WorldWideScience

Sample records for special form material

  1. Qualifications of and acceptance criteria for transporting special form radioactive material

    International Nuclear Information System (INIS)

    Hovingh, J.

    1991-01-01

    A special form radioactive material is a radioactive material that is in an inert, insoluble, indispersible form such that even in the event of an accident, it will not be dispersed into the environment in a way that could have an adverse impact on public health and safety. Methods of qualifying a special form radioactive material are discussed. Interpretation of acceptance criteria are proposed for the transportation of Type B quantities of a special form radioactive material. 11 refs

  2. 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

  3. Criteria for cesium capsules to be shipped as special form radioactive material

    International Nuclear Information System (INIS)

    Lundeen, J.E.

    1994-01-01

    The purpose of this report is to compile all the documentation which defines the criteria for Waste Encapsulation and Storage Facility (WESF) cesium capsules at the IOTECH facility and Applied Radiant Energy Corporation (ARECO) to be shipped as special form radioactive material in the Beneficial Uses Shipping System (BUSS) Cask. The capsules were originally approved as special form in 1975, but in 1988 the integrity of the capsules came into question. WHC developed the Pre-shipment Acceptance Test Criteria for capsules to meet in order to be shipped as special form material. The Department of Energy approved the criteria and directed WHC to ship the capsules at IOTECH and ARECO meeting this criteria to WHC as special form material

  4. 49 CFR 173.476 - Approval of special form Class 7 (radioactive) materials.

    Science.gov (United States)

    2010-10-01

    ... (radioactive) materials must maintain on file for at least one year after the latest shipment, and provide to... evidence based on calculative methods to show that the material is able to pass the tests; or other... shipping papers as “Radioactive Material, Special Form, n.o.s.” [Amdt. 173-244, 60 FR 50307, Sept. 28, 1995...

  5. Quality assurance in production and use of special form radioactive material - focal points in BAM approvals

    International Nuclear Information System (INIS)

    Rolle, A.; Buhlemann, L.

    2004-01-01

    BAM as the competent authority for approval of special form radioactive material attaches great importance to a detailed audit of the required quality assurance programs for design, manufacture, testing, documentation, use, maintenance and inspection. Applicants have to submit, together with application documentation information on general arrangements for quality assurance, as well as on quality assurance in production and in operation. Fields where BAM has often found deficiencies are leak test methods, weld seam quality and the safety level after use

  6. Directory of national competent authorities' approval certificates for packages, shipments, special arrangements and special form radioactive material

    International Nuclear Information System (INIS)

    1987-11-01

    The Agency's transport regulations prescribe various requirements for the authorization of packages and shipments in respect of both national and international movement of radioactive material. These authorizations are issued by the relevant competent authority of the country concerned; they take the form of package approval and/or shipment approval certificates. At the request of the Standing Advisory Group of the Safe Transport of Radioactive Material (SAGSTRAM), the Agency has established a programme to maintain a file of those certificates for packages and shipments which are either transported internationally or used outside the country of origin. The purpose of this directory is to facilitate the transfer of information to competent authorities and any other person wishing details on the packaging, authorized contents or special conditions pertinent to any package or shipment. The directory enables competent authorities to be aware of the status of any certificate submitted for validation. It also indicates any change in status of any certificate already validated

  7. Directory of national competent authorities' approval certificates for packages, shipments, special arrangements and special form radioactive material

    International Nuclear Information System (INIS)

    1986-09-01

    The Agency's transport regulations prescribe various requirements for the authorization of packages and shipments in respect of both national and international movement of radioactive materials. These authorizations are issued by the relevant competent authority of the country concerned; they take the form of package approval and/or shipment approval certificates. At the request of the Standing Advisory Group of the Safe Transport of Radioactive Material (SAGSTRAM), the Agency has established a programme to maintain a file of those certificates for packages and shipments which are either transported internationally or used outside the country of origin. The purpose of this directory is to facilitate the transfer of information to competent authorities and any other person wishing details on the packaging, authorized contents or special conditions pertinent to any package or shipment. The directory enables competent authorities to be aware of the status of any certificate submitted for validation. It also indicates any change in status of any certificate already validated. Future updates of the complete data will be distributed annually in a TECDOC form and, in addition, summary listings of the certificates will be issued every six months thereafter

