T.; Sovcik, J.; Hekel, P.; Suess, J.; Tomek, J.; Lukacovic, J.; Hekel, P.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Konecny, L.; Parimucha, F.; Vaclav, J.; Horvath, J.; Soos, F.; Betak, A.; Pospisil, P.; Mihaly, B.; Kubala, M.; Schmidtova, B.; Orihel, M.; Vasina, D.; Balaz, J.; Ehn, L.; Micovicova, D.; Vrtoch, M.; Mlcuch, L.; Granak, P.; Meleg, J.; Sedliak, D.; Bardy, M.; Gogoliak, J.; Prazska, M.; Burslova, J.

    2008-06-01

    A brief national safety report of the Slovak Republic compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management in 2008 is presented. This safety report consists of following chapters: (A) Introduction; (B) Spent nuclear fuel (SNF) and radioactive waste (RAW) management conception; (C) Scope of application; (D) Spent nuclear fuel (SNF) and radioactive waste (RAW) management; (E) Legislation and regulatory framework; (F) General safety provisions; (G) Safety of spent nuclear fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Discussed sealed radioactive sources; (K) Planned measures to improve safety; (L) Annexes

  19. Use of rice rusk ash and spent catalyst as a source of raw material for the production and characterization of soda-lime silicate glasses destined for packaging

    International Nuclear Information System (INIS)

    Araujo, Mariana Silva de

    2016-01-01

    In this study, the use of two industrial solid wastes (ISW), generated in large quantities in Brazil, were presented in production of soda-lime silicate glasses destined for packaging. The evaluated wastes were rice husk ash (RHA) and the spent catalyst at the Petrochemical Fluid Catalytic Cracking units (ECAT), both may be classified as a class II solid waste according to NBR 10.004. This new proposal for the allocation of such wastes is an alternative to current provisions, seeking not only to minimize environmental impacts, but also enrich them as raw materials. For the samples production, besides ISW were used melting oxide (Na 2 CO 3 ) and stabilizer oxide (CaO).The results demonstrate that both can be used in their raw form (without treatment) replacing important raw materials, sources of Al 2 O 3 and SiO 2 , essential for glass formation. The samples obtained presented amber color due to the presence of nickel (Ni² + ion) from ECAT and 18% of optical transmittance. They also showed a good homogeneity, i.e., absence of bubbles and striae and 1,33 x 10 -8 g/cm²·day of hydrolytic resistance according to ISO695-1984. Thus, the obtained glass is suitable for applications requiring low light transmittance such as colored glasses containers in general, which does not require perfect visibility and transparency. The incorporation in the final composition was approximately 78% in mass. (author)

  20. Nuclear waste vault sealing

    International Nuclear Information System (INIS)

    Gyenge, M.

    1980-01-01

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

  1. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    Dooley, R.A.

    1986-01-01

    This invention relates to an apparatus and method for sealing the cold leg nozzles of a nuclear reactor pressure vessel from a remote location during maintenance and inspection of associated steam generators and pumps while the pressure vessel and refueling canal are filled with water. The apparatus includes a sealing plug for mechanically sealing the cold leg nozzle from the inside of a reactor pressure vessel. The sealing plugs include a primary and a secondary O-ring. An installation tool is suspended within the reactor vessel and carries the sealing plug. The tool telescopes to insert the sealing plug within the cold leg nozzle, and to subsequently remove the plug. Hydraulic means are used to activate the sealing plug, and support means serve to suspend the installation tool within the reactor vessel during installation and removal of the sealing plug

  2. Fog seal guidelines.

    Science.gov (United States)

    2003-10-01

    Fog seals are a method of adding asphalt to an existing pavement surface to improve sealing or waterproofing, prevent further stone loss by holding aggregate in place, or simply improve the surface appearance. However, inappropriate use can result in...

  3. Hermetically Sealed Compressor

    Science.gov (United States)

    Holtzapple, Mark T.

    1994-01-01

    Proposed hermetically sealed pump compresses fluid to pressure up to 4,000 atm (400 MPa). Pump employs linear electric motor instead of rotary motor to avoid need for leakage-prone rotary seals. In addition, linear-motor-powered pump would not require packings to seal its piston. Concept thus eliminates major cause of friction and wear. Pump is double-ended diaphragm-type compressor. All moving parts sealed within compressor housing.

  4. 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.

  5. 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.

  6. Investigation of positive shaft seals

    Science.gov (United States)

    Pfouts, J. O.

    1970-01-01

    Welded metal bellows secondary seals prevent secondary seal leakage with a minimum number of potential leak paths. High performance seal is obtained by controlling the potentially unstable seal-face movements induced by mechanical vibrations and fluid pressure pulsations.

  7. Circumferential shaft seal

    Science.gov (United States)

    Ludwig, L. P. (Inventor)

    1981-01-01

    A circumferential shaft seal comprising two sealing rings held to a rotating shaft by means of a surrounding elastomeric band is disclosed. The rings are segmented and are of a rigid sealing material such as carbon or a polyimide and graphite fiber composite.

  8. Seals in motion

    NARCIS (Netherlands)

    Brasseur, Sophie Marie Jacqueline Michelle

    2017-01-01

    The harbour seal Phoca vitulina and the grey seal Halichoerus grypus have been inhabitants of the Wadden Sea since millennia. Prehistoric findings indicate the presence of both species around 5000 BC. This changed dramatically in the mid Middle-Ages as around 1500 AC, the grey seal disappeared from

  9. Radioactive source

    International Nuclear Information System (INIS)

    Drabkina, L.E.; Mazurek, V.; Myascedov, D.N.; Prokhorov, P.; Kachalov, V.A.; Ziv, D.M.

    1976-01-01

    A radioactive layer in a radioactive source is sealed by the application of a sealing layer on the radioactive layer. The sealing layer can consist of a film of oxide of titanium, tin, zirconium, aluminum, or chromium. Preferably, the sealing layer is pure titanium dioxide. The radioactive layer is embedded in a finish enamel which, in turn, is on a priming enamel which surrounds a substrate

  10. Electronic self-monitoring seal

    International Nuclear Information System (INIS)

    Campbell, J.W.

    1978-01-01

    The Electronic Self-Monitoring Seal is a new type of security seal which allows continuous verification of the seal's identity and status. The identity information is a function of the individual seal, time, and seal integrity. A description of this seal and its characteristics are presented. Also described are the use cycle for the seal and the support equipment for programming and verifying the seal

  11. VAK III. Seals and sealing system

    International Nuclear Information System (INIS)

    d'Agraives, B.C.; Dal Cero, G.; Debeir, R.; Mascetti, E.; Toornvliet, J.; Volcan, A.

    1986-01-01

    This report presents the VAK III seals and sealing system, which have been used over a period of two years at the Kahl nuclear facility (Federal Republic of Germany), where field tests and feasibility studies were conducted in order to offer a possible solution for the sealing of LWR fuel assemblies. It has been prepared with the aim of an assessment study to be done at the IAEA. It gives all characteristics and technical descriptions for: the sealing principle, the seal construction, the operating tools, the data processing, the drawings, the publications related to that seal. The main points of progress are: the Strong Random Internal Defects (STRID) incorporated in the seals, allowing the obtention of a good signature stability; the Integrity Check on the Seal Status (broken or not) obtained through a decisive mechanical improvement: the Double Breakage Integrity Check (DOBRIC) and with a better ultrasonic evidence of that status; the provision of new function tools, allowing the performance of Identity Measurements in dry conditions (which means also at the manufacturer plant) or in deeper water (wet storage); the study and development of a new JRC VAK 45 Compact Instrument Box, in which all the measuring functions can be grouped and incorporating an autonomous Minicomputer offering to the Inspection the possibility of performing, on the spot, Correlation and Decision processes. The general benefit of such a feasibility study should be to convince the potential users that such a Safeguards Sealing System can be studied for slightly - or largely - different other applications, provided that the Basic and Operating Functions required to the system be clearly defined, possibly after a common agreement would be stated

  12. Reinforced seal component

    International Nuclear Information System (INIS)

    Jeanson, G.M.; Odent, R.P.

    1980-01-01

    The invention concerns a seal component of the kind comprising a soft sheath and a flexible reinforcement housed throughout the entire length of the sheath. The invention enables O ring seals to be made capable of providing a radial seal, that is to say between two sides or flat collars of two cylindrical mechanical parts, or an axial seal, that is to say between two co-axial axisymmetrical areas. The seal so ensured is relative, but it remains adequately sufficient for many uses, for instance, to ensure the separation of two successive fixed blading compartments of axial compressors used in gas diffusion isotope concentration facilities [fr

  13. Cosmic ray muons for spent nuclear fuel monitoring

    Science.gov (United States)

    Chatzidakis, Stylianos

    There is a steady increase in the volume of spent nuclear fuel stored on-site (at reactor) as currently there is no permanent disposal option. No alternative disposal path is available and storage of spent nuclear fuel in dry storage containers is anticipated for the near future. In this dissertation, a capability to monitor spent nuclear fuel stored within dry casks using cosmic ray muons is developed. The motivation stems from the need to investigate whether the stored content agrees with facility declarations to allow proliferation detection and international treaty verification. Cosmic ray muons are charged particles generated naturally in the atmosphere from high energy cosmic rays. Using muons for proliferation detection and international treaty verification of spent nuclear fuel is a novel approach to nuclear security that presents significant advantages. Among others, muons have the ability to penetrate high density materials, are freely available, no radiological sources are required and consequently there is a total absence of any artificial radiological dose. A methodology is developed to demonstrate the applicability of muons for nuclear nonproliferation monitoring of spent nuclear fuel dry casks. Purpose is to use muons to differentiate between spent nuclear fuel dry casks with different amount of loading, not feasible with any other technique. Muon scattering and transmission are used to perform monitoring and imaging of the stored contents of dry casks loaded with spent nuclear fuel. It is shown that one missing fuel assembly can be distinguished from a fully loaded cask with a small overlapping between the scattering distributions with 300,000 muons or more. A Bayesian monitoring algorithm was derived to allow differentiation of a fully loaded dry cask from one with a fuel assembly missing in the order of minutes and negligible error rate. Muon scattering and transmission simulations are used to reconstruct the stored contents of sealed dry casks

  14. The IRES electronic seal

    International Nuclear Information System (INIS)

    Autrusson, B.; Brochard, D.; Moreau, J.F.; Martin, J.C.

    2001-01-01

    In the framework of the French Support Program for the IAEA Safeguards, the 'Institut de Protection et de Surete Nucleaire' (IPSN), developed an electronic seal called Integrated and Reusable Electronic Seal (IRES) that enables independent verification by different inspectorates (IAEA, Euratom, and National Inspectorate). The seal can be remotely interrogated by radio frequency and integrated to other Containment/surveillance systems by serial line RS 485. Data are authenticated and the IRESMAG software manages in the seal reader all functionalities of the seal and records inspection data compatible with the IAEA's Seal Database. To perform this development, IPSN relies on industrial partners: SAPHYMO for the general architecture of the seal and the electronics, THALES for the authentication of data and the security of transmission. The main features of the IRES seal are the following: Interrogation by different inspectorate, allowing independent conclusions; Recording of events, including tampering, in a non-volatile memory; Authentication of data and enhanced security of the communication between the seal and the seal reader; Remote interrogation by an inspector or/and automatic for unattended systems or remote monitoring; Reusable after erasing the seal memory and replacement of the batteries

  15. Severe service sealing solutions

    International Nuclear Information System (INIS)

    Metcalfe, R.; Wensel, R.

    1994-09-01

    Successful sealing usually requires much more than initial leak-tightness. Friction and wear must also be acceptable, requiring a good understanding of tribology at the sealing interface. This paper describes various sealing solutions for severe service conditions. The CAN2A and CAN8 rotary face seals use tungsten carbide against carbon-graphite to achieve low leakage and long lifetime in nuclear main coolant pumps. The smaller CAN6 seal successfully uses tungsten carbide against silicon carbide in reactor water cleanup pump service. Where friction in CANDU fuelling machine rams must be essentially zero, a hydrostatic seal using two silicon carbide faces is the solution. In the NRU reactor moderator pumps, where pressure is much lower, eccentric seals that prevent boiling at the seal faces are giving excellent service. All these rotary face seals rely on supplementary elastomer seals between their parts. An integrated engineering approach to high performance sealing with O-rings is described. This is epitomized in critical Space Shuttle applications, but is increasingly being applied in CANDU plants. It includes gland design, selection and qualification of material, quality assurance, detection of defects and the effects of lubrication, surface finish, squeeze, stretch and volume constraints. In conclusion, for the severe service applications described, customized solutions have more than paid for themselves by higher reliability, lower maintenance requirements and reduced outage time. (author)

  16. The IRES electronic seal

    International Nuclear Information System (INIS)

    Gourlez, P.; Funk, P.; Brochard, D.; Moreau, J.F.; Martin, J.C.

    2001-01-01

    In the framework of the French Support Program for the IAEA Safeguards, the 'Institut de Protection et de Surete Nucleaire' (IPSN), developed an electronic seal called Integrated and Reusable Electronic Seal (IRES) that enables independent verification by different inspectorates (IAEA, Euratom, and National Inspectorate) Furthermore, a bilateral co-ordination between Euratom and French domestic safeguards takes place in some French facilities regarding a common approach concerning the seals especially in case of crisis situation. The seal can be remotely interrogated by radio frequency and integrated to other Containment/surveillance systems by serial line RS 485. Data are authenticated and the IRESMAG software manages in the seal reader all functionalities of the seal and records inspection data compatible with the IAEA's Seal Database

  17. High pressure shaft seal

    International Nuclear Information System (INIS)

    Martinson, A.R.; Rogers, V.D.

    1980-01-01

    In relation to reactor primary coolant pumps, mechanical seal assembly for a pump shaft is disclosed which features a rotating seal ring mounting system which utilizes a rigid support ring loaded through narrow annular projections in combination with centering non-sealing O-rings which effectively isolate the rotating seal ring from temperature and pressure transients while securely positioning the ring to adjacent parts. A stationary seal ring mounting configuration allows the stationary seal ring freedom of motion to follow shaft axial movement up to 3/4 of an inch and shaft tilt about the pump axis without any change in the hydraulic or pressure loading on the stationary seal ring or its carrier. (author)

  18. Radioactive wastes and spent fuels management in Argentina

    International Nuclear Information System (INIS)

    Maset, Elvira R.

    2006-01-01

    CNEA was created in 1950 and since then has carried out research and development activities, production of radioisotopes, medical and industrial applications, and those activities related with the nuclear fuel cycle, including the operation of two nuclear power stations. More ever, different public and private institutions use radioactive materials in medical, industrial and research activities. These activities generate different types of radioactive waste, desuse sealed sources and spent fuel. The management of radioactive waste of all types produced in the country, as the spent nuclear fuel of power and research reactors and the used radioactive sources was always and it is at present a CNEA's responsibility. In February 2003, according to the Law No. 25.018, called 'Management of Radioactive Waste Regimen', the 'Radioactive Waste Management National Programme' was created by CNEA to fulfill the institutional functions and responsibilities established in the Law, in order to guarantee the safe management of radioactive waste according to the regulations established by the Argentine Nuclear Regulatory Agency and to the legislation in force. (author) [es

  19. Gamma-ray mirror technology for NDA of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Descalle, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ruz-Armendariz, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Decker, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Alameda, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Brejnholt, N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Soufli, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Robinson, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dreyer, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pivovaroff, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ziock, K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Chichester, D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Watson, S. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Trellue, H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-28

    Direct measurements of gamma rays emitted by fissile material have been proposed as an alternative to measurements of the gamma rays from fission products. From a safeguards applications perspective, direct detection of uranium (U) and plutonium (Pu) K-shell fluorescence emission lines and specific lines from some of their isotopes could lead to improved shipper-receiver difference or input accountability at the start of Pu reprocessing. However, these measurements are difficult to implement when the spent fuel is in the line-of-sight of the detector, as the detector is exposed to high rates dominated by fission product emissions. To overcome the combination of high rates and high background, grazing incidence multilayer mirrors have been proposed as a solution to selectively reflect U and Pu hard X-ray and soft gamma rays in the 90 to 420 keV energy into a high-purity germanium (HPGe) detector shielded from the direct line-of-sight of spent fuel. Several groups demonstrated that K-shell fluorescence lines of U and Pu in spent fuel could be detected with Ge detectors. In the field of hard X-ray optics the performance of reflective multilayer coated reflective optics was demonstrated up to 645 keV at the European Synchrotron Radiation Facility. Initial measurements conducted at Oak Ridge National Laboratory with sealed sources and scoping experiments conducted at the ORNL Irradiated Fuels Examination Laboratory (IFEL) with spent nuclear fuel further demonstrated the pass-band properties of multilayer mirrors for reflecting specific emission lines into 1D and 2D HPGe detectors, respectively.

  20. Flexible ring seal

    International Nuclear Information System (INIS)

    Abbes, Claude; Gournier, Andre; Rouaud, Christian; Villepoix, Raymond de.

    1976-01-01

    The invention concerns a flexible metal ring seal, able to ensure a perfect seal between two bearings due to the crushing and elastic deformation properties akin to similar properties in elastomers. Various designs of seal of this kind are already known, particularly a seal made of a core formed by a helical wire spring with close-wound turns and with high axial compression ratio, closed on itself and having the shape of an annulus. This wire ring is surrounded by at least one envelope having at rest the shape of a toroidal surface of which the generating circle does not close on itself. In a particular design mode, the seal in question can include, around the internal spring, two envelopes of which one in contact with the spring is composed of a low ductility elastic metal, such as mild steel or stainless steel and the other is, on the contrary, made of a malleable metal, such as copper or nickel. The first envelope evenly distributes the partial crushing of the spring, when the seal is tightened, on the second envelope which closely fits the two surfaces between which the seal operates. The stress-crushing curve characteristic of the seal comprises two separate parts, the first with a relatively sharp slope corresponds to the start of the seal compression phase, enabling at least some of these curves to reach the requisite seal threshold very quickly, then, beyond this, a second part, practically flat, where the stress is appreciably constant for a wide operating bracket [fr

  1. Detection of seal contamination in heat-sealed food packaging based on active infrared thermography

    Science.gov (United States)

    D'huys, Karlien; Saeys, Wouter; De Ketelaere, Bart

    2015-05-01

    In the food industry packaging is often applied to protect the product from the environment, assuring quality and safety throughout shelf life if properly performed. Packaging quality depends on the material used and the closure (seal). The material is selected based on the specific needs of the food product to be wrapped. However, proper closure of the package is often harder to achieve. One problem possibly jeopardizing seal quality is the presence of food particles between the seal. Seal contamination can cause a decreased seal strength and thus an increased packaging failure risk. It can also trigger the formation of microchannels through which air and microorganisms can enter and spoil the enclosed food. Therefore, early detection and removal of seal-contaminated packages from the production chain is essential. In this work, a pulsed-type active thermography method using the heat of the sealing bars as an excitation source was studied for detecting seal contamination. The cooling profile of contaminated seals was recorded. The detection performance of four processing methods (based on a single frame, a fit of the cooling profile, pulsed phase thermography and a matched filter) was compared. High resolution digital images served as a reference to quantify contamination. The lowest detection limit (equivalent diameter of 0.63 mm) and the lowest processing time (0.42 s per sample) were obtained for the method based on a single frame. Presumably, practical limitations in the recording stage prevented the added value of active thermography to be fully reflected in this application.