  8. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2003 ed

    International Nuclear Information System (INIS)

    2003-10-01

    This is the fourteenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Committee (TRANSSC). It supersedes IAEA-TECDOC-1302 'Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2002 Edition'. Through the database, the Secretariat collects administrative and technical information provided by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. The PACKTRAM database only contains information that has been provided to the IAEA. The data are not complete nor guaranteed to be accurate. If detailed information is required, the original package approval certificates must be consulted. If information is required about package approval certificates that are not contained in the database, the issuing competent authority must be consulted

  9. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2003 ed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-10-01

    This is the fourteenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Committee (TRANSSC). It supersedes IAEA-TECDOC-1302 'Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2002 Edition'. Through the database, the Secretariat collects administrative and technical information provided by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. The PACKTRAM database only contains information that has been provided to the IAEA. The data are not complete nor guaranteed to be accurate. If detailed information is required, the original package approval certificates must be consulted. If information is required about package approval certificates that are not contained in the database, the issuing competent authority must be consulted.

  10. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1992 ed

    International Nuclear Information System (INIS)

    1992-08-01

    Being in a unique position to facilitate information exchange, the Secretariat of the International Atomic Energy Agency was requested by its Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) to collate package approval data and publish periodical reports thereon. A database was implemented on the mainframe computer in the mid-1980s but this was soon adapted for use on a personal computer. A fully menu-driven system programme was designed that allows both contributing Member States and the Secretariat more flexibility in data processing and reporting. Complete documentation is available in the form of a user guide. The cut-off date used for this report is 31 August 1992. This report supersedes IAEA-TECDOC-617 ''Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 1991 Edition''. The information contained in this report is given in six tables. In each of these, information is presented in alphabetical order based on the certificate number. The certificate number is identical with the competent authority identification mark. It is composed of the issuing Member State's international vehicle registration identification (VRI) code, followed by a slash, then a unique number specific to a particular design or shipment that is assigned by the competent authority, another slash and finally a code identifying the type of package involved. ''-85'' is appended to those certificates that were approved on the basis of the 1985 Edition of Safety Series No. 6. Tables 1 to 4 present administrative data including issue and expiry dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6

  11. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2002 ed

    International Nuclear Information System (INIS)

    2002-08-01

    The current edition of the transport Regulations was published in 1996 and is more commonly referred to as 'ST-1'. Earlier Editions were known as Safety Series No. 6. The latest English reprint (2000) is now identified as TS-R-1 (ST-1, Revised). The transport Regulations elaborate requirements for the design, fabrication and maintenance of packaging as well as those for preparation, consigning, handling, carriage, storage in transit and receipt of the packages at final destination. Approval issued in the form of certificates is required for the design or shipment of packages. This report supersedes IAEA-TECDOC-1237 Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2001 Edition. It is distributed worldwide to the IAEA Member States' competent authorities for transport, and other entities who have requested copies. Electronic copies of the main data file are provided to registered users of the PACKTRAM database. The information contained in this report is given in six tables. In each of these, information is presented in alphabetical order based on the certificate number. Tables 1 to 4 present administrative data including issue and expiry dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of the IAEA Transport Safety Regulations on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6 shows the certificates reported to the Secretariat by each participating Member State

  12. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2001 edition

    International Nuclear Information System (INIS)

    2001-08-01

    The current edition of the transport Regulations was published in 1996 and is more commonly referred to as 'ST-1'. Earlier Editions were known as Safety Series No. 6. The latest English reprint (2000) is now identified as TS-R-1 (ST-1, Revised). The transport Regulations elaborate requirements for the design, fabrication and maintenance of packaging as well as those for preparation, consigning, handling, carriage, storage in transit and receipt of the packages at final destination. Approval issued in the form of certificates is required for the design or shipment of packages. This report supersedes IAEA-TECDOC-1171 D irectory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2000 Edition . It is distributed worldwide to the IAEA Member States' competent authorities for transport, and other entities who have requested copies. Electronic copies of the main data file are provided to registered users of the PACKTRAM database. The information contained in this report is given in six tables. In each of these, information is presented in alphabetical order based on the certificate number. Tables 1 to 4 present administrative data including issue and expiry dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of the IAEA Transport Safety Regulations on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6 shows the certificates reported to the Secretariat by each participating Member State

  13. The PACKTRAM database on national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. User's guide for compiled system program

    International Nuclear Information System (INIS)

    1995-01-01

    The PACKTRAM system program enables Member States to prepare data diskettes on national competent authorities' approval certificates for package design, special form material and shipment of radioactive material, for submission to the IAEA, and facilitates data manipulation and report preparation for the IAEA. The system program is provided as a 424 kbyte executable file, for which this document is the User Guide. The system is fully menu-driven and requires an IBM-compatible personal computer with a minimum of 640 kbyte random access memory, a hard drive and one 3-1/2 inch diskette drive. 3 refs, 6 tabs

  14. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1993 ed

    International Nuclear Information System (INIS)

    1993-10-01

    This is the fourth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose memberships consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

  15. Directory of national competent authorities` approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA`s transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ``Regulations for the Safe Transport of Radioactive Material`` highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs.

  16. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1999 Edition

    International Nuclear Information System (INIS)

    1999-08-01

    This is the tenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Advisory Committee (TRANSSAC), formerly known as the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM and endorsed by TRANSSAC, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the 'Regulations for the Safe Transport of Radioactive Material' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

  17. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1994 ed

    International Nuclear Information System (INIS)

    1994-08-01

    This is the fifth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

  18. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1996 edition

    International Nuclear Information System (INIS)

    1996-09-01

    This is the seventh annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificated (PACKTRAM) at the recommendation of the then Standing Advisory Group on the Sate Transport of Radioactive Material (SAGSTRAM). The functions of SAGSTRAM were taken over in 1996 by the Transport Safety Standards Advisory Committee (TRANSSAC). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'', highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

  19. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

    International Nuclear Information System (INIS)

    1995-09-01

    This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

  20. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2000 edition

    International Nuclear Information System (INIS)

    2000-08-01

    Safety in the transport of radioactive material is dependent on packaging appropriate for the contents being shipped, rather than on operational and/or administrative actions required on the package. The grater the radiological risk posed by the material being moved, the more stringent become the performance for the packaging that can be authorised to contain it. These principles have been expanded since 1061 into a set of regulations that are responsible for safety moving the ever-growing number and complexity of radioactive material shipments throughout the world. The IAEA Regulations for the Safe Transport of Radioactive Material are incorporated into UN regulations, as well as the requirements of other international transport organizations. This is the eleventh report published by the IAEA since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport safety Standards Advisory Committee (TRANSSAC). Through the PACKTRAM database, the IAEA collects administrative and technical information provided by the issuing competent authority about package approval certificates

  1. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1997 Edition

    International Nuclear Information System (INIS)

    1997-08-01

    This is the eighth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the then Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The functions of SAGSTRAM were taken over in 1996 by the Transport Safety Standards Advisory Committee (TRANSSAC). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consisted of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who showed a keen interest in the IAEA's transport safety programme. TRANSSAC underscores the importance of data collecting activities and recommends the continued publication of this annual report. The 1985 Edition of Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'', highlights the role of competent authorities in assuring regulatory compliance in their own countries. The issuance of package approval certificates is an important aspects of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

  2. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2004 ed

    International Nuclear Information System (INIS)

    2004-10-01

    The PACKTRAM database contains administrative and technical information provided annually by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. This is the fifteenth PACKTRAM annual report to being published by the IAEA. It is distributed worldwide mainly to designated competent authorities, as well as to registered interested parties. The database itself is maintained at www.packtram.org and can be accessed by the general public

  3. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1991 edition

    International Nuclear Information System (INIS)

    1991-08-01

    The format of this report is a result of recommendations made by the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) at its 6th meeting in November 1987. The database was at that time maintained on the main frame and it was felt that adapting it for use on a personal computer would allow more flexibility in data processing and reporting. This document supersedes TECDOC-552 ''Directory of National Competent Authorities' Approval Certificates for Package Design and Shipment of Radioactive Material 1990 Edition''. Since publication of TECDOC-552, some modifications affecting the structure of the database and reporting formats were undertaken. These are fully described in ''Working Material: The PACKTRAM Database National Competent Authority Package Approval Certificates, User Guide Rev. 1'', which was released in early 1991. The present report is contained in five tables. In each of these, information is presented in alphabetical order based on the certificate number. This is composed of the issuing Member State's VRI code, followed by a slash, then a three- or four-digit number, another slash and finally a code identifying the type of package involved. ''-85'' is appended to those certificates that were approved on the basis of the 1985 Edition of Safety Series No. 6. Tables 1 to 4 present administrative data including issue and expire, dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table. 5