  2. Spent fuel management in Japan

    International Nuclear Information System (INIS)

    Shirahashi, K.; Maeda, M.; Nakai, T.

    1996-01-01

    Japan has scarce energy resources and depends on foreign resources for 84% of its energy needs. Therefore, Japan has made efforts to utilize nuclear power as a key energy source since mid-1950's. Today, the nuclear energy produced from 49 nuclear power plants is responsible for about 31% of Japan's total electricity supply. The cumulative amount of spent fuel generated as of March 1995 was about 11,600 Mg U. Japan's policy of spent fuel management is to reprocess spent nuclear fuel and recycle recovered plutonium and uranium as nuclear fuel. The Tokai reprocessing plant continues stable operation keeping the annual treatment capacity or around 90 Mg U. A commercial reprocessing plant is under construction at Rokkasho, northern part of Japan. Although FBR is the principal reactor to use plutonium, LWR will be a major power source for some time and recycling of the fuel in LWRs will be prompted. (author). 3 figs

  3. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The seals described are for use in a nuclear reactor where there are fuel assemblies in a vessel, an inlet and an outlet for circulating a coolant in heat transfer relationship with the fuel assemblies and a closure head on the vessel in a tight fluid relationship. The closure head comprises rotatable plugs which have mechanical seals disposed in the annulus around each plug while allowing free rotation of the plug when the seal is not actuated. The seal is usually an elastomer or copper. A means of actuating the seal is attached for drawing it vertically into the annulus for sealing. When the reactor coolant is liquid sodium, contact with oxygen must be avoided and argon cover gas fills the space between the bottom of the closure head and the coolant liquid level and the annuli in the closure head. (U.K.)

  4. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  5. Compliant seal development

    Science.gov (United States)

    Hendricks, Robert C.

    1993-10-01

    The compliant metallic seal combines the noncontact feature of the labyrinth seal, the low leakage of a mechanical seal, and the compliant nature of the brush seal. It consists of several thin metallic elements or leaves mounted within a ring which is press fit into the housing, and in form, sort of resembles a lip seal sections wiping the shaft. A second set of overlapping cover leaves are placed on top of the shaft riding leaves which reduces leakage and provides stiffness. The leaves can be straight or angle cut. The shaft riding fingers are designed with mismatched curvature to provide lift off similar to the Rayleigh lift pads in mechanical seals with leading edge clearances nearly twice those of the trailing edge as as shown by Fleming to be optimal for gas flows in convergent seal passages. Leading edge clearances range from 300 to 500 microinches. Balance pockets beneath the leaves provide fluid film feed to the 'Rayleigh lift' surface and the proper balance ratio (mechanical seal) when combined with the static pressure and film pressure. The leaves flex in the radial direction and accommodate thermomechanical behavior as well as axial motion and angular misalignment. In the static mode, there is a net closing force on the leaves. The seals were tested to 70 psi at speeds to 16,000 rpm or surface speeds to 330 fps and temperatures from ambient to 440 F. A slow cycle through the rig critical at 10,000 rpm induced a radial vibration response of 0.004 to 0.005 inch were accommodated by the seal. Preliminary performance data are encouraging demonstrating hydrodynamic liftoff and noncontacting operation at pressure and speeds typical of gas turbine engines. The leakage performance data are significantly better than commercial labyrinth and brush seals which should be expected as this design incorporates the features of the low leakage face or mechanical seal along with the flexibility of the brush configuration.

  6. Safeguards sealing systems for Zebra

    International Nuclear Information System (INIS)

    Ingram, G.; Jamieson, G.R.

    1983-01-01

    A relatively simple design has been produced for safeguards seals to be applied throughout the fuel containing areas at Zebra. It is based on the use of wire seals and regular Inspector surveillance. The application of the system would allow an Inspector to establish to a high degree of confidence that significant quantities of fuel had not been diverted during an intensive experimental programme. It would add about 5% to the time required for experiments, and careful planning would reduce this value. The inspection effort required to witness element movements during the experimental programme would average about 2 hours per day, with a further 2 hours spent each week on NDA of the fuel exposed. The Safeguards Inspector would require to spend about 25% of his time in the reactor area and would have ample time to deal with the relatively small number of fuel movements taking place in the storage area and with his duties elsewhere in the plant. During a core change, full-time inspection effort would be required for about 6 weeks each year. (author)

  7. Seal containment system

    International Nuclear Information System (INIS)

    Kugler, R.W.; Gerkey, K.S.; Kasner, W.H.

    1978-01-01

    An automated system for transporting nuclear fuel elements between fuel element assembly stations without contaminating the area outside the sealed assembly stations is described. The system comprises a plurality of assembly stations connected together by an elongated horizontal sealing mechanism and an automatic transport mechanism for transporting a nuclear fuel element in a horizontal attitude between the assembly stations while the open end of the fuel element extends through the sealing mechanism into the assembly station enclosure. The sealing mechanism allows the fuel element to be advanced by the transport mechanism while limiting the escape of radioactive particles from within the assembly station enclosure. 4 claims, 6 figures

  8. National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. 2005

    International Nuclear Information System (INIS)

    Hekel, P.; Ivan, J.; Lukacovic, K.; Parimucha, F.; Suss, J; Tomek, J.; Jurina, V.; Kobzova, D.; Konecny, L.; Homola, J.; Zavazanova, A.; Metke, E.; Turner, M.; Vaclav, J.; Ziakova, M.; Pospisil, M.; Petrik, T.

    2005-09-01

    The National Report (Compiled in terms of the Joint Convention - September 2005) contains information how each of the obligations of the Joint Convention have been implemented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) and other Slovak organisations are presented. These activities are reported under the headings: (A) Introduction; (B) Spent fuel and radioactive waste management; C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of RAW management; (I) Transboundary movement of SF and RAW; (J) Disused sealed sources; (K) planned activiries to improve safety; (L) Annexes

  9. Improved cryogenic shaft seals

    Science.gov (United States)

    Gillon, W. A., Jr.; Tellier, G. F.

    1976-01-01

    Seals are designed for use with liquid propellant ball valves at temperatures ranging from -400 F to 130 F and 8,000 psig. Seals are capable of sustaining 90 degree rotation, with substantial amount of lateral and axial play, caused by large pressure loads and differential thermal contraction.

  10. Rotary shaft seal

    International Nuclear Information System (INIS)

    Langebrake, C.O.

    1984-01-01

    The invention is a novel rotary shaft seal assembly which provides positive-contact sealing when the shaft is not rotated and which operates with its sealing surfaces separated by a film of compressed ambient gas whose width is independent of the speed of shaft rotation. In a preferred embodiment, the assembly includes a disc affixed to the shaft for rotation therewith. Axially movable, non-rotatable plates respectively supported by sealing bellows are positioned on either side of the disc to be in sealing engagement therewith. Each plate carries piezoelectric transducer elements which are electrically energized at startup to produce films of compressed ambient gas between the confronting surfaces of the plates and the disc. Following shutdown of the shaft, the transducer elements are de-energized. A control circuit responds to incipient rubbing between the plate and either disc by altering the electrical input to the transducer elements to eliminate rubbing

  11. Sealing a conduit end

    International Nuclear Information System (INIS)

    Mentz, R.M.

    1993-01-01

    An apparatus for sealing or blocking conduits, such as the primary nozzles of a nuclear steam generator is described. It includes an annular bracket sealingly attached to the open end of the nozzle, the bracket having a plurality of threaded holes therein. Mounted atop the bracket is a generally circular nozzle dam for covering the opening. Interposed between the nozzle dam and the bracket is an extrusion-resistant seal member having a plurality of apertures therethrough for receiving each bolt. The seal member is configured to resist extrusion by having laminated layers of differing hardnesses, so that the seal member will not laterally extrude away from each bolt in a manner that enlarges the aperture surrounding each bolt as the nozzle dam is bolted to the bracket. (author)

  12. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    Dooley, R.A.

    1986-01-01

    An apparatus is described for sealing a cold leg nozzle of a nuclear reactor pressure vessel from a remote location comprising: at least one sealing plug for mechanically sealing the nozzle from the inside of the reactor pressure vessel. The sealing plug includes a plate and a cone assembly having an end part receptive in the nozzle, the plate being axially moveable relative to the cone assembly. The plate and cone assembly have confronting bevelled edges defining an opening therebetween. A primary O-ring is disposed about the opening and is supported on the bevelled edges, the plate being guidably mounted to the cone assembly for movement toward the cone assembly to radially expand the primary O-ring into sealing engagement with the nozzle. A means is included for providing relative movement between the outer plate and the cone assembly

  13. Brush seal performance measurement system

    OpenAIRE

    Aksoy, Serdar; Akşit, Mahmut Faruk; Aksit, Mahmut Faruk; Duran, Ertuğrul Tolga; Duran, Ertugrul Tolga

    2009-01-01

    Brush seals are rapidly replacing conventional labyrinth seals in turbomachinery applications. Upon pressure application, seal stiffness increases drastically due to frictional bristle interlocking. Operating stiffness is critical to determine seal wear life. Typically, seal stiffness is measured by pressing a curved shoe to brush bore. The static-unpressurized measurement is extrapolated to pressurized and high speed operating conditions. This work presents a seal stiffness measurement syste...

  14. Characteristics of spent nuclear fuel

    International Nuclear Information System (INIS)

    Notz, K.J.

    1988-04-01

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will, or may, eventually be disposed of in a geological repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. This report deals with spent fuels, but for completeness, the other sources are described briefly. Detailed characterizations are required for all of these potential repository wastes. These characteristics include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. In addition, the present inventories and projected quantities of the various wastes are needed. This information has been assembled in a Characteristics Data Base which provides data in four formats: hard copy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files. 5 refs., 3 figs., 4 tabs

  15. Calculation of Water Levels in Spent Fuel Pool and Effective Dose Followed by the Worker Geometrically Exposed to Radiation using Gamma-ray Source

    International Nuclear Information System (INIS)

    Lee, Donghee; Park, Kwangheon; Yoon, Hyoungju

    2013-01-01

    If the total effective dose value is lower than the surface dose rate of the water, the worker is able to work in a safe environment. In the case that the level of spent fuel pool is up to 550cm, there exists the limitation for workers to access to the storage pool because the result value is about 8 times higher than surface dose rate. In the case that the level of spent fuel pool is higher than 600cm, however, it can be safe work environment because the result value is lower than surface dose rate. Therefore, in the case of ISO geometry which is the same with practical situation, when considering Gamma-ray emission from spent fuel, effective dose is much higher than surface dose rate when the level of storage pool is lower than the height of fuel, 452.8cm. On the other hand, the level of effective dose decreases rapidly when the level of storage pool is higher than the level of the fuel. This means that it is not the safe environment when the level of fuel below 140cm is lower than surface dose rate. That is why the access of workers should be limited. Whereas, in the case of the level of storage pool above 600cm which is about 140cm higher than the level of the fuel, it is the safe environment for workers because the result value becomes lower than surface dose rate As a result, the level of wet storage of spent fuel should be at least 600cm for workers to work in safe environment because lower dose than surface dose rate makes less radiation exposure

  16. Assessment of nitrogen as an atmosphere for dry storage of spent LWR fuel

    International Nuclear Information System (INIS)

    Gilbert, E.R.; Knox, C.A.; White, G.D.

    1985-09-01

    Interim dry storage of spent light-water reactor (LWR) fuel is being developed as a licensed technology in the United States. Because it is anticipated that license agreements will specify dry storage atmospheres, the behavior of spent LWR fuel in a nitrogen atmosphere during dry storage was investigated. In particular, the thermodynamics of reaction of nitrogen compounds (expected to form in the cover gas during dry storage) and residual impurities (such as moisture and oxygen) with Zircaloy cladding and with spent fuel at sites of cladding breaches were examined. The kinetics of reaction were not considered it was assumed that the 20 to 40 years of interim dry storage would be sufficient for reactions to proceed to completion. The primary thermodynamics reactants were found to be NO 2 , N 2 O, H 2 O 2 , and O 2 . The evaluation revealed that the limited inventories of these reactants produced by the source terms in hermetically sealed dry storage systems would be too low to cause significant spent fuel degradation. Furthermore, the oxidation of spent fuel to degrading O/U ratios is unlikely because the oxidation potential in moist nitrogen limits O/U ratios to values less than UO/sub 2.006/ (the equilibrium stoichiometric form in equilibrium with moist nitrogen). Tests were performed with bare spent UO 2 fuel and nonirradiated UO 2 pellets (with no Zircaloy cladding) in a nitrogen atmosphere containing moisture concentrations greater than encountered under dry storage conditions. These tests were performed for at least 1100 h at temperatures as high as 380 0 C, where oxidation reactions proceed in a matter of minutes. No visible degradation was detected, and weight changes were negligible

  17. Spent fuel storage requirements, 1988

    International Nuclear Information System (INIS)

    1988-10-01

    Historical inventories of spent fuel and Department of Energy (DOE) estimates of future discharges from US commercial nuclear reactors are presented for the next 20 years, through the year 2007. The eventual needs for additional spent fuel storage capacity are estimated. These estimates are based on the maximum capacities within current and planned at-reactor facilities and on any planned transshipments of fuel to other reactors or facilities. Historical data through December 1987 and projected discharges through the end of reactor life are used in this analysis. The source data was supplied by the utilities to DOE through the 1988 RW-859 data survey and by DOE estimates of future nuclear capacity, generation, and spent fuel discharges. 12 refs., 3 figs., 28 tabs

  18. The role of engineered barriers in spent fuel disposal

    International Nuclear Information System (INIS)

    Vokal, A.

    1997-01-01

    Engineered, i.e. man-made, barriers in underground spent fuel disposal include the waste form itself, the fuel cladding, the storage container, and the isolating system made of buffering, filling, and sealing materials. The parameters of and requirements for each of the components are highlighted, and the methodology of materials selection is discussed. (P.A.)

  19. Reactor cavity seal ring

    International Nuclear Information System (INIS)

    Hankinson, M.F.

    1986-01-01

    A hydrostatic seal is described for sealing an annular gap between two flat substantially horizontal coplanar surfaces comprising, in combination: a generally flat annular plate of a width sufficient to span a gap between two surfaces: compressible annular sealing means disposed on the bottom surface of the flat annular plate for sealingly engaging the two flat surfaces in response to a downward force exerted on the plate; and fastening means, distributed along the center line of the plate, for releasably fastening the plate in a position to span the gap to be sealed and exert a downward force on the plate, each fastening means including a pair of elongated members of a size to fit into the gap to be sealed, means for mounting the members on the bottom surface of the plate so that at least a portion of each member is radially moveable in a direction toward a respective one of the vertical side surfaces defining the gap to be sealed to engage same and so that the plate is moveable relative to the members in a downward direction in response to hydrostatic pressure applied to the upper surface of the plate when the members are engaging the vertical side surfaces of an annular gap, and an actuating means, mounted on the plate for movement therewith in response to hydrostatic pressure, for radially moving the members, the actuating means extending through a bore in the plate to the upper surface of the plate

  20. SEALING SIMULATED LEAKS

    Energy Technology Data Exchange (ETDEWEB)

    Michael A. Romano

    2004-09-01

    This report details the testing equipment, procedures and results performed under Task 7.2 Sealing Simulated Leaks. In terms of our ability to seal leaks identified in the technical topical report, Analysis of Current Field Data, we were 100% successful. In regards to maintaining seal integrity after pigging operations we achieved varying degrees of success. Internal Corrosion defects proved to be the most resistant to the effects of pigging while External Corrosion proved to be the least resistant. Overall, with limitations, pressure activated sealant technology would be a viable option under the right circumstances.

  1. Cover-gas seals: 11-LMFBR seal-test program

    International Nuclear Information System (INIS)

    Steele, O.P. III; Horton, P.H.

    1977-01-01

    The objective of the Cover Gas Seal Material Development Program is to perform the engineering development required to provide reliable seals for LMFBR application. Specific objectives are to verify the performance of commercial solid cross-section and inflatable seals under reactor environments including radiation, to develop advanced materials and configurations capable of achieving significant improvement in radioactive gas containment and seal temperature capabilities, and to optimize seal geometry for maximum reliability and minimal gas permeation

  2. Rotatable seal assembly

    International Nuclear Information System (INIS)

    Garibaldi, J.L.; Logan, C.M.

    1982-01-01

    An assembly is provided for rotatably supporting a rotor on a stator so that vacuum chambers in the rotor and stator remain in communication while the chambers are sealed from ambient air, which enables the use of a ball bearing or the like to support most of the weight of the rotor. The apparatus includes a seal device mounted on the rotor to rotate therewith, but shiftable in position on the rotor while being sealed to the rotor as by an oring. The seal device has a flat face that is biased towards a flat face on the stator, and pressurized air is pumped between the faces to prevent contact between them while spacing them a small distance apart to avoid the inflow of large amounts of air between the faces and into the vacuum chambers

  3. Core disruptive accident margin seal

    International Nuclear Information System (INIS)

    Golden, M.P.

    1979-01-01

    An apparatus for sealing the annulus defined within a substantially cylindrical rotatable riser assembly and plug combination of a nuclear reactor closure head is described. The apparatus comprises an inflatable sealing mechanism disposed in one portion of the riser assembly near the annulus such that upon inflation the sealing mechanism is radially actuated against the other portion of the riser assembly thereby sealing the annulus. The apparatus further comprises a connecting mechanism which places one end of the sealing mechanism in fluid communication with the reactor cover gas so that overpressurization of the reactor cover gas will increase the radial actuation of the sealing mechanism thus enhancing sealing of the annulus

  4. Self-acting shaft seals

    Science.gov (United States)

    Ludwig, L. P.

    1978-01-01

    Self-acting seals are described in detail. The mathematical models for obtaining a seal force balance and the equilibrium operating film thickness are outlined. Particular attention is given to primary ring response (seal vibration) to rotating seat face runout. This response analysis reveals three different vibration models with secondary seal friction being an important parameter. Leakage flow inlet pressure drop and affects of axisymmetric sealing face deformations are discussed. Experimental data on self-acting face seals operating under simulated gas turbine conditions are given. Also a spiral groove seal design operated to 244 m/sec (800 ft/sec) is described.

  5. Sealing arrangement for radioactive material

    International Nuclear Information System (INIS)

    Gray, I.L.S.; Sievwright, R.W.T.; Elliott, J.C.