  4. Method for forming materials

    Science.gov (United States)

    Tolle, Charles R [Idaho Falls, ID; Clark, Denis E [Idaho Falls, ID; Smartt, Herschel B [Idaho Falls, ID; Miller, Karen S [Idaho Falls, ID

    2009-10-06

    A material-forming tool and a method for forming a material are described including a shank portion; a shoulder portion that releasably engages the shank portion; a pin that releasably engages the shoulder portion, wherein the pin defines a passageway; and a source of a material coupled in material flowing relation relative to the pin and wherein the material-forming tool is utilized in methodology that includes providing a first material; providing a second material, and placing the second material into contact with the first material; and locally plastically deforming the first material with the material-forming tool so as mix the first material and second material together to form a resulting material having characteristics different from the respective first and second materials.

  5. Special Geometry and Automorphic Forms

    CERN Document Server

    Berglund, P; Wyllard, N; Berglund, Per; Henningson, Mans; Wyllard, Niclas

    1997-01-01

    We consider special geometry of the vector multiplet moduli space in compactifications of the heterotic string on $K3 \\times T^2$ or the type IIA string on $K3$-fibered Calabi-Yau threefolds. In particular, we construct a modified dilaton that is invariant under $SO(2, n; Z)$ T-duality transformations at the non-perturbative level and regular everywhere on the moduli space. The invariant dilaton, together with a set of other coordinates that transform covariantly under $SO(2, n; Z)$, parameterize the moduli space. The construction involves a meromorphic automorphic function of $SO(2, n; Z)$, that also depends on the invariant dilaton. In the weak coupling limit, the divisor of this automorphic form is an integer linear combination of the rational quadratic divisors where the gauge symmetry is enhanced classically. We also show how the non-perturbative prepotential can be expressed in terms of meromorphic automorphic forms, by expanding a T-duality invariant quantity both in terms of the standard special coord...

  6. Special nuclear material simulation device

    Science.gov (United States)

    Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

    2014-08-12

    An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

  7. Smuggling special nuclear materials

    International Nuclear Information System (INIS)

    Lazaroiu, Gheorghe

    1999-01-01

    Ever since the collapse of the former Soviet Union reports have circulated with increasing frequency concerning attempts to smuggle materials from that country's civil and military nuclear programs. Such an increase obviously raises a number of concerns (outlined in the author's introduction), chief among which is the possibility that these materials might eventually fall into the hands of proliferant states or terrorist groups. The following issues are presented: significance of materials being smuggled; sources and smuggling routes; potential customers; international efforts to reduce nuclear smuggling; long-term disposition of fissile materials. (author)

  8. Supercapacitors specialities - Materials review

    Science.gov (United States)

    Obreja, Vasile V. N.

    2014-06-01

    The electrode material is a key component for supercapacitor cell performance. As it is known, performance comparison of commercial available batteries and supercapacitors reveals significantly lower energy storage capability for supercapacitor devices. The energy density of commercial supercapacitor cells is limited to 10 Wh/kg whereas that of common lead acid batteries reaches 35-40 Wh/kg. For lithium ion batteries a value higher than 100 Wh/kg is easily available. Nevertheless, supercapacitors also known as ultracapacitors or electrochemical capacitors have other advantages in comparison with batteries. As a consequence, many efforts have been made in the last years to increase the storage energy density of electrochemical capacitors. A lot of results from published work (research and review papers, patents and reports) are available at this time. The purpose of this review is a presentation of the progress to date for the use of new materials and approaches for supercapacitor electrodes, with focus on the energy storage capability for practical applications. Many reported results refer to nanostructured carbon based materials and the related composites, used for the manufacture of experimental electrodes. A specific capacitance and a specific energy are seldom revealed as the main result of the performed investigation. Thus for nanoprous (activated) carbon based electrodes a specific capacitance up to 200-220 F/g is mentioned for organic electrolyte, whereas for aqueous electrolyte, the value is limited to 400-500 F/g. Significant contribution to specific capacitance is possible from fast faradaic reactions at the electrode-electrolyte interface in addition to the electric double layer effect. The corresponding energy density is limited to 30-50 Wh/kg for organic electrolyte and to 12-17 Wh/kg for aqueous electrolyte. However such performance indicators are given only for the carbon material used in electrodes. For a supercapacitor cell, where two electrodes