    1993-01-01

    A sealing arrangement for hermetically sealing two mating surfaces comprises two seals arranged to lie between the surfaces. Each seal provides hermetic sealing over a respective different temperature range and lie serially along the surfaces between the regions to be isolated. A main seal integrity test arrangement is provided in the form of a port and passage. This allows for the introduction of a fluid into or the evacuation of a region between the two seals to detect a leak. The port is also provided with at least two test port seals which seal with a plug. The plug is also provided with a test port to allow the integrity of the test port seal to be tested. (UK)

  6. Nuclear instrumentation cable end seal

    International Nuclear Information System (INIS)

    Cannon, C.P.; Brown, D.P.

    1979-01-01

    An improved coaxial end seal for hermetically sealed nuclear instrumentation cable exhibiting an improved breakdown pulse noise characteristic under high voltage, high temperature conditions is described. A tubular insulator body has metallized interior and exterior surface portions which are braze sealed to a center conductor and an outer conductive sheath. The end surface of the insulator body which is directed toward the coaxial cable to which it is sealed has a recessed surface portion within which the braze seal material terminates

  7. Device for verification of seals by optical fibers

    International Nuclear Information System (INIS)

    Neuilly, M.; Guitaud, M.H.; Dufour, J.L.

    1993-01-01

    The seal is built around an optical fiber with a verification device. This device is made of a lighting source and photographic means supported by a rotating assembly which allow to take an image of each optical fiber end. These images are compared with reference images taken just after the sealing. (A.B.). 5 refs., 6 figs

  8. Pressure Actuated Leaf Seals for Improved Turbine Shaft Sealing

    Science.gov (United States)

    Grondahl, Clayton

    2006-01-01

    This presentation introduces a shaft seal in which leaf seal elements are constructed from slotted shim material formed and layered into a frusto-conical assembly. Limited elastic deflection of seal leaves with increasing system pressure close large startup clearance to a small, non-contacting, steady state running clearance. At shutdown seal elements resiliently retract as differential seal pressure diminishes. Large seal clearance during startup and shutdown provides a mechanism for rub avoidance. Minimum operating clearance improves performance and non-contacting operation promises long seal life. Design features of this seal, sample calculations at differential pressures up to 2400 psid and benefit comparison with brush and labyrinth seals is documented in paper, AIAA 2005 3985, presented at the Advanced Seal Technology session of the Joint Propulsion Conference in Tucson this past July. In this presentation use of bimetallic leaf material will be discussed. Frictional heating of bimetallic leaf seals during a seal rub can relieve the rub condition to some extent with a change in seal shape. Improved leaf seal rub tolerance is expected with bimetallic material.

  9. Spent fuels program

    International Nuclear Information System (INIS)

    Shappert, L.B.

    1983-01-01

    The goal of this task is to support the Domestic Spent Fuel Storage Program through studies involving the transport of spent fuel. A catalog was developed to provide authoritative, timely, and accessible transportation information for persons involved in the transport of irradiated reactor fuel. The catalog, drafted and submitted to the Transportation Technology Center, Sandia National Laboratories, for their review and approval, covers such topics as federal, state, and local regulations, spent fuel characteristics, cask characteristics, transportation costs, and emergency response information

  10. Spent fuel canister docking station

    International Nuclear Information System (INIS)

    Suikki, M.

    2006-01-01

    The working report for the spent fuel canister docking station presents a design for the operation and structure of the docking equipment located in the fuel handling cell for the spent fuel in the encapsulation plant. The report contains a description of the basic requirements for the docking station equipment and their implementation, the operation of the equipment, maintenance and a cost estimate. In the designing of the equipment all the problems related with the operation have been solved at the level of principle, nevertheless, detailed designing and the selection of final components have not yet been carried out. In case of defects and failures, solutions have been considered for postulated problems, and furthermore, the entire equipment was gone through by the means of systematic risk analysis (PFMEA). During the docking station designing we came across with needs to influence the structure of the actual disposal canister for spent nuclear fuel, too. Proposed changes for the structure of the steel lid fastening screw were included in the report. The report also contains a description of installation with the fuel handling cell structures. The purpose of the docking station for the fuel handling cell is to position and to seal the disposal canister for spent nuclear fuel into a penetration located on the cell floor and to provide suitable means for executing the loading of the disposal canister and the changing of atmosphere. The designed docking station consists of a docking ring, a covering hatch, a protective cone and an atmosphere-changing cap as well as the vacuum technology pertaining to the changing of atmosphere and the inert gas system. As far as the solutions are concerned, we have arrived at rather simple structures and most of the actuators of the system are situated outside of the actual fuel handling cell. When necessary, the equipment can also be used for the dismantling of a faulty disposal canister, cut from its upper end by machining. The

  11. International safeguards for spent fuel storage

    International Nuclear Information System (INIS)

    Kratzer, M.; Wonder, E.; Immerman, W.; Crane, F.

    1981-08-01

    This report analyzes the nonproliferation effectiveness and political and economic acceptability of prospective improvements in international safeguard techniques for LWR spent fuel storage. Although the applicability of item accounting considerably eases the safeguarding of stored spent fuel, the problem of verification is potentially serious. A number of simple gamma and neutron nondestructive assay techniques were found to offer considerable improvements, of a qualitative rather than quantitative nature, in verification-related data and information, and possess the major advantage of intruding very little on facility operations. A number of improved seals and monitors appear feasible as well, but improvements in the timeliness of detection will not occur unless the frequency of inspection is increased or a remote monitoring capability is established. Limitations on IAEA Safeguards resources and on the integration of results from material accounting and containment and surveillance remain problems

  12. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    Pajunen, A.L.

    1998-01-01

    Product specifications are limits and controls established for each significant parameter that potentially affects safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for transport to dry storage. The product specifications in this document cover the spent fuel packaged in MultiCanister Overpacks (MCOs) to be transported throughout the SNF Project. The SNF includes N Reactor fuel and single-pass reactor fuel. The FRS removes the SNF from the storage canisters, cleans it, and places it into baskets. The MCO loading system places the baskets into MCO/Cask assembly packages. These packages are then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the MCO cask packages are transferred to the Canister Storage Building (CSB), where the MCOs are removed from the casks, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The key criteria necessary to achieve these goals are documented in this specification

  13. Shaft seal assembly and method

    Science.gov (United States)

    Keba, John E. (Inventor)

    2007-01-01

    A pressure-actuated shaft seal assembly and associated method for controlling the flow of fluid adjacent a rotatable shaft are provided. The seal assembly includes one or more seal members that can be adjusted between open and closed positions, for example, according to the rotational speed of the shaft. For example, the seal member can be configured to be adjusted according to a radial pressure differential in a fluid that varies with the rotational speed of the shaft. In addition, in the closed position, each seal member can contact a rotatable member connected to the shaft to form a seal with the rotatable member and prevent fluid from flowing through the assembly. Thus, the seal can be closed at low speeds of operation and opened at high speeds of operation, thereby reducing the heat and wear in the seal assembly while maintaining a sufficient seal during all speeds of operation.

  14. Spent fuel storage for ISER plant

    International Nuclear Information System (INIS)

    Nakajima, Takasuke; Kimura, Yuzi

    1987-01-01

    ISER is an intrinsically safe reactor basing its safety only on physical laws, and uses a steel reactor vessel in order to be economical. For such a new type reactor, it is essentially important to be accepted by the society by showing that the reactor is more profitable than conventional reactors to the public in both technical and economic viewpoint. It is also important that the reactor raises no serious problem in the total fuel cycle. Reprocessing seems one of the major worldwide fuel cycle issues. Spent fuel storage is also one of the key technologies for fuel cycle back end. Various systems for ISER spent fuel storages are examined in the present report. Spent fuel specifications of ISER are similar to those of LWR and therefore, most of LWR spent fuel technologies are basically applicable to ISER spent fuel. Design requirements and examples of storage facilities are also discussed. Dry storage seems to be preferable for the relatively long cooling time spent fuel like ISER's one from economical viewpoint. Vault storage will possibly be the most advantageous for large storage capacity. Another point for discussion is the location and international collaboration for spent fuel storages: ISER expected to be a worldwide energy source and therefore, international spent fuel management seems to be fairly attractive way for an energy recipient country. (Nogami, K.)

  15. Pool gateway seal

    International Nuclear Information System (INIS)

    Starr, J.A.; Steinert, L.A.

    1983-01-01

    A device for sealing a gateway between interconnectable pools in a nuclear facility comprising a frame supporting a liquid impermeable sheet positioned in a u-shaped gateway between the pools. An inflatable tube carried in a channel in the periphery of the frame and adjoining the gateway provides a seal therebetween when inflated. A restraining arrangement on the bottom edge of the frame is releasably engagable with an adjacent portion of the gateway to restrict the movement of the frame in the u-shaped gateway upon inflation of the tube, thereby enhancing the seal. The impermeable sheet is formed of an elastomer and thus is conformable to a liquid permeable supportive wall upon application of liquid pressure to the side of the sheet opposite the wall

  16. HMSRP Hawaiian Monk Seal Master Identification Records (seal)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains records of all individually identified Hawaiian monk seals since 1981. These seals were identified by PSD personnel and cooperating scientists...

  17. Dye filled security seal

    International Nuclear Information System (INIS)

    Wilson, D.C.

    1982-01-01

    A security seal for providing an indication of unauthorized access to a sealed object includes an elongate member to be entwined in the object such that access is denied unless the member is removed. The elongate member has a hollow, pressurizable chamber extending throughout its length that is filled with a permanent dye under greater than atmospheric pressure. Attempts to cut the member and weld it together are revealed when dye flows through a rupture in the chamber wall and stains the outside surface of the member

  18. Sealed ion accelerator tubes (survey)

    International Nuclear Information System (INIS)

    Voitsik, L.R.

    1985-01-01

    The first publications on developing commercial models of small-scale sealed accelerator tubes in which neutrons are generated appeared in the foreign press in 1954 to 1957; they were very brief and were advertising-oriented. The tubes were designed for neutron logging of oil wells instead of ampule neutron sources (Po + Be, Ra + Be). Later, instruments of this type began to be called neutron tubes from the resulting neutron radiation that they gave off. In Soviet Union a neutron tube was developed in 1958 in connection with the development of the pulsed neutron-neutron method of studying the geological profile of oil wells. At that time the tube developed was intended, in the view of its inventors, to replace standard isotope sources with constant neutron yield. A fairly detailed survey of neutron tubes was made in the studies. 8 refs., 8 figs

  19. Cost saving synergistic shaft seal

    Science.gov (United States)

    Ludwig, L. P.; Strom, T. N.

    1976-01-01

    Segmented carbon rings, used to replace elastomeric seal lip, provide resistance to high temperatures generated in lubricating film. Machining and close manufacturing tolerances of conventional segmented seal are avoided by mounting segmented rings in elastomeric flex section.

  20. Magnetically Actuated Seal, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — FTT proposes development of a magnetically actuated dynamic seal. Dynamic seals are used throughout the turbopump in high-performance, pump-fed, liquid rocket...

  1. Magnetically Actuated Seal, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — FTT proposes development of a magnetically actuated dynamic seal. Dynamic seals are used throughout the turbopump in high-performance, pump-fed, liquid rocket...

  2. Continuous improvement of pump seals

    International Nuclear Information System (INIS)

    Wong, W.; Eyvindson, A.; Rhodes, D.B.

    2003-01-01

    Pump seal reliability continues to be an area needing improvement and ongoing vigilance. Methods have been developed for identifying and assessing factors relating to seal performance, selecting the most relevant ones for a specific station, and then focusing on the most significant aspects and how to improve. Discussion invariably addresses maintenance practices, seal design, monitoring capabilities, operating conditions, transients, and pump and motor design. Success in reliability improvement requires ongoing dialogue among the station operators, pump manufacturers and seal designers. AECL CAN-seals lead the nuclear industry in reliability and seal life. They effectively save operators millions of dollars in outage time and person-rem. This paper describes some of the significant developments in AECL's ongoing program in seal R and D, as well as recent new installations following the most demanding seal qualification programs to date. (author)

  3. Production of sealed sup 6 sup 0 Co and sup 1 sup 9 sup 2 Ir sources of high specific activity in the nuclear reactor RA

    International Nuclear Information System (INIS)

    Dobrijevic, R.; Vucina, J.

    1998-01-01

    Given is a review on the development of the production of 60 Co and 192 Ir performed in the Vinca Institute in the nuclear reactor RA. The experience gained showed that this reactor was suitable for obtaining of these and some other radionuclides. One possibility of its re-start is that the performances of the reactor remain the same (power 6.5 MW, max.neutron flux up to 6x10 13 n.cm -2 s -1 ). By applying new techniques of target preparation, 60 Co for sterilization units of specific activity 1.11 TBq/g could be produced. Maximal activity of sup 1 sup 9 sup 2 Ir would be about 1.48 TBq what is satisfactory for the sources for gamma radiography. The increase of the flux to 10 14 n.cm -2 s -1 would enable the production of 60 Co of specific activities about 3.335 TBq/g. This is satisfactory for the sources for the radiation therapy of activities up to 111 TBq and for gamma radiography of activities about 0.37 TBq. In the case of 192 Ir the sources for the radiation therapy of activities about 0.37 TBq could be obtained. Maximal achievable activities of 192 Ir would be about 3.7 TBq. (author)

  4. Spent nuclear fuel storage

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2005-01-01

    When a country becomes self-sufficient in part of the nuclear cycle, as production of fuel that will be used in nuclear power plants for energy generation, it is necessary to pay attention for the best method of storing the spent fuel. Temporary storage of spent nuclear fuel is a necessary practice and is applied nowadays all over the world, so much in countries that have not been defined their plan for a definitive repository, as well for those that already put in practice such storage form. There are two main aspects that involve the spent fuels: one regarding the spent nuclear fuel storage intended to reprocessing and the other in which the spent fuel will be sent for final deposition when the definitive place is defined, correctly located, appropriately characterized as to several technical aspects, and licentiate. This last aspect can involve decades of studies because of the technical and normative definitions at a given country. In Brazil, the interest is linked with the storage of spent fuels that will not be reprocessed. This work analyses possible types of storage, the international panorama and a proposal for future construction of a spent nuclear fuel temporary storage place in the country. (author)

  5. Intratracheal Seal Disc

    DEFF Research Database (Denmark)

    Christiansen, Karen J; Moeslund, Niels; Lauridsen, Henrik

    2017-01-01

    . The device consisted of an intratracheal silicone seal disc fixated by a cord through the stoma to an external part. At day 14, computed tomography (CT) was performed before the device was extracted. With the pulling of a cord, the disc unraveled into a thin thread and was extracted through the stoma. At day...

  6. GOLD PRESSURE VESSEL SEAL

    Science.gov (United States)

    Smith, A.E.

    1963-11-26

    An improved seal between the piston and die member of a piston-cylinder type pressure vessel is presented. A layer of gold, of sufficient thickness to provide an interference fit between the piston and die member, is plated on the contacting surface of at least one of the members. (AEC)

  7. Final environmental statement: US Spent Fuel Policy. Storage of foreign spent power reactor fuel

    International Nuclear Information System (INIS)

    1980-05-01

    In October 1977, the Department of Energy (DOE) announced a Spent Fuel Storage Policy for nuclear power reactors. Under this policy, as approved by the President, US utilities will be given the opportunity to deliver spent fuel to US Government custody in exchange for payment of a fee. The US Government will also be prepared to accept a limited amount of spent fuel from foreign sources when such action would contribute to meeting nonproliferation goals. Under the new policy, spent fuel transferred to the US Government will be delivered - at user expense - to a US Government-approved site. Foreign spent fuel would be stored in Interim Spent Fuel Storage (ISFS) facilities with domestic fuel. This volume of the environmental impact statement includes effects associated with implementing or not implementing the Spent Fuel Storage Policy for the foreign fuels. The analyses show that there are no substantial radiological health impacts whether the policy is implemented or not. In no case considered does the population dose commitment exceed 0.000006% of the world population dose commitment from natural radiation sources over the period analyzed. Full implementation of the US offer to accept a limited amount of foreign spent fuel for storage provides the greatest benefits for US nonproliferation policy. Acceptance of lesser quantities of foreign spent fuel in the US or less US support of foreign spent fuel storage abroad provides some nonproliferation benefits, but at a significantly lower level than full implementation of the offer. Not implementing the policy in regard to foreign spent fuel will be least productive in the context of US nonproliferation objectives. The remainder of the summary provides a brief description of the options that are evaluated, the facilities involved in these options, and the environmental impacts, including nonproliferation considerations, associated with each option

  8. Shaft Seal Compensates for Cold Flow

    Science.gov (United States)

    Myers, W. N.; Hein, L. A.

    1985-01-01

    Seal components easy to install. Ring seal for rotating or reciprocating shafts spring-loaded to compensate for slow yielding (cold flow) of sealing material. New seal relatively easy to install because components preassembled, then installed in one piece.

  9. Fiber Optic Safeguards Sealing System

    Science.gov (United States)

    1978-01-01

    8217 or trade names does not constitute an official indorsement or approval of the use thereof. Destroy this report when it is no longer needed. Do not...an intergrity check of a seal than to photograph the seal’s fingerprints and to match positive/negative overlays. The seal identification time and

  10. Ultrasonic dip seal maintenance system

    International Nuclear Information System (INIS)

    Poindexter, A.M.; Ricks, H.E.

    1978-01-01

    Disclosed is a system for removing impurities from the surfaces of liquid dip seals and for wetting the metal surfaces of liquid dip seals in nuclear components. The system comprises an ultrasonic transducer that transmits ultrasonic vibrations along an ultrasonic probe to the metal and liquid surfaces of the dip seal thereby loosening and removing those impurities

  11. Radial lip seals, thermal aspects

    NARCIS (Netherlands)

    Stakenborg, M.J.L.; van Ostaijen, R.A.J.; Dowson, D.

    1989-01-01

    In this paper the influence of temperature on tne seal-snarc contact is studied, using coupled temperature-stress FEH analysis. A thermal network model is used to calculate the seal-shaft contact temperature for steady-state and transient conditions. Contact temperatures were measured under the seal

  12. Cover gas seals: FFTF-LMFBR seal test program

    International Nuclear Information System (INIS)

    Kurzeka, W.; Oliva, R.; Welch, T.S.; Shimazaki, T.

    1974-01-01

    The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor-inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels

  13. Thermal neutron imaging with rare-earth-ion-doped LiCaAlF6 scintillators and a sealed 252Cf source

    International Nuclear Information System (INIS)

    Kawaguchi, Noriaki; Yanagida, Takayuki; Fujimoto, Yutaka; Yokota, Yuui; Kamada, Kei; Fukuda, Kentaro; Suyama, Toshihisa; Watanabe, Kenichi; Yamazaki, Atsushi; Chani, Valery; Yoshikawa, Akira

    2011-01-01

    Thermal neutron imaging with Ce-doped LiCaAlF 6 crystals has been performed. The prototype of the neutron imager using a Ce-doped LiCaAlF 6 scintillating crystal and a position sensitive photomultiplier tube (PSPMT) which had 64 multi-channel anode was developed. The Ce-doped LiCaAlF 6 single crystal was grown by the Czochralski method. A plate with dimensions of a diameter of 50x2 mm 2 was cut from the grown crystal, polished, and optically coupled to PSPMT by silicone grease. The 252 Cf source ( 6 .

  14. Failure analysis and seal life prediction for contacting mechanical seals

    Science.gov (United States)

    Sun, J. J.; He, X. Y.; Wei, L.; Feng, X.

    2008-11-01

    Fault tree analysis method was applied to quantitatively investigate the causes of the leakage failure of mechanical seals. It is pointed out that the change of the surface topography is the main reasons causing the leakage of mechanical seals under the condition of constant preloads. Based on the fractal geometry theory, the relationship between the surface topography and working time were investigated by experiments, and the effects of unit load acting on seal face on leakage path in a mechanical seal were analyzed. The model of predicting seal life of mechanical seals was established on the basis of the relationship between the surface topography and working time and allowable leakage. The seal life of 108 mechanical seal operating at the system of diesel fuel storage and transportation was predicted and the problem of the condition monitoring for the long-period operation of mechanical seal was discussed by this method. The research results indicate that the method of predicting seal life of mechanical seals is feasible, and also is foundation to make scheduled maintenance time and to achieve safe-reliability and low-cost operation for industrial devices.

  15. Spent sulfite liquor developments

    Energy Technology Data Exchange (ETDEWEB)

    Black, H H

    1958-01-01

    A review of methods of utilizing spent sulfite liquor, including evaporation and burning, fermentation to produce yeast or alcohol, production of vanillin and lignosulfonates, and use as a roadbinder.

  16. Spent fuel workshop'2002

    International Nuclear Information System (INIS)

    Poinssot, Ch.

    2002-01-01

    This document gathers the transparencies of the presentations given at the 2002 spent fuel workshop: Session 1 - Research Projects: Overview on the IN CAN PROCESSES European project (M. Cowper), Overview on the SPENT FUEL STABILITY European project (C. Poinssot), Overview on the French R and D project on spent fuel long term evolution, PRECCI (C. Poinssot); Session 2 - Spent Fuel Oxidation: Oxidation of uranium dioxide single crystals (F. Garrido), Experimental results on SF oxidation and new modeling approach (L. Desgranges), LWR spent fuel oxidation - effects of burn-up and humidity (B. Hanson), An approach to modeling CANDU fuel oxidation under dry storage conditions (P. Taylor); Session 3 - Spent Fuel Dissolution Experiments: Overview on high burnup spent fuel dissolution studies at FZK/INE (A. Loida), Results on the influence of hydrogen on spent fuel leaching (K. Spahiu), Leaching of spent UO 2 fuel under inert and reducing conditions (Y. Albinsson), Fuel corrosion investigation by electrochemical techniques (D. Wegen), A reanalysis of LWR spent fuel flow through dissolution tests (B. Hanson), U-bearing secondary phases formed during fuel corrosion (R. Finch), The near-field chemical conditions and spent fuel leaching (D. Cui), The release of radionuclides from spent fuel in bentonite block (S.S. Kim), Trace actinide behavior in altered spent fuel (E. Buck, B. Hanson); Session 4 - Radiolysis Issues: The effect of radiolysis on UO 2 dissolution determined from electrochemical experiments with 238 Pu doped UO 2 M. Stroess-Gascoyne (F. King, J.S. Betteridge, F. Garisto), doped UO 2 studies (V. Rondinella), Preliminary results of static and dynamic dissolution tests with α doped UO 2 in Boom clay conditions (K. Lemmens), Studies of the behavior of UO 2 / water interfaces under He 2+ beam (C. Corbel), Alpha and gamma radiolysis effects on UO 2 alteration in water (C. Jegou), Behavior of Pu-doped pellets in brines (M. Kelm), On the potential catalytic behavior of

  17. Thermal test and analysis of a spent fuel storage cask

    International Nuclear Information System (INIS)

    Yamakawa, H.; Gomi, Y.; Ozaki, S.; Kosaki, A.

    1993-01-01

    A thermal test simulated with full-scale cask model for the normal storage was performed to verify the storage skill of the spent fuels of the cask. The maximum temperature at each point in the test was lower than the allowable temperature. The integrity of the cask was maintained. It was observed that the safety of containment system was also kept according to the check of the seal before and after the thermal test. Therefore it was shown that using the present skill, it is possible to store spent fuels in the dry-type cask safely. Moreover, because of the good agreement between analysis and experimental results, it was shown that the analysis model was successfully established to estimate the temperature distribution of the fuel cladding and the seal portion. (J.P.N.)

  18. Refrigeration system with clearance seals

    International Nuclear Information System (INIS)

    Holland, N. J.

    1985-01-01

    In a refrigeration system such as a split Stirling system, fluid seals associated with the reciprocating displacer are virtually dragless clearance seals. Movement of the displacer relative to the pressure variations in the working volume of gas is retarded by a discrete braking element. Because it is not necessary that the brake providing any sealing action, the brake can be designed for greater durability and less dependence on ambient and operating temperatures. Similarly, the clearance seal can be formed of elements having low thermal expansion such that the seal is not temperature dependent. In the primary embodiments the braking element is a split friction brake

  19. Hermetic Seal Leak Detection Apparatus

    Science.gov (United States)

    Kelley, Anthony R. (Inventor)

    2013-01-01

    The present invention is a hermetic seal leak detection apparatus, which can be used to test for hermetic seal leaks in instruments and containers. A vacuum tight chamber is created around the unit being tested to minimize gas space outside of the hermetic seal. A vacuum inducing device is then used to increase the gas chamber volume inside the device, so that a slight vacuum is pulled on the unit being tested. The pressure in the unit being tested will stabilize. If the stabilized pressure reads close to a known good seal calibration, there is not a leak in the seal. If the stabilized pressure reads closer to a known bad seal calibration value, there is a leak in the seal. The speed of the plunger can be varied and by evaluating the resulting pressure change rates and final values, the leak rate/size can be accurately calculated.

  20. Regenerator cross arm seal assembly

    Science.gov (United States)

    Jackman, Anthony V.

    1988-01-01

    A seal assembly for disposition between a cross arm on a gas turbine engine block and a regenerator disc, the seal assembly including a platform coextensive with the cross arm, a seal and wear layer sealingly and slidingly engaging the regenerator disc, a porous and compliant support layer between the platform and the seal and wear layer porous enough to permit flow of cooling air therethrough and compliant to accommodate relative thermal growth and distortion, a dike between the seal and wear layer and the platform for preventing cross flow through the support layer between engine exhaust and pressurized air passages, and air diversion passages for directing unregenerated pressurized air through the support layer to cool the seal and wear layer and then back into the flow of regenerated pressurized air.

  1. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements

    International Nuclear Information System (INIS)

    KLEM, M.J.

    2000-01-01

    In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8.0 References lists the

  2. Sealed source and device design safety testing. Technical report on the findings of task 4. Investigation of a failed brachtherapy needle applicator

    International Nuclear Information System (INIS)

    Lukezich, S.J.

    1997-05-01

    As a result of an incident in which a radioactive brachytherapy treatment source was temporarily unable to be retracted, an analysis was performed on the needle applicator used during the treatment. In this report, the results of laboratory evaluations of the physical, mechanical, and metallurgical condition of the subject applicator and two additional applicators are presented. A kink formed in the subject applicator during the incident. The laboratory investigation focused on identifying characteristics which would increase the susceptibility of an applicator to form a kink when subjected to bending loads. The results obtained during this investigation could not conclusively identify the cause of the kink. The subject applicator exhibited no unique features which would have made it particularly susceptible to forming a kink. The three applicators examined represent two methods of manufacturing. A number of characteristics inherent to the method used to manufacture the subject applicator which could lead to an increased susceptibility to the formation of a kink were observed. The use of an insertion device, such as the biopsy needle used during this incident, could also dramatically increase the likelihood of the formation of a kink if the applicator is subjected to bending loads. 33 figs., 4 tabs

  3. Sealing wells with gel

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, E C

    1967-10-01

    A new system is being used in Mexico to temporarily plug producing wells. The temporary seal is a gel with a catalyst. The use of this temporary plug allows gas-lift wells to be taken off production in order to carry out emergency repairs. The gel solidifies by the action of the catalyst to a high temperature (70 - 150/sup 0/C). By locating the bottom of the tubing at the top of the production interval, the gel material will go into the permeable formation, and immediately set. When the gel has solidified, it seals off the horizon that must not be stimulated, and leaves the others exposed to the acid action. When the treatment is finished, the gel, by action of the catalyst, is liquefied and removed from the formation, being produced with the oil.

  4. Radioactive waste sealing container

    International Nuclear Information System (INIS)

    Tozawa, S.; Kitamura, T.; Sugimoto, S.

    1984-01-01

    A low- to medium-level radioactive waste sealing container is constructed by depositing a foundation coating consisting essentially of zinc, cadmium or a zinc-aluminum alloy over a steel base, then coating an organic synthetic resin paint containing a metal phosphate over the foundation coating, and thereafter coating an acryl resin, epoxy resin, and/or polyurethane paint. The sealing container can consist of a main container body, a lid placed over the main body, and fixing members for clamping and fixing the lid to the main body. Each fixing member may consist of a material obtained by depositing a coating consisting essentially of cadmium or a zinc-aluminum alloy over a steel base

  5. Spent fuel storage requirements 1987

    International Nuclear Information System (INIS)

    1987-09-01

    Historical inventories of spent fuel and utility estimates of future discharges from US commercial nuclear reactors are presented through the year 2005. The ultimate needs for additional storage capacity are estimated. These estimtes are based on the maximum capacities within current and planned at-reactor facilities and on any planned transshipments of fuel to other reactors or facilities. Historical data through December, 1986, and projected discharges through the end of reactor life are used in this analysis. The source data was supplied by the utilities to the DOE Energy Information Administration (EIA) through the 1987 RW-859 data survey. 14 refs., 4 figs., 9 tabs

  6. Electromagnetic shaft seal

    International Nuclear Information System (INIS)

    Takahashi, Kenji.

    1994-01-01

    As an electromagnetic shaft seal, there are disposed outwarding electromagnetic induction devices having generating power directing to an electroconductive fluid as an object of sealing, and inwarding electromagnetic induction device added coaxially. There are disposed elongate rectangular looped first coils having a predetermined inner diameter, second coils having the same shape and shifted by a predetermined pitch relative to the first coil and third coil having the same shape and shifted by a predetermined pitch relative to the second coil respectively each at a predetermined inner diameter of clearance to the outwarding electromagnetic induction devices and the inwarding electromagnetic induction device. If the inwarding electromagnetic induction device and the outwarding electromagnetic induction device are operated, they are stopped at a point that the generating power of the former is equal with the sum of the generating power of the latter and a differential pressure. When three-phase AC is charged to the first coil, the second coil and the third coil successively, a force is generated in the advancing direction of the magnetic field in the electroconductive fluid by the similar effect to that of a linear motor, and the seal is maintained at high reliability. Moreover, the limit for the rotational angle of the shaft is not caused. (N.H.)

  7. Separation and preconcentration of platinum-group metals from spent autocatalysts solutions using a hetero-polymeric S, N-containing sorbent and determination by high-resolution continuum source graphite furnace atomic absorption spectrometry.

    Science.gov (United States)

    Eskina, Vasilina V; Dalnova, Olga A; Filatova, Daria G; Baranovskaya, Vasilisa B; Karpov, Yuri A

    2016-10-01

    This paper describes the potential of high-resolution continuum source graphite furnace atomic absorption spectrometry for determination of Pt, Pd and Rh after separation and concentration by original in-house developed heterochain polymer S, N-containing sorbent. The methods of sample preparation of spent ceramic-based autocatalysts were considered, two of which were used: autoclave decomposition in mixture of acids HCl:HNO3 (3:1) and high-temperature melting with K2S2O7. Both methods anyway limit the direct determination of analytes by HR CS GFAAS. Using the first method it is an incomplete digestion of spent autocatalysts samples, since the precipitate is Si, and the rhodium metal dissolves with difficulty and partially passes into solution. In contrast to the first method, the second method allow to completely transfer analytes into solution, however, the background signal produced by the chemical composition of the flux, overlaps the analytical zone. It was found, that Pt, Pd and Rh contained in the spent ceramic automotive catalysts could be effectively separated and concentrated by heterochain polymer S, N-containing sorbent, which has high sorption capacity, selectivity and resistant to dilute acids. The chosen HR CS GFAAS analysis conditions enable us to determine Pt, Pd and Rh with good metrological characteristics. The concentrations of Pt, Pd and Rh in two samples of automobile exhaust catalysts were found in range of 0.00015-0.00050; 0.170-0.189; 0.0180-0.0210wt%, respectively. The relative standard deviation obtained by HR CS GFAAS was not more than 5%. Limits of detection by HR CS GFAAS achieved were 6.2·10(-6)wt% for Pt, 1.8·10(-6)wt% for Pd, and 3.4·10(-6)wt% for Rh. Limits of determination achieved by HR CS GFAAS were 1.1·10(-5)wt% for Pt, 6.9·10(-5)wt% for Pd, and 8.3·10(-5)wt% for Rh. To control the accuracy of PGM in sorption concentrates by HR CS GFAAS method, it was appropriate to conduct an inter-method comparative experiment. The

  8. Spent fuel storage facility, Kalpakkam

    International Nuclear Information System (INIS)

    Shreekumar, B.; Anthony, S.

    2017-01-01

    Spent Fuel Storage Facility (SFSF), Kalpakkam is designed to store spent fuel arising from PHWRs. Spent fuel is transported in AERB qualified/authorized shipping cask by NPCIL to SFSF by road or rail route. The spent fuel storage facility at Kalpakkam was hot commissioned in December 2006. All systems, structures and components (SSCs) related to safety are designed to meet the operational requirements

  9. Disposal of spent fuel

    International Nuclear Information System (INIS)

    Blomeke, J.O.; Ferguson, D.E.; Croff, A.G.

    1978-01-01

    Based on preliminary analyses, spent fuel assemblies are an acceptable form for waste disposal. The following studies appear necessary to bring our knowledge of spent fuel as a final disposal form to a level comparable with that of the solidified wastes from reprocessing: 1. A complete systems analysis is needed of spent fuel disposition from reactor discharge to final isolation in a repository. 2. Since it appears desirable to encase the spent fuel assembly in a metal canister, candidate materials for this container need to be studied. 3. It is highly likely that some ''filler'' material will be needed between the fuel elements and the can. 4. Leachability, stability, and waste-rock interaction studies should be carried out on the fuels. The major disadvantages of spent fuel as a disposal form are the lower maximum heat loading, 60 kW/acre versus 150 kW/acre for high-level waste from a reprocessing plant; the greater long-term potential hazard due to the larger quantities of plutonium and uranium introduced into a repository; and the possibility of criticality in case the repository is breached. The major advantages are the lower cost and increased near-term safety resulting from eliminating reprocessing and the treatment and handling of the wastes therefrom

  10. Development on application of ultrasonic sealing techniques to plutonium transportation cask

    International Nuclear Information System (INIS)

    Hayakawa, Tsuyoshi; Akiba, Mitsunori; D'Agraives, B.C.

    1994-01-01

    In a cooperation research between Power Reactor and Nuclear Fuel Development Corporation and Commission of the European Communities, Joint Research Centre, Ispra establishment, application of ultrasonic sealing techniques to a plutonium container is developed in Ispra. The seal is derived from the sealing-bolt technology currently in use at the BNFL site of sellafield (UK) for the safeguarding of underwater spent fuel storage containers called MEBs. In this technique, one of the normal bolts closing the lid of the container is replaced by a special ultrasonically verifiable sealing-bolt. In the application to the plutonium container, it is proposed to attach a clamping seal which has the same internal configuration as a MEB sealing-bolt but is fastened with a 'one-way' mechanism to one of the protruding pins of the container. Similarly the seal is provided with an identity and integrity features. The uniqueness of the identity, as well as the integrity can be checked on the spot by an inspector carrying a reading equipment. Thus, in a few minutes, one identifies the seal and knows whether its integrity is intact, which tells that the container has not been opened or attempted to open illeagally. By application of the seal to the plutonium container, the containment/surveillance during the transportation will be upgraded. (author)

  11. Closure and Sealing Design Calculation

    International Nuclear Information System (INIS)

    T. Lahnalampi; J. Case

    2005-01-01

    The purpose of the ''Closure and Sealing Design Calculation'' is to illustrate closure and sealing methods for sealing shafts, ramps, and identify boreholes that require sealing in order to limit the potential of water infiltration. In addition, this calculation will provide a description of the magma that can reduce the consequences of an igneous event intersecting the repository. This calculation will also include a listing of the project requirements related to closure and sealing. The scope of this calculation is to: summarize applicable project requirements and codes relating to backfilling nonemplacement openings, removal of uncommitted materials from the subsurface, installation of drip shields, and erecting monuments; compile an inventory of boreholes that are found in the area of the subsurface repository; describe the magma bulkhead feature and location; and include figures for the proposed shaft and ramp seals. The objective of this calculation is to: categorize the boreholes for sealing by depth and proximity to the subsurface repository; develop drawing figures which show the location and geometry for the magma bulkhead; include the shaft seal figures and a proposed construction sequence; and include the ramp seal figure and a proposed construction sequence. The intent of this closure and sealing calculation is to support the License Application by providing a description of the closure and sealing methods for the Safety Analysis Report. The closure and sealing calculation will also provide input for Post Closure Activities by describing the location of the magma bulkhead. This calculation is limited to describing the final configuration of the sealing and backfill systems for the underground area. The methods and procedures used to place the backfill and remove uncommitted materials (such as concrete) from the repository and detailed design of the magma bulkhead will be the subject of separate analyses or calculations. Post-closure monitoring will not

  12. TECHNOLOGY ROADMAPPING FOR IAEA SEALS.

    Energy Technology Data Exchange (ETDEWEB)

    HOFFHEINS,B.; ANNESE,C.; GOODMAN,M.; OCONNOR,W.; GUSHUE,S.; PEPPER,S.