  9. Supercapacitors specialities - Materials review

    Energy Technology Data Exchange (ETDEWEB)

    Obreja, Vasile V. N. [National Research and Development Institute for Microtechnologies (IMT-Bucuresti), Bucharest, 126A Erou Iancu Nicolae Street, 077190 (Romania)

    2014-06-16

    The electrode material is a key component for supercapacitor cell performance. As it is known, performance comparison of commercial available batteries and supercapacitors reveals significantly lower energy storage capability for supercapacitor devices. The energy density of commercial supercapacitor cells is limited to 10 Wh/kg whereas that of common lead acid batteries reaches 35-40 Wh/kg. For lithium ion batteries a value higher than 100 Wh/kg is easily available. Nevertheless, supercapacitors also known as ultracapacitors or electrochemical capacitors have other advantages in comparison with batteries. As a consequence, many efforts have been made in the last years to increase the storage energy density of electrochemical capacitors. A lot of results from published work (research and review papers, patents and reports) are available at this time. The purpose of this review is a presentation of the progress to date for the use of new materials and approaches for supercapacitor electrodes, with focus on the energy storage capability for practical applications. Many reported results refer to nanostructured carbon based materials and the related composites, used for the manufacture of experimental electrodes. A specific capacitance and a specific energy are seldom revealed as the main result of the performed investigation. Thus for nanoprous (activated) carbon based electrodes a specific capacitance up to 200-220 F/g is mentioned for organic electrolyte, whereas for aqueous electrolyte, the value is limited to 400-500 F/g. Significant contribution to specific capacitance is possible from fast faradaic reactions at the electrode-electrolyte interface in addition to the electric double layer effect. The corresponding energy density is limited to 30-50 Wh/kg for organic electrolyte and to 12-17 Wh/kg for aqueous electrolyte. However such performance indicators are given only for the carbon material used in electrodes. For a supercapacitor cell, where two electrodes

  10. Supercapacitors specialities - Materials review

    International Nuclear Information System (INIS)

    Obreja, Vasile V. N.

    2014-01-01

    The electrode material is a key component for supercapacitor cell performance. As it is known, performance comparison of commercial available batteries and supercapacitors reveals significantly lower energy storage capability for supercapacitor devices. The energy density of commercial supercapacitor cells is limited to 10 Wh/kg whereas that of common lead acid batteries reaches 35-40 Wh/kg. For lithium ion batteries a value higher than 100 Wh/kg is easily available. Nevertheless, supercapacitors also known as ultracapacitors or electrochemical capacitors have other advantages in comparison with batteries. As a consequence, many efforts have been made in the last years to increase the storage energy density of electrochemical capacitors. A lot of results from published work (research and review papers, patents and reports) are available at this time. The purpose of this review is a presentation of the progress to date for the use of new materials and approaches for supercapacitor electrodes, with focus on the energy storage capability for practical applications. Many reported results refer to nanostructured carbon based materials and the related composites, used for the manufacture of experimental electrodes. A specific capacitance and a specific energy are seldom revealed as the main result of the performed investigation. Thus for nanoprous (activated) carbon based electrodes a specific capacitance up to 200-220 F/g is mentioned for organic electrolyte, whereas for aqueous electrolyte, the value is limited to 400-500 F/g. Significant contribution to specific capacitance is possible from fast faradaic reactions at the electrode-electrolyte interface in addition to the electric double layer effect. The corresponding energy density is limited to 30-50 Wh/kg for organic electrolyte and to 12-17 Wh/kg for aqueous electrolyte. However such performance indicators are given only for the carbon material used in electrodes. For a supercapacitor cell, where two electrodes