    2003-07-13

    In the fall of 2002, the U.S. Support Program (USSP) initiated an effort to define a strategy or ''roadmap'' for future seals technologies and to develop a generalized process for planning safeguards equipment development, which includes seals and other safeguards equipment. The underlying objectives of the USSP include becoming more proactive than reactive in addressing safeguards equipment needs, helping the IAEA to maintain an inventory of cost-effective, reliable, and effective safeguards equipment, establishing a long-term planning horizon, and securing IAEA ownership in the process of effective requirements definition and timely transitioning of new or improved systems for IAEA use. At an initial workshop, seals, their functions, performance issues, and future embodiments were discussed in the following order: adhesive seals, metal seals, passive and active loop seals, ultrasonic seals, tamper indicating enclosures (including sample containers, equipment enclosures, and conduits). Suggested improvements to these technologies focused largely on a few themes: (1) The seals must be applied quickly, easily, and correctly; (2) Seals and their associated equipment should not unduly add bulk or weight to the inspectors load; (3) Rapid, in-situ verifiability of seals is desirable; and (4) Seal systems for high risk or high value applications should have two-way, remote communications. Based upon these observations and other insights, the participants constructed a skeletal approach for seals technology planning. The process begins with a top-level review of the fundamental safeguards requirements and extraction of required system features, which is followed by analysis of suitable technologies and identification of technology gaps, and finally by development of a planning schedule for system improvements and new technology integration. Development of a comprehensive procedure will require the partnership and participation of the IAEA. The

  13. Design of repository sealing systems - 1981

    International Nuclear Information System (INIS)

    Ellison, R.D.; Shukla, D.K.; Kelsall, P.C.; D'Appolonia Consulting Engineers, Albuquerque, NM)

    1982-01-01

    Isolating nuclear waste in geologic repositories will require the sealing of penetrations such as access shafts and tunnels, disposal rooms, and exploration boreholes. This paper discusses seal designs developed for a repository in bedded salt referenced to the stratigraphy of southeastern New Mexico. Designs are based on a multiple component concept whereby individual components are designed for a specific function and location. For a repository in salt the major function of the seals is to exclude groundwater inflow. Two main types of component are included for this purpose: (1) bulk-heads are dense concrete structures keyed into the walls of the penetration and are intended to reduce flow at the interface between the seal and the salt; (2) backfills are granular materials compacted in place in the penetration. In the repository the major backfill material is crushed salt, which is expected to consolidate and recrystallize as the rooms close in response to salt creep. Densely compacted clays will be used as backfill in the shafts closer to potential sources of water inflow. 22 references, 10 figures, 1 table

  14. Guidebook on spent fuel storage

    International Nuclear Information System (INIS)

    1984-01-01

    The Guidebook summarizes the experience and information in various areas related to spent fuel storage: technological aspects, the transport of spent fuel, economical, regulatory and institutional aspects, international safeguards, evaluation criteria for the selection of a specific spent fuel storage concept, international cooperation on spent fuel storage. The last part of the Guidebook presents specific problems on the spent fuel storage in the United Kingdom, Sweden, USSR, USA, Federal Republic of Germany and Switzerland

  15. Spent fuel pyroprocessing demonstration

    International Nuclear Information System (INIS)

    McFarlane, L.F.; Lineberry, M.J.

    1995-01-01

    A major element of the shutdown of the US liquid metal reactor development program is managing the sodium-bonded spent metallic fuel from the Experimental Breeder Reactor-II to meet US environmental laws. Argonne National Laboratory has refurbished and equipped an existing hot cell facility for treating the spent fuel by a high-temperature electrochemical process commonly called pyroprocessing. Four products will be produced for storage and disposal. Two high-level waste forms will be produced and qualified for disposal of the fission and activation products. Uranium and transuranium alloys will be produced for storage pending a decision by the US Department of Energy on the fate of its plutonium and enriched uranium. Together these activities will demonstrate a unique electrochemical treatment technology for spent nuclear fuel. This technology potentially has significant economic and technical advantages over either conventional reprocessing or direct disposal as a high-level waste option

  16. Spent Fuel in Chile

    International Nuclear Information System (INIS)

    López Lizana, F.

    2015-01-01

    The government has made a complete and serious study of many different aspects and possible road maps for nuclear electric power with strong emphasis on safety and energy independence. In the study, the chapter of SFM has not been a relevant issue at this early stage due to the fact that it has been left for later implementation stage. This paper deals with the options Chile might consider in managing its Spent Fuel taking into account foreign experience and factors related to safety, economics, public acceptance and possible novel approaches in spent fuel treatment. The country’s distinctiveness and past experience in this area taking into account that Chile has two research reactors which will have an influence in the design of the Spent Fuel option. (author)

  17. Use of rice rusk ash and spent catalyst as a source of raw material for the production and characterization of soda-lime silicate glasses destined for packaging

    International Nuclear Information System (INIS)

    Araujo, M.S.; Martinelli, J.R.; Genova, L.A.; Prado, U.S. do

    2016-01-01

    Study on the use of rice husk ash (RHA) and waste catalyst (ECAT), two industrial solid waste generated in large quantities in Brazil, getting soda-lime glass for the production of packaging. Both the waste may be classified as class II waste according to NBR 10,004. Samples were produced adding Na_2CO_3 and CaO to obtain a composition within the range of commercial soda-lime glasses. The results showed that both can be used as received (without any previous treatment) replacing important raw materials, source of Al_2O_3 and SiO2, necessary for glass formation. The produced samples were amber due to the presence of nickel (Ni2+ ions) from the ECAT and optical transmittance of 18%. These also showed good homogeneity, i.e., absence of bubbles and striae and dissolution rate higher than a commercial soda-lime glass. In general, the samples are presented suitable for applications that require low transmittance such as colored glass containers, which does not require perfect visibility and transparency. Finally, the waste level of incorporation was approximately 78 mass%. (author)

  18. Development of advanced spent fuel management process

    International Nuclear Information System (INIS)

    Park, Seong Won; Shin, Y. J.; Cho, S. H.

    2004-03-01

    The research on spent fuel management focuses on the maximization of the disposal efficiency by a volume reduction, the improvement of the environmental friendliness by the partitioning and transmutation of the long lived nuclides, and the recycling of the spent fuel for an efficient utilization of the uranium source. In the second phase which started in 2001, the performance test of the advanced spent fuel management process consisting of voloxidation, reduction of spent fuel and the lithium recovery process has been completed successfully on a laboratory scale. The world-premier spent fuel reduction hot test of a 5 kgHM/batch has been performed successfully by joint research with Russia and the valuable data on the actinides and FPs material balance and the characteristics of the metal product were obtained with experience to help design an engineering scale reduction system. The electrolytic reduction technology which integrates uranium oxide reduction in a molten LiCl-Li 2 O system and Li 2 O electrolysis is developed and a unique reaction system is also devised. Design data such as the treatment capacity, current density and mass transfer behavior obtained from the performance test of a 5 kgU/batch electrolytic reduction system pave the way for the third phase of the hot cell demonstration of the advanced spent fuel management technology

  19. Investigation of novel spent fuel verification system for safeguard application

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Haneol; Yim, Man-Sung [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    Radioactive waste, especially spent fuel, is generated from the operation of nuclear power plants. The final stage of radioactive waste management is disposal which isolates radioactive waste from the accessible environment and allows it to decay. The safety, security, and safeguard of a spent fuel repository have to be evaluated before its operation. Many researchers have evaluated the safety of a repository. These researchers calculated dose to public after the repository is closed depending on their scenario. Because most spent fuel repositories are non-retrievable, research on security or safeguards of spent fuel repositories have to be performed. Design based security or safeguard have to be developed for future repository designs. This study summarizes the requirements of future spent fuel repositories especially safeguards, and suggests a novel system which meets the safeguard requirements. Applying safeguards to a spent fuel repository is becoming increasingly important. The future requirements for a spent fuel repository are suggested by several expert groups, such as ASTOR in IAEA. The requirements emphasizes surveillance and verification. The surveillance and verification of spent fuel is currently accomplished by using the Cerenkov radiation detector while spent fuel is being stored in a fuel pool. This research investigated an advanced spent fuel verification system using a system which converts spent fuel radiation into electricity. The system generates electricity while it is conveyed from a transportation cask to a disposal cask. The electricity conversion system was verified in a lab scale experiment using an 8.51GBq Cs-137 gamma source.

  20. Investigation of novel spent fuel verification system for safeguard application

    International Nuclear Information System (INIS)

    Lee, Haneol; Yim, Man-Sung

    2016-01-01

    Radioactive waste, especially spent fuel, is generated from the operation of nuclear power plants. The final stage of radioactive waste management is disposal which isolates radioactive waste from the accessible environment and allows it to decay. The safety, security, and safeguard of a spent fuel repository have to be evaluated before its operation. Many researchers have evaluated the safety of a repository. These researchers calculated dose to public after the repository is closed depending on their scenario. Because most spent fuel repositories are non-retrievable, research on security or safeguards of spent fuel repositories have to be performed. Design based security or safeguard have to be developed for future repository designs. This study summarizes the requirements of future spent fuel repositories especially safeguards, and suggests a novel system which meets the safeguard requirements. Applying safeguards to a spent fuel repository is becoming increasingly important. The future requirements for a spent fuel repository are suggested by several expert groups, such as ASTOR in IAEA. The requirements emphasizes surveillance and verification. The surveillance and verification of spent fuel is currently accomplished by using the Cerenkov radiation detector while spent fuel is being stored in a fuel pool. This research investigated an advanced spent fuel verification system using a system which converts spent fuel radiation into electricity. The system generates electricity while it is conveyed from a transportation cask to a disposal cask. The electricity conversion system was verified in a lab scale experiment using an 8.51GBq Cs-137 gamma source

  1. Remote Monitoring of Instrumentation in Sealed Compartments

    International Nuclear Information System (INIS)

    Landron, Clinton; Moser, John C.

    1999-01-01

    The Instrumentation and Telemetry Departments at Sandia National Laboratories have been exploring the instrumentation of sealed canisters where the flight application will not tolerate either the presence of a chemical power source or penetration by power supply wires. This paper will describe the application of a low power micro-controller based instrumentation system that uses magnetic coupling for both power and data to support a flight application

  2. Order of the 13. of October 2009 approving the decision no 2009-DC-0150 of the Nuclear Safety Authority on the 16. of July 2009 defining the technical criteria on which relies the prolongation of the use duration of sealed radioactive sources awarded according to the R. 1333-52 article of the Public Health Code

    International Nuclear Information System (INIS)

    2010-01-01

    This legal publication defines the technical framework for the prolongation of the use of sealed radioactive sources beyond the ten-year period which had been initially defined. It defines the sources which are concerned, those which are not, or need a specific request. It defines the required controls and verifications, the usage conditions for species used in different systems present in electronuclear reactors. It describes the content and the associated administrative procedure of a prolongation request, as well as the consequences of a loss of integrity of a source

  3. Spent fuel reprocessing options

    International Nuclear Information System (INIS)

    2008-08-01

    The objective of this publication is to provide an update on the latest developments in nuclear reprocessing technologies in the light of new developments on the global nuclear scene. The background information on spent fuel reprocessing is provided in Section One. Substantial global growth of nuclear electricity generation is expected to occur during this century, in response to environmental issues and to assure the sustainability of the electrical energy supply in both industrial and less-developed countries. This growth carries with it an increasing responsibility to ensure that nuclear fuel cycle technologies are used only for peaceful purposes. In Section Two, an overview of the options for spent fuel reprocessing and their level of development are provided. A number of options exist for the treatment of spent fuel. Some, including those that avoid separation of a pure plutonium stream, are at an advanced level of technological maturity. These could be deployed in the next generation of industrial-scale reprocessing plants, while others (such as dry methods) are at a pilot scale, laboratory scale or conceptual stage of development. In Section Three, research and development in support of advanced reprocessing options is described. Next-generation spent fuel reprocessing plants are likely to be based on aqueous extraction processes that can be designed to a country specific set of spent fuel partitioning criteria for recycling of fissile materials to advanced light water reactors or fast spectrum reactors. The physical design of these plants must incorporate effective means for materials accountancy, safeguards and physical protection. Section four deals with issues and challenges related to spent fuel reprocessing. The spent fuel reprocessing options assessment of economics, proliferation resistance, and environmental impact are discussed. The importance of public acceptance for a reprocessing strategy is discussed. A review of modelling tools to support the

  4. Shaft and tunnel sealing considerations

    International Nuclear Information System (INIS)

    Kelsall, P.C.; Shukla, D.K.

    1980-01-01

    Much of the emphasis of previous repository sealing research has been placed on plugging small diameter boreholes. It is increasingly evident that equal emphasis should now be given to shafts and tunnels which constitute more significant pathways between a repository and the biosphere. The paper discusses differences in requirements for sealing shafts and tunnels as compared with boreholes and the implications for seal design. Consideration is given to a design approach for shaft and tunnel seals based on a multiple component design concept, taking into account the requirements for retrievability of the waste. A work plan is developed for the future studies required to advance shaft and tunnel sealing technology to a level comparable with the existing technology for borehole sealing

  5. Test plan for Series 3 NNWSI spent fuel leaching/dissolution tests

    International Nuclear Information System (INIS)

    Wilson, C.N.

    1986-04-01

    The Series 3 tests will differ from the Series 2 tests in that the Series 3 tests will be run at 85 0 C (J-13 water) in sealed 304 stainless steel (SS) test vessels. The current NNWSI reference spent fuel container material is 304L SS. The candidate NNWSI repository horizon is above the water table, and 95 0 C (boiling temperature at the repository elevation) is the maximum liquid water temperature expected to contact spent fuel in the repository

  6. Sealing of rock fractures

    International Nuclear Information System (INIS)

    Pusch, R.; Erlstroem, M.; Boergesson, L.

    1985-12-01

    The major water-bearing fractures in granite usually from fairly regular sets but the extension and degree of connectivity is varying. This means that only a few fractures that are interconnected with the deposition holes and larger water-bearing structures in a HLW repository are expected and if they can be identified and cut off through sealing it would be possible to improve the isolation of waste packages very effectively. Nature's own fracture sealing mechanisms may be simulated and a survey of the involved processes actually suggests a number of possible filling methods and substances. Most of them require high temperature and pressure and correspondingly sophisticated techniques, but some are of potential interest for immediate application with rather moderate effort. Such a technique is to fill the fractures with clayey substances which stay flexible and low-permeable provided that they remain physically and chemically intact. It is demonstrated in the report that effective grouting requires a very low viscosity and shear strength of the substance and this can be achieved by mechanical agitation as demonstrated in this report. Thus, by superimposing static pressure and shear waves induced by percussion hammering at a suitable frequency, clays and fine-grained silts as well as cement can be driven into fractures with an average aperture as small as 0.1 mm. Experiments were made in the laboratory using concrete and steel plates, and a field pilot test was also conducted under realistic conditions on site in Stripa. They all demonstrated the practicality of the 'dynamic injection technique' and that the fluid condition of the grouts yielded complete filling of the injected space to a considerable distance from the injection point. The field test indicated a good sealing ability as well as a surprisingly high resistance to erosion and piping. (author)

  7. Low-Torque Seal Development

    Science.gov (United States)

    Lattime, Scott B.; Borowski, Richard

    2009-01-01

    The EcoTurn Class K production prototypes have passed all AAR qualification tests and received conditional approval. The accelerated life test on the second set of seals is in progress. Due to the performance of the first set, no problems are expected.The seal has demonstrated superior performance over the HDL seal in the test lab with virtually zero torque and excellent contamination exclusion and grease retention.

  8. SEAL FOR HIGH SPEED CENTRIFUGE

    Science.gov (United States)

    Skarstrom, C.W.

    1957-12-17

    A seal is described for a high speed centrifuge wherein the centrifugal force of rotation acts on the gasket to form a tight seal. The cylindrical rotating bowl of the centrifuge contains a closure member resting on a shoulder in the bowl wall having a lower surface containing bands of gasket material, parallel and adjacent to the cylinder wall. As the centrifuge speed increases, centrifugal force acts on the bands of gasket material forcing them in to a sealing contact against the cylinder wall. This arrangememt forms a simple and effective seal for high speed centrifuges, replacing more costly methods such as welding a closure in place.

  9. Advanced High Temperature Structural Seals

    Science.gov (United States)

    Newquist, Charles W.; Verzemnieks, Juris; Keller, Peter C.; Rorabaugh, Michael; Shorey, Mark

    2002-10-01

    This program addresses the development of high temperature structural seals for control surfaces for a new generation of small reusable launch vehicles. Successful development will contribute significantly to the mission goal of reducing launch cost for small, 200 to 300 pound payloads. Development of high temperature seals is mission enabling. For instance, ineffective control surface seals can result in high temperature (3100 F) flows in the elevon area exceeding structural material limits. Longer sealing life will allow use for many missions before replacement, contributing to the reduction of hardware, operation and launch costs.

  10. Borehole sealing method and apparatus

    International Nuclear Information System (INIS)

    Hartley, J.N.; Jansen, G. Jr.

    1977-01-01

    A method and apparatus is described for sealing boreholes in the earth. The borehole is blocked at the sealing level, and a sealing apparatus capable of melting rock and earth is positioned in the borehole just above seal level. The apparatus is heated to rock-melting temperature and powdered rock or other sealing material is transported down the borehole to the apparatus where it is melted, pooling on the mechanical block and allowed to cool and solidify, sealing the hole. Any length of the borehole can be sealed by slowly raising the apparatus in the borehole while continuously supplying powdered rock to the apparatus to be melted and added to the top of the column of molten and cooling rock, forming a continuous borehole seal. The sealing apparatus consists of a heater capable of melting rock, including means for supplying power to the heater, means for transporting powdered rock down the borehole to the heater, means for cooling the apparatus and means for positioning the apparatus in the borehole. 5 claims, 1 figure

  11. Reprocessing of spent plasma

    International Nuclear Information System (INIS)

    Pierini, G.

    1981-01-01

    This invention relates to a process for removing helium and other impurities from a mixture containing deuterium and tritium, a deuterium/tritium mixture when purified in accordance with such a process and, more particularly, to a process for the reprocessing of spent plasma removed from a thermofusion reactor. (U.K.)

  12. Joint seal in tank

    International Nuclear Information System (INIS)

    Colquhoun, J.; White, G.V.

    1981-01-01

    A seal for a joint or gap between edges of adjacent wall sections (e.g. of concrete) of a liquid-containing vessel, such as a nuclear reactor cooling pond, comprises a sheet metal strip having longitudinally-extending edge parts, secured to the respective vessel-section edges, and a central part which is longitudinally corrugated to provide sufficient flexibility to accommodate slight relative movements between the vessel-section edges (e.g. due to thermal expansions). The edges of the sheet metal of the strip are turned in so that the edge parts of the strip are formed as generally U-section channels. These accommodate longitudinally extending securing bars which are bolted to the vessel wall sections by bolts which pass through the bars, through the free-edged wall of the channel section and through a longitudinally extending resilient seal pad compressed between that wall of the channel section and the vessel wall section to which it is secured. The other wall of the channel section (integral with the corrugated central part of the strip) has access windows through which the bolts are inserted and tightened, the windows being then closed off in liquid-tight manner by welding closure caps over them. (author)

  13. A model of the dose rate calculation for a spent fuel storage structure by Monte Carlo method using the modulated code system SCALE 4.4a

    International Nuclear Information System (INIS)

    Pantazi, D.; Mateescu, S.; Stanciu, M.; Mete, M.

    2001-01-01

    The modulated code system SCALE is used to perform a standardized shielding analysis for any facility containing spent fuel: handling devices, transport cask, intermediate and final storage facility. The neutron and gamma sources as well as the dose rates can be obtained using either discrete-ordinates or Monte Carlo methods. The shielding analysis control modules (SAS1, SAS2H and SAS4) provide a general procedure for cross-section preparation, fuel depletion/decay calculation and general onedimensional or multi-dimensional shielding analysis. The module SAS4 used in the analysis presented in this paper, is a three-dimensional Monte Carlo shielding analysis module, which uses an automated biasing procedure specialized for a nuclear fuel transport or storage container. The Spent Fuel Interim Storage Facility in our country is projected to be a parallelepiped concrete monolithic module, consisting of an external reinforced concrete structure with vertical storage cylinders (pits) arranged in a rectangular array. A pit is filled with sealed cylindrical baskets of stainless steel arranged in a stack, and with each basket containing spent fuel bundles in vertical position. The pit is closed with a concrete plug. The cylindrical geometry model is used in the shielding evaluation for a spent fuel storage structure (pit), and only the active parts of the superposed bundles is considered. The dose rates have been calculated in both the axial and radial directions using SAS4.(author)

  14. Nanobiotechnology for the production of biofuels from spent tea ...

    African Journals Online (AJOL)

    Bioenergy is the only alternative and cheap source of energy which can be made easily available to the world. The present experiment included three steps for the conversion of spent tea (Camellia sinensis) into biofuels. In the first step, spent tea was gasified using Co nano catalyst at 300°C and atmospheric pressure.

  15. Integrated spent nuclear fuel database system

    International Nuclear Information System (INIS)

    Henline, S.P.; Klingler, K.G.; Schierman, B.H.

    1994-01-01

    The Distributed Information Systems software Unit at the Idaho National Engineering Laboratory has designed and developed an Integrated Spent Nuclear Fuel Database System (ISNFDS), which maintains a computerized inventory of all US Department of Energy (DOE) spent nuclear fuel (SNF). Commercial SNF is not included in the ISNFDS unless it is owned or stored by DOE. The ISNFDS is an integrated, single data source containing accurate, traceable, and consistent data and provides extensive data for each fuel, extensive facility data for every facility, and numerous data reports and queries

  16. Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third national report on the implementation of obligations of the Joint Convention

    International Nuclear Information System (INIS)

    2008-09-01

    This report is published in compliance with the Joint Convention and presents the measures implemented by France to comply with each of the obligations defined by this convention. The structure of the report refers to the articles of the Convention. Therefore, after a presentation of the main evolutions since France's previous report, the following themes are addressed: policies and practices, scope of application, inventories and lists, legislative and regulatory system, other general safety provisions, safety of spent fuel management, trans-boundary movement, disused sealed sources, and planned activities to improve safety

  17. Repository Closure and Sealing Approach

    International Nuclear Information System (INIS)

    A.T. Watkins

    2000-01-01

    The scope of this analysis will be to develop the conceptual design of the closure seals and their locations in the Subsurface Facilities. The design will be based on the recently established program requirements for transitioning to the Site Recommendation (SR) design as outlined by ''Approach to Implementing the Site Recommendation Baseline'' (Stroupe 2000) and the ''Monitored Geologic Repository Project Description Document'' (CRWMS M andO 1999b). The objective of this analysis will be to assist in providing a description for the Subsurface Facilities System Description Document, Section 2 and finally to document any conclusions reached in order to contribute and provide support to the SR. This analysis is at a conceptual level and is considered adequate to support the SR design. The final closure barriers and seals for the ventilation shafts, and the north and south ramps will require these openings to be permanently sealed to limit excessive air and water inflows and prevent human intrusion. The major tasks identified with closure in this analysis are: (1) Developing the overall subsurface seal layout and identifying design and operational interfaces for the Subsurface Facilities. (2) Summarizing the general site conditions and general rock characteristic with respect to seal location and describing the seal selected. (3) Identify seal construction materials, methodology of construction and strategic locations including design of the seal and plugs. (4) Discussing methods to prevent human intrusion

  18. Face-Sealing Butterfly Valve

    Science.gov (United States)

    Tervo, John N.

    1992-01-01

    Valve plate made to translate as well as rotate. Valve opened and closed by turning shaft and lever. Interactions among lever, spring, valve plate, and face seal cause plate to undergo combination of translation and rotation so valve plate clears seal during parts of opening and closing motions.

  19. Seals, Concrete Anchors, and Connections

    Science.gov (United States)

    1989-02-01

    caulking compounds, nonhardening extruded tapes, nonhardening mastics, strippable spray coatings, pressure sensitive tapes, gaskets, adhesives, fabrics...films, etc. Although all of these materials may provide a seal, care must be taken when selecting a sealing material as to its chemical and...gaskets have performed satisfactorily. Another factor to be considered in the selection of gasketing material is its compatibility with both the

  20. Research on seal control systems for international nuclear safeguard and the vulnerability assessment on the seals

    International Nuclear Information System (INIS)

    Zhang Hongjian; Liu Tianshu; Cao Fangfang; Xu Chunyan

    2014-01-01

    Safeguard seals, also called Tamper-indicating devices (TIDs), are widely used to detect tampering or unauthorized entry in the international safeguard and security systems, Seal control systems consist of seal implementing plan, seal development and the vulnerability assessment on tbe seals, effective implementing procedures and methods of the seals. The vulnerability assessment contents of safeguard seals, thermo-shrinked film seals being as an example, and seals control systems in the implementation program are researched. The seal control systems discuss task assignment, seals management flow and seals program data flow to promote applying effectively seals. The vulnerability assessment program of seals studies assurance level to some different tampering techniques and measures. The researches must promote utilizing seals effectively for nuclear security, non-proliferation of nuclear weapons, radioactive waste management, and the nuclear material accounting and control. (authors)

  1. Airfoil seal system for gas turbine engine

    Science.gov (United States)

    None, None

    2013-06-25

    A turbine airfoil seal system of a turbine engine having a seal base with a plurality of seal strips extending therefrom for sealing gaps between rotational airfoils and adjacent stationary components. The seal strips may overlap each other and may be generally aligned with each other. The seal strips may flex during operation to further reduce the gap between the rotational airfoils and adjacent stationary components.

  2. Tamper tape seals

    International Nuclear Information System (INIS)

    Wright, B.W.; Undem, H.A.

    1994-07-01

    Tamper tapes are appealing for many applications due to their ease of use and relative robustness. Applications include seals for temporary area denial, protection of sensitive equipment, chain-of-custody audit trails, and inventory control practices. A next generation of adhesive tamper tapes is being developed that combines the best features of commercially available devices with additional state-of-the-art features in tamper indication, tamper-resistance, and counterfeit-resistance. The additional features are based on U.S. Department of Energy (DOE) research and development (R ampersand D) activities that were originally associated with preparations for the Strategic Arms Reduction Treaty (START). New features include rapid-set, chemical-cure adhesive systems that allow user-friendly application and layered levels of counterfeit-resistance based on unique open-quotes fingerprintclose quotes characteristics that can be accessed as desired

  3. High pressure mechanical seal

    Science.gov (United States)

    Babel, Henry W. (Inventor); Anderson, Raymond H. (Inventor)

    1996-01-01

    A relatively impervious mechanical seal is formed between the outer surface of a tube and the inside surface of a mechanical fitting of a high pressure fluid or hydraulic system by applying a very thin soft metal layer onto the outer surface of the hard metal tube and/or inner surface of the hard metal fitting. The thickness of such thin metal layer is independent of the size of the tube and/or fittings. Many metals and alloys of those metals exhibit the requisite softness, including silver, gold, tin, platinum, indium, rhodium and cadmium. Suitably, the coating is about 0.0025 millimeters (0.10 mils) in thickness. After compression, the tube and fitting combination exhibits very low leak rates on the order or 10.sup.-8 cubic centimeters per second or less as measured using the Helium leak test.

  4. Encapsulating spent nuclear fuel

    International Nuclear Information System (INIS)

    Fleischer, L.R.; Gunasekaran, M.

    1979-01-01

    A system is described for encapsulating spent nuclear fuel discharged from nuclear reactors in the form of rods or multi-rod assemblies. The rods are completely and contiguously enclosed in concrete in which metallic fibres are incorporated to increase thermal conductivity and polymers to decrease fluid permeability. This technique provides the advantage of acceptable long-term stability for storage over the conventional underwater storage method. Examples are given of suitable concrete compositions. (UK)

  5. Spent fuel dissolution mechanisms

    International Nuclear Information System (INIS)

    Ollila, K.

    1993-11-01

    This study is a literature survey on the dissolution mechanisms of spent fuel under disposal conditions. First, the effects of radiolysis products on the oxidative dissolution mechanisms and rates of UO 2 are discussed. These effects have mainly been investigated by using electrochemical methods. Then the release mechanisms of soluble radionuclides and the dissolution of the UO 2 matrix including the actinides, are treated. Experimental methods have been developed for measuring the grain-boundary inventories of radionuclides. The behaviour of cesium, strontium and technetium in leaching tests shows different trends. Comparison of spent fuel leaching data strongly suggests that the release of 90 Sr into the leachant can be used as a measure of the oxidation/dissolution of the fuel matrix. Approaches to the modelling UO 2 , dissolution are briefly discussed in the next chapter. Lastly, the use of natural material, uraninite, in the evaluation of the long-term performance of spent fuel is discussed. (orig.). (81 ref., 37 figs., 8 tabs.)

  6. Turbine and Structural Seals Team Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — Seals Team Facilities conceive, develop, and test advanced turbine seal concepts to increase efficiency and durability of turbine engines. Current projects include...

  7. Apparatus for lifting spent fuel assembly

    International Nuclear Information System (INIS)

    Hirasawa, Yoshinari; Sato, Isao; Yoneda, Yoshiyuki.

    1976-01-01

    Object: To increase the efficiency of cooling of a used fuel assembly being moved within a guide tube in the axial direction thereof by directly cooling the assembly with cooling gas fed into the guide tube, thus facilitating the handling of the spent fuel assembly. Structure: An end of a lock portion is inserted into the top portion of a spent fuel assembly, the assembly being hooked on the lock portion. The lock portion is provided on its outer periphery with a seal member and a centering member and at its tip with a pawl capable of being projected and retracted in the radial direction. Thus, when the lock portion is moved along the guide tube, the used fuel assembly can be moved along the guide tube by maintaining the concentric relation thereto. Meanwhile, when cooling gas is fed into the guide tube, it is blown into the used fuel assembly to directly cool the same. Thus, the cooling efficiency can be increased. (Moriyama, M.)

  8. Symptoms prevalence among office workers of a sealed versus a non-sealed building: associations to indoor air quality.

    Science.gov (United States)

    Rios, José Luiz de Magalhães; Boechat, José Laerte; Gioda, Adriana; dos Santos, Celeste Yara; de Aquino Neto, Francisco Radler; Lapa e Silva, José Roberto

    2009-11-01

    An increasing number of complaints related to time spent in artificially ventilated buildings have been progressively reported and attributed, at least in part, to physical and chemical exposures in the office environment. The objective of this research was to investigate the association between the prevalence of work-related symptoms and the indoor air quality, comparing a sealed office building with a naturally ventilated one, considering, specially, the indoor concentration of TPM, TVOCs and the main individual VOCs. A cross-sectional study was performed to compare the prevalence of sick building syndrome (SBS) symptoms among 1736 office workers of a sealed office building and 950 of a non-sealed one, both in Rio de Janeiro's downtown. The prevalence of symptoms was obtained by a SBS standardized questionnaire. The IAQ of the buildings was evaluated through specific methods, to determine the temperature, humidity, particulate matter and volatile organic compound (VOC) concentrations. Upper airways and ophthalmic symptoms, tiredness and headache were highly prevalent in both buildings. Some symptoms were more prevalent in the sealed building: "eye dryness" 33.3% and 27.1% (p: 0.01); "runny nose" 37.3% and 31.3% (p: 0.03); "dry throat" 42% and 36% (p: 0.02); and "lethargy" 58.5% and 50.5% (p: 0.03) respectively. However, relative humidity and indoor total particulate matter (TPM) concentration as well as total volatile organic compounds (TVOCs) were paradoxically greater in the non-sealed building, in which aromatic compounds had higher concentration, especially benzene. The analysis between measured exposure levels and resulting symptoms showed no association among its prevalence and TPM, TVOCs, benzene or toluene concentration in none of the buildings. Other disregarded factors, like undetected VOCs, mites, molds and endotoxin concentrations, may be associated to the greater prevalence of symptoms in the sealed building.

  9. Avoidance of wind farms by harbour seals is limited to pile driving activities.

    Science.gov (United States)

    Russell, Debbie J F; Hastie, Gordon D; Thompson, David; Janik, Vincent M; Hammond, Philip S; Scott-Hayward, Lindesay A S; Matthiopoulos, Jason; Jones, Esther L; McConnell, Bernie J

    2016-12-01

    As part of global efforts to reduce dependence on carbon-based energy sources there has been a rapid increase in the installation of renewable energy devices. The installation and operation of these devices can result in conflicts with wildlife. In the marine environment, mammals may avoid wind farms that are under construction or operating. Such avoidance may lead to more time spent travelling or displacement from key habitats. A paucity of data on at-sea movements of marine mammals around wind farms limits our understanding of the nature of their potential impacts.Here, we present the results of a telemetry study on harbour seals Phoca vitulina in The Wash, south-east England, an area where wind farms are being constructed using impact pile driving. We investigated whether seals avoid wind farms during operation, construction in its entirety, or during piling activity. The study was carried out using historical telemetry data collected prior to any wind farm development and telemetry data collected in 2012 during the construction of one wind farm and the operation of another.Within an operational wind farm, there was a close-to-significant increase in seal usage compared to prior to wind farm development. However, the wind farm was at the edge of a large area of increased usage, so the presence of the wind farm was unlikely to be the cause.There was no significant displacement during construction as a whole. However, during piling, seal usage (abundance) was significantly reduced up to 25 km from the piling activity; within 25 km of the centre of the wind farm, there was a 19 to 83% (95% confidence intervals) decrease in usage compared to during breaks in piling, equating to a mean estimated displacement of 440 individuals. This amounts to significant displacement starting from predicted received levels of between 166 and 178 dB re 1 μPa (p-p) . Displacement was limited to piling activity; within 2 h of cessation of pile driving, seals were distributed as

  10. Leak detection of KNI seals

    International Nuclear Information System (INIS)

    Baranyai, G.; Peter, A.; Windberg, P.

    1990-03-01

    In Unit 3 and 4 of the Paks Nuclear Power Plant, Hungary, KNI type seals are used as lead-throughs with conical nickel sealing rings. Their failure can be critical for the operation of the reactor. An Acoustical Leak Detection System (ALDS) was constructed and tested for the operational testing of the seals. Some individual papers are presented in this collection on the calibration and testing of the ALDS intended to be placed on the top of the reactor vessels. The papers include simulation measurements of Unit 3 of NPP, laboratory experiments, evaluation of measurements, and further development needs with the ALDS. (R.P.) 50 figs.; 19 tabs

  11. Silicone foam for penetration seal

    International Nuclear Information System (INIS)

    Hoshino, Yoshikazu

    1986-01-01

    In nuclear power plants or general buildings, it is very important to form a fire-resistant seal around cables, cable trays and conduits passing through a wall or a floor. Rockwool, asbestos, glasswool and flame-retarded urethane foam have so far been used for these purposes. However, they were not satisfactory in sealing property, workability and safety. The silicone foam newly developed, ''TOSSEAL'' 300, has cleared these defects. It has now come to be used for fire resistant seal in nuclear power plants. (author)

  12. Spent fuel storage requirements

    International Nuclear Information System (INIS)

    Fletcher, J.

    1982-06-01

    Spent fuel storage requirements, as projected through the year 2000 for U.S. LWRs, were calculated using information supplied by the utilities reflecting plant status as of December 31, 1981. Projections through the year 2000 combined fuel discharge projections of the utilities with the assumed discharges of typical reactors required to meet the nuclear capacity of 165 GWe projected by the Energy Information Administration (EIA) for the year 2000. Three cases were developed and are summarized. A reference case, or maximum at-reactor (AR) capacity case, assumes that all reactor storage pools are increased to their maximum capacities as estimated by the utilities for spent fuel storage utilizing currently licensed technologies. The reference case assumes no transshipments between pools except as currently licensed by the Nuclear Regulatory Commission (NRC). This case identifies an initial requirement for 13 MTU of additional storage in 1984, and a cumulative requirement for 14,490 MTU additional storage in the year 2000. The reference case is bounded by two alternative cases. One, a current capacity case, assumes that only those pool storage capacity increases currently planned by the operating utilities will occur. The second, or maximum capacity with transshipment case, assumes maximum development of pool storage capacity as described above and also assumes no constraints on transshipment of spent fuel among pools of reactors of like type (BWR, PWR) within a given utility. In all cases, a full core discharge capability (full core reserve or FCR) is assumed to be maintained for each reactor, except that only one FCR is maintained when two reactors share a common pool. For the current AR capacity case the indicated storage requirements in the year 2000 are indicated to be 18,190 MTU; for the maximum capacity with transshipment case they are 11,320 MTU

  13. Spent fuel transportation problems

    International Nuclear Information System (INIS)

    Kondrat'ev, A.N.; Kosarev, Yu.A.; Yulikov, E.A.

    1977-01-01

    In this paper, problems of transportation of nuclear spent fuel to reprocessing plants are discussed. The solutions proposed are directed toward the achievement of the transportation as economic and safe as possible. The increase of the nuclear power plants number in the USSR and the great distances between these plants and the reprocessing plants involve an intensification of the spent fuel transportation. Higher burnup and holdup time reduction cause the necessity of more bulky casks. In this connection, the economic problems become still more important. One of the ways of the problem solution is the development of rational and cheap cask designs. Also, the enforcement in the world of the environmental and personnel health protection requires to increase the transportation reliability and safety. The paper summarizes safe transportation rules with clarifying the following questions: the increase of the transport unit quantity of the spent fuel; rational shipment organization that minimizes vehicle turnover cycle duration; development of the reliable calculation methods to determine strength, thermal conditions and nuclear safety of transport packaging as applied to the vehicles of high capacity; maximum unification of vehicles, calculation methods and documents; and cask testing on models and in pilot scale on specific test rigs to assure that they meet the international safe fuel shipment rules. Besides, some considerations on the choice and use of structural materials for casks are given, and problems of manufacturing such casks from uranium and lead are considered, as well as problems of the development of fireproof shells, control instrumentation, vehicles decontamination, etc. All the problems are considered from the point of view of normal and accidental shipment conditions. Conclusions are presented [ru

  14. Handling of radioactive sources in Ecuador

    International Nuclear Information System (INIS)

    Benitez, Manuel

    2000-01-01

    This document describes the following aspects: sealed and unsealed radioactive sources, radiation detectors, personnel and area monitoring, surface pollution, radioactive wastes control and radioactive sources transferring. (The author)

  15. Development of an externally controllable sealed isotope generator.

    Science.gov (United States)

    Sasaki, Toru; Aoki, Katsumi; Yamashita, Ryosuke; Hori, Kensuke; Kato, Taiga; Saito, Misaki; Niisawa, Kazuhiro; Nagatsu, Kotaro; Nozaki, Tadashi

    2018-03-01

    An externally controllable sealed isotope generator has been proposed for radiation education activities. Column ( 68 Ge- 68 Ga and 137 Cs- 137m Ba) and solvent extraction ( 68 Ge- 68 Ga)-based isotope generators were applied as radioactive sources. These generators showed high milking efficiencies and low breakthrough after repeated uses, and are expected to promote the use of isotope generators without radioactive contamination or the emission of radioactive waste. This isotope generator provides a new concept for sealed radioisotope sources. Copyright © 2017 Elsevier Ltd. All rights reserved.