  11. Package materials, waste form

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The schedules for waste package development for the various host rocks were presented. The waste form subtask activities were reviewed, with the papers focusing on high-level waste, transuranic waste, and spent fuel. The following ten papers were presented: (1) Waste Package Development Approach; (2) Borosilicate Glass as a Matrix for Savannah River Plant Waste; (3) Development of Alternative High-Level Waste Forms; (4) Overview of the Transuranic Waste Management Program; (5) Assessment of the Impacts of Spent Fuel Disassembly - Alternatives on the Nuclear Waste Isolation System; (6) Reactions of Spent Fuel and Reprocessing Waste Forms with Water in the Presence of Basalt; (7) Spent Fuel Stabilizer Screening Studies; (8) Chemical Interactions of Shale Rock, Prototype Waste Forms, and Prototype Canister Metals in a Simulated Wet Repository Environment; (9) Impact of Fission Gas and Volatiles on Spent Fuel During Geologic Disposal; and (10) Spent Fuel Assembly Decay Heat Measurement and Analysis

  12. Brazing of special metallic materials and material combinations using a special material

    International Nuclear Information System (INIS)

    Lison, R.

    1981-01-01

    The special materials include metals of groups IVa, Va and VIa of the periodic tables and their alloys. Their particular properties have won them applications in many highly specialized industries. For these materials to be used, mastery of thermal joining methods appropriate to their characteristics is necessary. High-temperature brazing is one such method for joining special materials. This paper presents variants of this technique suitable for each individual special material. Compatibility tests between various brazing metals and various special materials have been carried out by simulating the temperature/time cycle involved in brazing procedures. Special materials are relatively expensive, and their special properties are not required at every point in a structure: elsewhere they can be replaced by a different special material or by other metals or alloys. This means that joints must be made between two special materials or between a special material and a conventional material. When certain conditions are fulfilled, such joins can be made by high-temperature brazing. This paper also shows the extent to which the geometry of the join determines the choice of process. Example of applications are also given. (orig.)

  13. LDEF materials special investigation group's data bases

    Science.gov (United States)

    Strickland, John W.; Funk, Joan G.; Davis, John M.

    1993-01-01

    The Long Duration Exposure Facility (LDEF) was composed of and contained a wide array of materials, representing the largest collection of materials flown for space exposure and returned for ground-based analyses to date. The results and implications of the data from these materials are the foundation on which future space missions will be built. The LDEF Materials Special Investigation Group (MSIG) has been tasked with establishing and developing data bases to document these materials and their performance to assure not only that the data are archived for future generations but also that the data are available to the space user community in an easily accessed, user-friendly form. The format and content of the data bases developed or being developed to accomplish this task are discussed. The hardware and software requirements for each of the three data bases are discussed along with current availability of the data bases.

  14. Summary: special waste form lysimeters - arid program

    International Nuclear Information System (INIS)

    Skaggs, R.L.; Walter, M.B.

    1987-01-01

    The purpose of the Special Waste Form Lysimeters - Arid Program is to determine the performance of solidified commercial low-level waste forms using a field-scale lysimeter facility constructed for measuring the release and migration of radionuclides from the waste forms. The performance of these waste forms, as measured by radionuclide concentrations in lysimeter effluent, will be compared to that predicted by laboratory characterization of the waste forms. Waste forms being tested include nuclear power reactor waste streams that have been solidified in cement, Dow polymer, and bitumen. To conduct the field leaching experiments a lysimeter facility was built to measure leachate under actual environmental conditions. Field-scale samples of waste were buried in lysimeters equipped to measure water balance components, effluent radionuclide concentrations, and to a limited extent, radionuclide concentrations in lysimeter soil samples. The waste forms are being characterized by standard laboratory leach tests to obtain estimates of radionuclide release. These estimates will be compared to leach rates observed in the field. Adsorption studies are being conducted to determine the amount of contaminant available for transport after the release. Theoretical solubility calculations will also be performed to investigate whether common solid phases could be controlling radionuclide release. 4 references, 8 figures, 1 table

  15. Safeguards for special nuclear materials

    International Nuclear Information System (INIS)

    Carlson, R.L.

    1979-12-01

    Safeguards, accountability, and nuclear materials are defined. The accuracy of measuring nuclear materials is discussed. The use of computers in nuclear materials accounting is described. Measures taken to physically protect nuclear materials are described

  16. Type B activity limits for air transport - (an examination of special form and non-special form limits)

    International Nuclear Information System (INIS)

    Eyre, P.