  16. Seal coat binder performance specifications.

    Science.gov (United States)

    2013-11-01

    Need to improve seal coat binder specs: replace empirical tests (penetration, ductility) with : performance-related tests applicable to both : unmodified and modified binders; consider temperatures that cover entire in service : range that are tied t...

  17. Alaska Harbor Seal Glacial Surveys

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Floating glacial ice serves as a haul-out substrate for a significant number (10-15%) of Alaskan harbor seals, and thus surveying tidewater glacial fjords is an...

  18. Coupled processes in repository sealing

    International Nuclear Information System (INIS)

    Case, J.B.; Kelsall, P.C.

    1985-01-01

    The significance of coupled processes in repository sealing is evaluated. In most repository designs, shaft seals will be located in areas of relatively low temperature perturbation, in which case the coupling of temperature with stress and permeability may be less significant than the coupling between stress and permeability that occurs during excavation. Constitutive relationships between stress and permeability are reviewed for crystalline rock and rocksalt. These provide a basis for predicting the development of disturbed zones near excavations. Field case histories of the degree of disturbance are presented for two contrasting rock types - Stripa granite and Southeastern New Mexico rocksalt. The results of field investigations in both rock types confirm that hydraulic conductivity or permeability is stress dependent, and that shaft seal performance may be related to the degree that stresses are perturbed and restored near the seal

  19. Northern Fur Seal Food Habits

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains food habits samples, usually scats, collected opportunistically on northern fur seal rookeries and haulouts in Alaska from 1987 to present....

  20. Technological progress in sealed lead/acid batteries

    Science.gov (United States)

    Yamashita, J.; Nakashima, H.; Kasai, Y.

    A brief review is given of the history of the research and development of sealed lead/acid batteries during the 30 years since, in 1959, the Yuasa Battery Co. introduced a small-sized sealed battery as the power supply for portable television sets. In 1965, Yuasa began the full-scale mass production and sale of a small-sized sealed lead/acid battery under the NOYPER brand. In 1970, the use of a PbCa alloy grid was adopted, and there followed the successful development of a sealed battery with an oxygen-recombination facility. In 1976, Yuasa more or less established the basic technology for the valve-regulated sealed lead/acid battery — the NP battery — which is now the type in general use. Throughout the 1980s, Yuasa, has continued development in order to expand the sphere of application for the production technology of valve-regulated batteries for motorcycles, as well as for stationary duties with large capacities of 100 to 3000 A h. Recently, in order to improve the reliability and boost the output of sealed lead/acid batteries for employment in UPS power sources, Yuasa has been working intently on the design of a valve-regulated lead/acid battery with outstanding characteristics for high-rate discharge and resistance to high temperatures.

  1. Catch history of ringed seals (Phoca hispida in Canada

    Directory of Open Access Journals (Sweden)

    Randall R Reeves

    1998-06-01

    Full Text Available The ringed seal (Phoca hispida has always been a staple in the diet and household economy of Inuit in Canada. The present paper was prepared at the request of the NAMMCO Scientific Committee to support their assessment of ringed seal stocks in the North Atlantic Basin and adjacent arctic and subarctic waters. Specifically, our objective was to evaluate recent and current levels of use of ringed seals by Canadian Inuit. Annual removals probably were highest (possibly greater than 100,000 in the 1960s and 1970s, a period when sealskin prices were particularly strong. Catches declined substantially in the 1980s following a collapse in sealskin prices, presumably related to the European trade ban on skins from newborn harp and hooded seals (Phoca groenlandica and Cystophora cristata, respectively. Recent catch levels throughout Canada (1980s and early 1990s are believed to be in the order of 50,000 to 65,000 ringed seals, with a total average annual kill (including hunting loss in the high tens of thousands. No reliable system is in place to monitor catches of ringed seals, so any estimate must be derived from a heterogeneous array of sources.

  2. Design considerations for mechanical face seals

    Science.gov (United States)

    Ludwig, L. P.; Greiner, H. F.

    1980-01-01

    Two companion reports deal with design considerations for improving performance of mechanical face seals, one of family of devices used in general area of fluid sealing of rotating shafts. One report deals with basic seal configuration and other with lubrication of seal.

  3. Spent fuel reprocessing method

    International Nuclear Information System (INIS)

    Shoji, Hirokazu; Mizuguchi, Koji; Kobayashi, Tsuguyuki.

    1996-01-01

    Spent oxide fuels containing oxides of uranium and transuranium elements are dismantled and sheared, then oxide fuels are reduced into metals of uranium and transuranium elements in a molten salt with or without mechanical removal of coatings. The reduced metals of uranium and transuranium elements and the molten salts are subjected to phase separation. From the metals of uranium and transuranium elements subjected to phase separation, uranium is separated to a solid cathode and transuranium elements are separated to a cadmium cathode by an electrolytic method. Molten salts deposited together with uranium to the solid cathode, and uranium and transuranium elements deposited to the cadmium cathode are distilled to remove deposited molten salts and cadmium. As a result, TRU oxides (solid) such as UO 2 , Pu 2 in spent fuels can be reduced to U and TRU by a high temperature metallurgical method not using an aqueous solution to separate them in the form of metal from other ingredients, and further, metal fuels can be obtained through an injection molding step depending on the purpose. (N.H.)

  4. Spent fuel interim storage

    International Nuclear Information System (INIS)

    Bilegan, Iosif C.

    2003-01-01

    The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

  5. Spent fuel storage rack

    International Nuclear Information System (INIS)

    Kurokawa, Hideaki; Kumagaya, Naomi; Oda, Masashi; Matsuda, Masami; Maruyama, Hiromi; Yamanaka, Tsuneyasu.

    1997-01-01

    The structure of a spent fuel storage rack is determined by the material, thickness, size of square cylindrical tubes (the gap between spent fuel assemblies and the square cylindrical tubes) and pitch of the arrangement (the gap between each of the square cylindrical tubes). In the present invention, the thickness and the pitch of the arrangement of the square tubes are optimized while evaluating subcriticality. Namely, when the sum of the thickness of the water gap at the outer side (the pitch of arrangement of the cylindrical tubes) and the thickness of the cylindrical tubes is made constant, the storage rack is formed by determining the thickness of the cylindrical tubes which is smaller than the optimum value among the combination of the thickness of the water gap at the outer side and that of the cylindrical tube under the effective multiplication factor to be performed. Then, the weight of the rack can be reduced, and the burden of the load on the bottom of the pool can be reduced. Further, the amount of the constitutional materials of the rack itself can be reduced thereby capable of reducing the cost for the materials of the rack. (T.M.)

  6. Seals Research at AlliedSignal

    Science.gov (United States)

    Ullah, M. Rifat

    1996-01-01

    A consortium has been formed to address seal problems in the Aerospace sector of Allied Signal, Inc. The consortium is represented by makers of Propulsion Engines, Auxiliary Power Units, Gas Turbine Starters, etc. The goal is to improve Face Seal reliability, since Face Seals have become reliability drivers in many of our product lines. Several research programs are being implemented simultaneously this year. They include: Face Seal Modeling and Analysis Methodology; Oil Cooling of Seals; Seal Tracking Dynamics; Coking Formation & Prevention; and Seal Reliability Methods.

  7. Sealing Failure Analysis on V-Shaped Sealing Rings of an Inserted Sealing Tool Used for Multistage Fracturing Processes

    Directory of Open Access Journals (Sweden)

    Gang Hu

    2018-06-01

    Full Text Available The inserted sealing tool is a critical downhole implement that is used to balance the downhole pressure in multistage fracturing operations and prevent fracturing fluid from overflow and/or backward flow. The sealing ring of an inserted sealing tool plays an important role in downhole sealing since a sealing failure would ail the fracturing operation. In order to improve the sealing performance and reduce the potential fracturing failures, this research aims to investigate the influence of V-shaped sealing ring geometries on sealing performance. Constitutive experiments of rubber materials were carried out and the parameters of the constitutive relationship of rubber materials were obtained. A two-dimensional axisymmetric model considering the sealing ring has been established and influences are investigated with considerations of various system parameters and operating conditions. It is found that the stresses concentrated at the shoulder and inner vertex of the sealing ring have direct impact on the damage of the sealing rings under operational conditions. Moreover, the sealing interference, among several other factors, greatly affects the life of the sealing ring. A new design of the sealing ring is suggested with optimized geometric parameters. Its geometric parameters are the edge height of 5 mm, the vertex angle of 90°–100°, and the interference of 0.1 mm, which show a better performance and prolonged operation life of the sealing ring.

  8. Reusable, tamper-indicating seal

    International Nuclear Information System (INIS)

    Ryan, M.J.

    1978-01-01

    A reusable, tamper-indicating seal is comprised of a drum confined within a fixed body and rotatable in one direction therewithin, the top of the drum constituting a tray carrying a large number of small balls of several different colors. The fixed body contains parallel holes for looping a seal wire therethrough. The base of the drums carries cams adapted to coact with cam followers to lock the wire within the seal at one angular position of the drum. A channel in the fixed body, visible from outside the seal, adjacent the tray constitutes a segregated location for a small plurality of the colored balls. A spring in the tray forces colored balls into the segregated location at one angular position of the drum, further rotation securing the balls in position and the wires in the seal. A wedge-shaped plough removes the balls from the segregated location, at a different angular position of the drum, the wire being unlocked at the same postion. A new pattern of colored balls will appear in the segregated location when the seal is relocked

  9. Hydrodynamic perception in true seals (Phocidae) and eared seals (Otariidae).

    Science.gov (United States)

    Hanke, Wolf; Wieskotten, Sven; Marshall, Christopher; Dehnhardt, Guido

    2013-06-01

    Pinnipeds, that is true seals (Phocidae), eared seals (Otariidae), and walruses (Odobenidae), possess highly developed vibrissal systems for mechanoreception. They can use their vibrissae to detect and discriminate objects by direct touch. At least in Phocidae and Otariidae, the vibrissae can also be used to detect and analyse water movements. Here, we review what is known about this ability, known as hydrodynamic perception, in pinnipeds. Hydrodynamic perception in pinnipeds developed convergently to the hydrodynamic perception with the lateral line system in fish and the sensory hairs in crustaceans. So far two species of pinnipeds, the harbour seal (Phoca vitulina) representing the Phocidae and the California sea lion (Zalophus californianus) representing the Otariidae, have been studied for their ability to detect local water movements (dipole stimuli) and to follow hydrodynamic trails, that is the water movements left behind by objects that have passed by at an earlier point in time. Both species are highly sensitive to dipole stimuli and can follow hydrodynamic trails accurately. In the individuals tested, California sea lions were clearly more sensitive to dipole stimuli than harbour seals, and harbour seals showed a superior trail following ability as compared to California sea lions. Harbour seals have also been shown to derive additional information from hydrodynamic trails, such as motion direction, size and shape of the object that caused the trail (California sea lions have not yet been tested). The peculiar undulated shape of the harbour seals' vibrissae appears to play a crucial role in trail following, as it suppresses self-generated noise while the animal is swimming.

  10. Spent nuclear fuel storage device and spent nuclear fuel storage method using the device

    International Nuclear Information System (INIS)

    Tani, Yutaro

    1998-01-01

    Storage cells attachably/detachably support nuclear fuel containing vessels while keeping the vertical posture of them. A ventilation pipe which forms air channels for ventilating air to the outer circumference of the nuclear fuel containing vessel is disposed at the outer circumference of the nuclear fuel containing vessel contained in the storage cell. A shielding port for keeping the support openings gas tightly is moved, and a communication port thereof can be aligned with the upper portion of the support opening. The lower end of the transporting and containing vessel is placed on the shielding port, and an opening/closing shutter is opened. The gas tightness is kept by the shielding port, the nuclear fuel containing vessel filled with spent nuclear fuels is inserted to the support opening and supported. Then, the support opening is closed by a sealing lid. (I.N.)

  11. The spent fuel safety experiment

    International Nuclear Information System (INIS)

    Harmms, G.A.; Davis, F.J.; Ford, J.T.

    1995-01-01

    The Department of Energy is conducting an ongoing investigation of the consequences of taking fuel burnup into account in the design of spent fuel transportation packages. A series of experiments, collectively called the Spent Fuel Safety Experiment (SFSX), has been devised to provide integral benchmarks for testing computer-generated predictions of spent fuel behavior. A set of experiments is planned in which sections of unirradiated fuel rods are interchanged with similar sections of spent PWR fuel rods in a critical assembly. By determining the critical size of the arrays, one can obtain benchmark data for comparison with criticality safety calculations. The integral reactivity worth of the spent fuel can be assessed by comparing the measured delayed critical fuel loading with and without spent fuel. An analytical effort to model the experiments and anticipate the core loadings required to yield the delayed critical conditions runs in parallel with the experimental effort

  12. Spent fuel: prediction model development

    International Nuclear Information System (INIS)

    Almassy, M.Y.; Bosi, D.M.; Cantley, D.A.

    1979-07-01

    The need for spent fuel disposal performance modeling stems from a requirement to assess the risks involved with deep geologic disposal of spent fuel, and to support licensing and public acceptance of spent fuel repositories. Through the balanced program of analysis, diagnostic testing, and disposal demonstration tests, highlighted in this presentation, the goal of defining risks and of quantifying fuel performance during long-term disposal can be attained

  13. Spent fuel and waste inventories and projections

    International Nuclear Information System (INIS)

    Carter, W.L.; Finney, B.C.; Alexander, C.W.; Blomeke, J.O.; McNair, J.M.

    1980-08-01

    Current inventories of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on judgments of the most reliable information available from Government sources and the open literature. Future waste generation rates and quantities to be accumulated over the remainder of this century are also presented, based on a present projection of US commercial nuclear power growth and expected defense-related activities. Spent fuel projections are based on the current DOE/EIA estimate of nuclear growth, which projects 180 GW(e) in the year 2000. It is recognized that the calculated spent fuel discharges are probably high in view of recent reactor cancellations; hence adjustments will be made in future updates of this report. Wastes considered, on a chapter-by-chapter basis, are: spent fuel, high-level wastes, transuranic wastes, low-level wastes, mill tailings (active sites), and remedial action wastes. The latter category includes mill tailings (inactive sites), surplus facilities, formerly utilized sites, and the Grand Junction Project. For each category, waste volume inventories and projections are given through the year 2000. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for present inventories of mill tailings

  14. Prototype spent-fuel canister design, analysis, and test

    International Nuclear Information System (INIS)

    Leisher, W.B.; Eakes, R.G.; Duffey, T.A.

    1982-03-01

    Sandia National Laboratories was asked by the US Energy Research and Development Administration (now US Department of Energy) to design the spent fuel shipping cask system for the Clinch River Breeder Reactor Plant (CRBRP). As a part of this task, a canister which holds liquid sodium and the spent fuel assembly was designed, analyzed, and tested. The canister body survived the regulatory Type-B 9.1-m (30-ft) drop test with no apparent leakage. However, the commercially available metal seal used in this design leaked after the tests. This report describes the design approach, analysis, and prototype canister testing. Recommended work for completing the design, when funding is available, is included

  15. Sources

    International Nuclear Information System (INIS)

    Duffy, L.P.

    1991-01-01

    This paper discusses the sources of radiation in the narrow perspective of radioactivity and the even narrow perspective of those sources that concern environmental management and restoration activities at DOE facilities, as well as a few related sources. Sources of irritation, Sources of inflammatory jingoism, and Sources of information. First, the sources of irritation fall into three categories: No reliable scientific ombudsman to speak without bias and prejudice for the public good, Technical jargon with unclear definitions exists within the radioactive nomenclature, and Scientific community keeps a low-profile with regard to public information. The next area of personal concern are the sources of inflammation. This include such things as: Plutonium being described as the most dangerous substance known to man, The amount of plutonium required to make a bomb, Talk of transuranic waste containing plutonium and its health affects, TMI-2 and Chernobyl being described as Siamese twins, Inadequate information on low-level disposal sites and current regulatory requirements under 10 CFR 61, Enhanced engineered waste disposal not being presented to the public accurately. Numerous sources of disinformation regarding low level radiation high-level radiation, Elusive nature of the scientific community, The Federal and State Health Agencies resources to address comparative risk, and Regulatory agencies speaking out without the support of the scientific community

  16. STUDY ON THERMAL DEFORMATIONS OF THE PRIMARY SEALING OF FRONT SEALING

    Directory of Open Access Journals (Sweden)

    Mihaela ISTRATE

    2015-05-01

    Full Text Available The thermal phenomena appear at the level of the film within the primary sealing interstitium. An important temperature gradient is performed in the stator and in the rotor, which produces thermoelastic deformations. These deformations are of the order of film width and affect essentially the interstitium geometry. According to the temperature increase direction the repartition in the friction ring is different. The farthest areas from the temperature drops or the nearest to the heat sources will have he highest temperature. These dilate more that the rest of the areas and modify the interstitium form. From the calculation relations it comes out that deformations depend also on certain operating conditions, which can be modified through time (pressure, temperature, the sealing efficiency being thus different in time.

  17. Seal Related Development Activities at EG/G

    Science.gov (United States)

    Greiner, Harold F.

    1991-01-01

    Seal related development activities including modeling, analysis, and performance testing are described for several current seal related projects. Among the current seal related projects are the following: high pressure gas sealing systems for turbomachinery; brush seals for gas path sealing in gas turbines; and tribological material evaluation for wear surfaces in sealing systems.

  18. Radioactive material package seal tests

    International Nuclear Information System (INIS)

    Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

    1990-01-01

    General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 x 10 -7 std cm 3 /s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab

  19. Both the Antarctic fur seal Arctocephalus gazella and the ...

    African Journals Online (AJOL)

    spamer

    cause the pupping season continues into the second week of January (Kerley 1983b). On the open vegetated areas behind landing beaches, all fur seals were counted and classified. Pup numbers were derived from three sources: first, an estimate of the degree of polygyny. (2.4 pups per adult male) calculated for a Marion.

  20. Spent fuel management in Japan

    International Nuclear Information System (INIS)

    Mineo, H.; Nomura, Y.; Sakamoto, K.

    1998-01-01

    In Japan 52 commercial nuclear power units are now operated, and the total power generation capacity is about 45 GWe. The cumulative amount of spent fuel arising is about 13,500 tU as of March 1997. Spent fuel is reprocessed, and recovered nuclear materials are to be recycled in LWRs and FBRs. In February 1997 short-term policy measures were announced by the Atomic Energy Commission, which addressed promotion of reprocessing programme in Rokkasho, plutonium utilization in LWRs, spent fuel management, backend measures and FBR development. With regard to the spent fuel management, the policy measures included expansion of spent fuel storage capacity at reactor sites and a study on spent fuel storage away from reactor sites, considering the increasing amount of spent fuel arising. Research and development on spent fuel storage has been carried out, particularly on dry storage technology. Fundamental studies are also conducted to implement the burnup credit into the criticality safety design of storage and transportation casks. Rokkasho reprocessing plant is being constructed towards its commencement in 2003, and Pu utilization in LWRs will be started in 1999. Research and development of future recycling technology are also continued for the establishment of nuclear fuel cycle based on FBRs and LWRs. (author)

  1. Processes and Technologies for the Recycling of Spent Fluorescent Lamps

    Directory of Open Access Journals (Sweden)

    Kujawski Wojciech

    2014-09-01

    Full Text Available The growing industrial application of rare earth metals led to great interest in the new technologies for the recycling and recovery of REEs from diverse sources. This work reviews the various methods for the recycling of spent fluorescent lamps. The spent fluorescent lamps are potential source of important rare earth elements (REEs such as: yttrium, terbium, europium, lanthanum and cerium. The characteristics of REEs properties and construction of typical fl uorescent lamps is described. The work compares also current technologies which can be utilized for an efficient recovery of REEs from phosphors powders coming from spent fluorescent lamps. The work is especially focused on the hydrometallurgical and pyrometallurgical processes. It was concluded that hydrometallurgical processes are especially useful for the recovery of REEs from spent fluorescent lamps. Moreover, the methods used for recycling of REEs are identical or very similar to those utilized for the raw ores processing.

  2. Mechanical seal with textured sidewall

    Energy Technology Data Exchange (ETDEWEB)

    Khonsari, Michael M.; Xiao, Nian

    2017-02-14

    The present invention discloses a mating ring, a primary ring, and associated mechanical seal having superior heat transfer and wear characteristics. According to an exemplary embodiment of the present invention, one or more dimples are formed onto the cylindrical outer surface of a mating ring sidewall and/or a primary ring sidewall. A stationary mating ring for a mechanical seal assembly is disclosed. Such a mating ring comprises an annular body having a central axis and a sealing face, wherein a plurality of dimples are formed into the outer circumferential surface of the annular body such that the exposed circumferential surface area of the annular body is increased. The texture added to the sidewall of the mating ring yields superior heat transfer and wear characteristics.

  3. Turbine interstage seal with self-balancing capability

    Science.gov (United States)

    Mills, Jacob A; Jones, Russell B; Sexton, Thomas D

    2017-09-26

    An interstage seal for a turbine of a gas turbine engine, the interstage seal having a seal carrier with an axial extending seal tooth movable with a stator of the engine, and a rotor with a seal surface that forms the interstage seal with the seal tooth, where a magnetic force produced by two magnets and a gas force produced by a gas pressure acting on the seal carrier forms a balancing force to maintain a close clearance of the seal without the seal tooth contacting the rotor seal surfaces during engine operation. In other embodiments, two pairs of magnets produce first and second magnetic forces that balance the seal in the engine.

  4. EBR-II rotating plug seal maintenance

    International Nuclear Information System (INIS)

    Allen, K.J.

    1986-01-01

    The EBR-II rotating plug seals require frequent cleaning and maintenance to keep the plugs from sticking during fuel handling. Time consuming cleaning on the cover gas and air sides of the dip ring seal is required to remove oxidation and sodium reaction products that accumulate and stop plug rotation. Despite severely limited access, effective seal cleaning techniques have removed 11 800 lb (5 352 kg) of deposits from the seals since 1964. Temperature control modifications and repairs have also required major maintenance work. Suggested seal design recommendations could significantly reduce maintenance on future similar seals

  5. Self-acting and hydrodynamic shaft seals

    Science.gov (United States)

    Ludwig, L. P.

    1973-01-01

    Self-acting and hydrodynamic seals are described. The analytical procedures are outlined for obtaining a seal force balance and the operating film thickness. Particular attention is given to primary ring response (seal vibration) to rotating seat face runout. This response analysis revealed three different vibration modes. Proposed applications of self-acting seals in gas turbine engines and in rocket vehicle turbopumps are described. Also experimental data on self-acting face seals operating under simulated gas turbine conditions are given; these data show the feasibility of operating the seal at conditions of 345 newtons per square centimeter (500 psi) and 152 meters per second (500 ft/sec) sliding speed.

  6. sources

    Directory of Open Access Journals (Sweden)

    Shu-Yin Chiang

    2002-01-01

    Full Text Available In this paper, we study the simplified models of the ATM (Asynchronous Transfer Mode multiplexer network with Bernoulli random traffic sources. Based on the model, the performance measures are analyzed by the different output service schemes.

  7. WWER spent fuel storage

    Energy Technology Data Exchange (ETDEWEB)

    Bower, C C; Lettington, C [GEC Alsthom Engineering Systems Ltd., Whetstone (United Kingdom)

    1994-12-31

    Selection criteria for PAKS NPP dry storage system are outlined. They include the following: fuel temperature in storage; sub-criticality assurance (avoidance of criticality for fuel in the unirradiated condition without having to take credit for burn-up); assurance of decay heat removal; dose uptake to the operators and public; protection of environment; volume of waste produced during operation and decommissioning; physical protection of stored irradiated fuel assemblies; IAEA safeguards assurance; storage system versus final disposal route; cost of construction and extent of technology transfer to Hungarian industry. Several available systems are evaluated against these criteria, and as a result the GEC ALSTHOM Modular Vault Dry Store (MVDS) system has been selected. The MVDS is a passively cooled dry storage facility. Its most important technical, safety, licensing and technology transfer characteristics are outlined. On the basis of the experience gained some key questions and considerations related to the East European perspective in the field of spent fuel storage are discussed. 8 figs.

  8. WWER spent fuel storage

    International Nuclear Information System (INIS)

    Bower, C.C.; Lettington, C.

    1994-01-01

    Selection criteria for PAKS NPP dry storage system are outlined. They include the following: fuel temperature in storage; sub-criticality assurance (avoidance of criticality for fuel in the unirradiated condition without having to take credit for burn-up); assurance of decay heat removal; dose uptake to the operators and public; protection of environment; volume of waste produced during operation and decommissioning; physical protection of stored irradiated fuel assemblies; IAEA safeguards assurance; storage system versus final disposal route; cost of construction and extent of technology transfer to Hungarian industry. Several available systems are evaluated against these criteria, and as a result the GEC ALSTHOM Modular Vault Dry Store (MVDS) system has been selected. The MVDS is a passively cooled dry storage facility. Its most important technical, safety, licensing and technology transfer characteristics are outlined. On the basis of the experience gained some key questions and considerations related to the East European perspective in the field of spent fuel storage are discussed. 8 figs

  9. Secondary seal effects in hydrostatic non-contact seals for reactor coolant pump shaft

    International Nuclear Information System (INIS)

    Fujita, T.; Koga, T.; Tanoue, H.; Hirabayashi, H.

    1987-01-01

    The paper presents a seal flow analysis in a hydrostatic non-contact seal for a PWR coolant pump shaft. A description is given of the non-contact seal for the reactor coolant pump. Results are presented for a distortion analysis of the seal ring, along with the seal flow characteristics and the contact pressure profiles of the secondary seals. The results of the work confirm previously reported findings that the seal ring distortion is sensitive to the o-ring location (which was placed between the ceramic seal face and the seal ring retainer). The paper concludes that the seal flow characteristics and the tracking performance depend upon the dynamic properties of the secondary seal. (U.K.)

  10. Spent fuel management overview: a global perspective

    International Nuclear Information System (INIS)

    Bonne, A.; Crijns, M.J.; Dyck, P.H.; Fukuda, K.; Mourogov, V.M.

    1999-01-01

    The paper defines the main spent fuel management strategies and options, highlights the challenges for spent fuel storage and gives an overview of the regional balances of spent fuel storage capacity and spent fuel arising. The relevant IAEA activities in the area of spent fuel management are summarised. (author)

  11. Historical overview of domestic spent fuel shipments

    International Nuclear Information System (INIS)

    Pope, R.B.; Wankerl, M.W.; Armstrong, S.; Hamberger, C.; Schmid, S.

    1991-01-01

    The purpose of this paper is to provide available historical data on most commercial and research reactor spent fuel shipments that have been completed in the United States between 1964 and 1989. This information includes data on the sources of spent fuel that has been shipped, the types of shipping casks used, the number of fuel assemblies that have been shipped, and the number of shipments that have been made. The data are updated periodically to keep abreast of changes. Information on shipments is provided for planning purposes; to support program decisions of the US Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM); and to inform interested members of the public, federal, state, and local government, Indian tribes, and the transportation community. 5 refs., 7 figs., 2 tabs

  12. Reliability in maintenance and design of elastomer sealed closures

    International Nuclear Information System (INIS)

    Lake, W.H.

    1978-01-01

    The methods of reliability are considered for maintenance and design of elastomer sealed containment closures. Component reliability is used to establish a replacement schedule for system maintenance. Reliability data on elastomer seals is used to evaluate the common practice of annual replacement, and to calculate component reliability values for several typical shipment time periods. System reliability methods are used to examine the relative merits of typical closure designs. These include single component and redundant seal closure, with and without closure verification testing. The paper presents a general method of quantifying the merits of closure designs through the use of reliability analysis, which is a probabilistic technique. The reference list offers a general source of information in the field of reliability, and should offer the opportunity to extend the procedures discussed in this paper to other design safety applications

  13. Influence of the soil sealing on the geoaccumulation index of heavy metals and various pollution factors.

    Science.gov (United States)

    Charzyński, Przemysław; Plak, Andrzej; Hanaka, Agnieszka

    2017-02-01

    Soil sealing belongs to the most destructive and damaging processes to the soil environment. Soil sealing interrupts or greatly restricts the exchange of matter and energy between the biosphere, hydrosphere, and atmosphere and the soil environment. The aim of this study was to compare the content of heavy metals (Cd, Cr, Cu, Hg, Fe, Ni, Pb, Zn) of Ekranic Technosols by applying indicators such as geoaccumulation index (I geo ), enrichment factor (EF), and pollution load index (PLI), which allowed to determine quantitatively the impact of the soil sealing degree on the content of heavy metals and to distinguish natural from anthropogenic sources of origin of heavy metals. In general, 42 soils from different parts of the city of Toruń (NW Poland) were sampled and divided into three groups according to the degree of soil sealing: completely sealed with asphalt or concrete (A), semi-permeable (partially sealed with cobblestones and concrete paving slabs (B)), and reference (non-sealed) (C). The results indicate that the artificial sealing in urban areas slightly affects the content of heavy metals in soils. However, based on PLI, I geo , and EF, it was found that the sealing has influence on soil properties and unsealed soil is the most exposed to the accumulation of pollutants.

  14. Risk Analyses of Charging Pump Control Improvements for Alternative RCP Seal Cooling

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eun-Chan [Korea Hydro and Nuclear Power Co. Ltd. Daejeon (Korea, Republic of)

    2015-10-15

    There are two events that significantly affect the plant risk during a TLOCCW event. One is an event in which the seal assembly of a reactor coolant pump (RCP) fails due to heating stress from the loss of cooling water; the other is an event in which the operators fail to conduct alternative cooling for the RCP seal during the accident. KHNP reviewed the replacement of the RCP seal with a qualified shutdown seal in order to remove the risk due to RCP seal failure during a TLOCCW. As an optional measure, a design improvement in the alternative cooling method for the RCP seal is being considered. This analysis presents the alternative RCP seal cooling improvement and its safety effect. K2 is a nuclear power plant with a Westinghouse design, and it has a relatively high CDF during TLOCCW events because it has a different CCW system design and difficulty in preparing alternative cooling water sources. This analysis confirmed that an operator action providing cold water to the RWST as RCP seal injection water during a TLOCCW event is very important in K2. The control circuit improvement plan for the auxiliary charging pump was established in order to reduce the failure probability of this operator action. This analysis modeled the improvement as a fault tree and evaluated the resulting CDF change. The consequence demonstrated that the RCP seal injection failure probability was reduced by 89%, and the CDF decreased by 28%.

  15. A sealed turbo-alternator using any working-fluid

    International Nuclear Information System (INIS)

    Chollet, Maurice.

    1973-01-01

    The invention relates to a sealed turbo-alternator operating with a working fluid other than water. The turbo-alternator and the feed and lubricating pumps thereof are housed in a sealed casing. The latter constitutes, with the heat pump and the heat sink, a sealed enclosure containing the working and lubricating fluid. The alternator, which comprises neither collector nor brushes, is dipped in the working fluid vapor. Electric energy leaves the sealed enclosure through insulating sealed passager. In view of the absence of leakage it is possible to select (e.g. among freons) a working fluid well suited to the temperature differential between the heat source and the heat sink, and, accordingly to use temperature drops which could be too small in the case of steam. The various applications are as follows: recovery of calories at the exhaust of diesels and of gas turbines or in the cooling water of diesels; equipment of isotopic generators; recovery of calories from factory waste thrown into rivers (anti-pollution effect in view of the lowering of water temperature); non-polluting engine for special electrical vehicles [fr

  16. Testing of neutron-irradiated ceramic-to-metal seals

    International Nuclear Information System (INIS)

    Brown, R.D.; Clinard, F.W. Jr.; Lopez, M.R.; Martinez, H.; Romero, T.J.; Cook, J.H.; Barr, H.N.; Hittman, F.

    1990-01-01

    This paper reports on ceramic-to-metal seals prepared by sputtering a titanium metallizing layer onto ceramic disks and then brazing to metal tubes. The ceramics used were alumina, MACOR, spinel, AlON, and a mixture of Al 2 O 3 and Si 3 N 4 . Except for the MACOR, which was brazed to a titanium tube, the ceramics were brazed to niobium tubes. The seals were leak tested and then sent to Los Alamos National Laboratory, where they were irradiated using the spallation neutron source at the Los Alamos Meson Physics Facility. Following irradiation for ∼ 90 days to a fluence of 2.8 x 10 23 n/m 2 , the samples were moved to hot cells and again leak tested. Only the MACOR samples showed any measurable leaks. One set of samples was then pressurized to 6.9 MPa (1000 psi) and subsequently leak tested. No leaks were found. Bursting the seals required hydrostatic pressures of at least 34 MPa (5000 psi). The high seal strength and few leaks indicate that ceramic-to-metal seals can resist radiation-induced degradation

  17. Spent fuel treatment in Japan

    International Nuclear Information System (INIS)

    Takahashi, K.

    1999-01-01

    In Japan, 52 nuclear power reactors are operating with a total power generation capacity of 45 GWe. The cumulative amount of spent fuel arising, as of March 1998, is about 14,700 W. Spent fuel is reprocessed and recovered nuclear materials are to be recycled in LWRs and FBRs. Pu utilization in LWRs will commence in 1999. In January 1997, short-term policy measures were announced by the Atomic Energy Commission, which addressed promotion of the reprocessing programme in Rokkasho, plutonium utilization in LWRs, spent fuel management, back-end measures and FBR development. With regard to the spent fuel management, the policy measures included expansion of spent fuel storage capacity at reactor sites and a study on spent fuel storage away-from-reactor sites, considering the increasing amount of spent fuel arising. Valuable experience was been accumulated at the Tokai Reprocessing Plant (TRP), from the start of hot operation in 1977 up to now. The role of the TRP will be changed from an operation-oriented to a more R and D oriented facility, when PNC is reorganized into the new organization JNC. The Rokkasho reprocessing plant is under construction and is expected to commence operation in 2003. R and D of future recycling technologies is also continued for the establishment of a nuclear fuel cycle based on FBRs and LWRs. (author)

  18. Disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    1979-12-01

    This report addresses the topic of the mined geologic disposal of spent nuclear fuel from Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). Although some fuel processing options are identified, most of the information in this report relates to the isolation of spent fuel in the form it is removed from the reactor. The characteristics of the waste management system and research which relate to spent fuel isolation are discussed. The differences between spent fuel and processed HLW which impact the waste isolation system are defined and evaluated for the nature and extent of that impact. What is known and what needs to be determined about spent fuel as a waste form to design a viable waste isolation system is presented. Other waste forms and programs such as geologic exploration, site characterization and licensing which are generic to all waste forms are also discussed. R and D is being carried out to establish the technical information to develop the methods used for disposal of spent fuel. All evidence to date indicates that there is no reason, based on safety considerations, that spent fuel should not be disposed of as a waste

  19. Dry spent fuel storage licensing

    International Nuclear Information System (INIS)

    Sturz, F.C.

    1995-01-01

    In the US, at-reactor-site dry spent fuel storage in independent spent fuel storage installations (ISFSI) has become the principal option for utilities needing storage capacity outside of the reactor spent fuel pools. Delays in the geologic repository operational date at or beyond 2010, and the increasing uncertainty of the US Department of Energy's (DOE) being able to site and license a Monitored Retrievable Storage (MRS) facility by 1998 make at-reactor-site dry storage of spent nuclear fuel increasingly desirable to utilities and DOE to meet the need for additional spent fuel storage capacity until disposal, in a repository, is available. The past year has been another busy year for dry spent fuel storage licensing. The licensing staff has been reviewing 7 applications and 12 amendment requests, as well as participating in inspection-related activities. The authors have licensed, on a site-specific basis, a variety of dry technologies (cask, module, and vault). By using certified designs, site-specific licensing is no longer required. Another new cask has been certified. They have received one new application for cask certification and two amendments to a certified cask design. As they stand on the brink of receiving multiple applications from DOE for the MPC, they are preparing to meet the needs of this national program. With the range of technical and licensing options available to utilities, the authors believe that utilities can meet their need for additional spent fuel storage capacity for essentially all reactor sites through the next decade

  20. Aerial Survey Counts of Harbor Seals in Lake Iliamna, Alaska, 1984-2013 (NODC Accession 0123188)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This dataset provides counts of harbor seals from aerial surveys over Lake Iliamna, Alaska, USA. The data have been collated from three previously published sources...