    2004-01-01

    This paper examines the application of the ''Q system'' with respect to the maximum limits of activity permitted in Type B (Type B(U) or Type B(M)) packages when transported by air. In particular, estimation is made of the radiological consequences to determine if there is a difference depending on whether the material is in special form or not. An estimate is also made of the radiological consequences of an air accident involving low dispersible radioactive material (LDRM) in the reference Type B package

  17. Safety analysis report for packaging: the ORNL DOT specification 6M - special form package

    Energy Technology Data Exchange (ETDEWEB)

    Schaich, R.W.

    1982-07-01

    The ORNL DOT Specification 6M - Special Form Package was fabricated at the Oak Ridge Nation al Laboratory (ORNL) for the transport of Type B solid non-fissile radioactive materials in special form. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities in special form of non-fissile radioactive materials.

  18. Safety analysis report for packaging: the ORNL DOT Specification 20WC-5 - special form packaging

    International Nuclear Information System (INIS)

    Schaich, R.W.

    1982-10-01

    The ORNL DOT Specification 20WC-5 - Special Form Package was fabricated for the transport of large quantities of solid nonfissile radioactive materials in special form. The package was evaluated on the basis of tests performed at Sandia National Laboratories, Albuquerque, New Mexico on an identical fire and impact shield and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of large quantities of nonfissile radioactive materials in special form

  19. Safety analysis report for packaging: the ORNL DOT specification 6M - special form package

    International Nuclear Information System (INIS)

    Schaich, R.W.

    1982-07-01

    The ORNL DOT Specification 6M - Special Form Package was fabricated at the Oak Ridge Nation al Laboratory (ORNL) for the transport of Type B solid non-fissile radioactive materials in special form. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities in special form of non-fissile radioactive materials

  20. Estimation methods for special nuclear materials holdup

    International Nuclear Information System (INIS)

    Pillay, K.K.S.; Picard, R.R.

    1984-01-01

    The potential value of statistical models for the estimation of residual inventories of special nuclear materials was examined using holdup data from processing facilities and through controlled experiments. Although the measurement of hidden inventories of special nuclear materials in large facilities is a challenging task, reliable estimates of these inventories can be developed through a combination of good measurements and the use of statistical models. 7 references, 5 figures

  1. Control of Nuclear Materials and Special Equipment (Nuclear Safety Regulations)

    International Nuclear Information System (INIS)

    Cizmek, A.; Prah, M.; Medakovic, S.; Ilijas, B.

    2008-01-01

    Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

  2. Composite materials formed with anchored nanostructures

    Science.gov (United States)

    Seals, Roland D; Menchhofer, Paul A; Howe, Jane Y; Wang, Wei

    2015-03-10

    A method of forming nano-structure composite materials that have a binder material and a nanostructure fiber material is described. A precursor material may be formed using a mixture of at least one metal powder and anchored nanostructure materials. The metal powder mixture may be (a) Ni powder and (b) NiAl powder. The anchored nanostructure materials may comprise (i) NiAl powder as a support material and (ii) carbon nanotubes attached to nanoparticles adjacent to a surface of the support material. The process of forming nano-structure composite materials typically involves sintering the mixture under vacuum in a die. When Ni and NiAl are used in the metal powder mixture Ni.sub.3Al may form as the binder material after sintering. The mixture is sintered until it consolidates to form the nano-structure composite material.

  3. Gamma spectrometric discrimination of special nuclear materials

    International Nuclear Information System (INIS)

    Dowdall, M.; Mattila, A.; Ramebaeck, H.; Aage, H.K.; Palsson, S.E.

    2012-12-01

    This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing special nuclear materials. A range of scenarios were developed involving sources that may or may not contain special nuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving special nuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved special nuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

  4. Gamma spectrometric discrimination of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dowdall, M. [Norwegian Radiation Protection Authority (Norway); Mattila, A. [Radiation and Nuclear Safety Authority, Helsinki (Finland); Ramebaeck, H. [Swedish Defence Research Agency, Stockholm (Sweden); Aage, H.K. [Danish Emergency Management Agency, Birkeroed (Denmark); Palsson, S.E. [Icelandic Radiation Safety Authority, Reykjavik (Iceland)

    2012-12-15

    This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing special nuclear materials. A range of scenarios were developed involving sources that may or may not contain special nuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving special nuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved special nuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

  5. Special waste-form lysimeters: Arid

    International Nuclear Information System (INIS)

    Jones, T.L.; Serne, R.J.

    1987-08-01

    The release of contaminant from solidified low-level waste forms is being studied in a field lysimeter facility at the Hanford Site in southeastern Washington State. Duplicate samples of five different waste forms have been buried in 10 lysimeters since March 1984. Waste-form samples represent three different waste streams and four solidification agents (masonry cement, Portland III cement, Dow polymer /sup (a)/, and bitumen). Most precipitation at the Hanford Site arrives as winter snow; this contributes to a strong seasonal pattern in water storage and drainage observed in the lysimeters. The result is an annual range in the volumetric soil water content from 11% in late winter to 7% in the late summer and early fall, as well as annual changes in pore water velocities from approximately 1 cm/wk in early spring to less than 0.05 cm/wk in early fall. Measurable quantities of tritium and cobalt-60 are being collected in lysimeter drainage water. Approximately 30% of the original tritium inventory has been leached from two lysimeters originally containing tritium. Cobalt-60 is present in all waste forms; it is being collected in the leachate from five lysimeters. The total amount released varies, but in each case it is less than 0.1% of the original cobalt inventory of the waste sample. Nonradioactive constituents contained in the waste form, such as sodium, boron, and sulfate, are also being leached

  6. Abelian 2-form gauge theory: special features

    International Nuclear Information System (INIS)

    Malik, R P

    2003-01-01

    It is shown that the four (3 + 1)-dimensional (4D) free Abelian 2-form gauge theory provides an example of (i) a class of field theoretical models for the Hodge theory, and (ii) a possible candidate for the quasi-topological field theory (q-TFT). Despite many striking similarities with some of the key topological features of the two (1 + 1)-dimensional (2D) free Abelian (and self-interacting non-Abelian) gauge theories, it turns out that the 4D free Abelian 2-form gauge theory is not an exact TFT. To corroborate this conclusion, some of the key issues are discussed. In particular, it is shown that the (anti-)BRST and (anti-)co-BRST invariant quantities of the 4D 2-form Abelian gauge theory obey recursion relations that are reminiscent of the exact TFTs but the Lagrangian density of this theory is not found to be able to be expressed as the sum of (anti-)BRST and (anti-)co-BRST exact quantities as is the case with the topological 2D free Abelian (and self-interacting non-Abelian) gauge theories

  7. Scientific text as a special form of communication

    OpenAIRE

    CHERNYAKOVA NATALIA STEPANOVNA

    2016-01-01

    It is asserted in the article that scientific text, even being a product of spiritual culture, never ceased to be the main form of an objectivization of scientific thought and the means of special scientific communication.

  8. Modular forms and special cycles on Shimura curves (AM-161)

    CERN Document Server

    Kudla, Stephen S; Yang, Tonghai

    2006-01-01

    Modular Forms and Special Cycles on Shimura Curves is a thorough study of the generating functions constructed from special cycles, both divisors and zero-cycles, on the arithmetic surface ""M"" attached to a Shimura curve ""M"" over the field of rational numbers. These generating functions are shown to be the q-expansions of modular forms and Siegel modular forms of genus two respectively, valued in the Gillet-Soulé arithmetic Chow groups of ""M"". The two types of generating functions are related via an arithmetic inner product formula. In addition, an analogue of the classical Siegel-Weil

  9. Special purpose materials for fusion application

    International Nuclear Information System (INIS)

    Scott, J.L.; Clinard, F.W. Jr.; Wiffen, F.W.

    1984-01-01

    Originally in 1978 the Special Purpose Materials Task Group was concerned with tritium breeding materials, coolants, tritium barriers, graphite and silicon carbide, ceramics, heat-sink materials, and magnet components. Since then several other task groups have been created, so now the category includes only materials for superconducting magnets and ceramics. For the former application copper-stabilized Nb 3 Sn (Ti) insulated with polyimides will meet the general requirements, so that testing of prototype components is the priority task. Ceramics are required for several critical components of fusion reactors either as dielectrics or as a structural material. Components near the first wall will receive exposures of 5 to 20 MW.year/m"2. Other ceramic applications are well behind the first wall, with lower damage levels. Most insulators operate near room temperature, but ceramic blanket structures may operate up to 1000 0 C. Because of a meager data base, one cannot identify optimum ceramics for structural application; but MgAl 2 O 4 is an attractive dielectric material

  10. Revisited. Euratom's ownership of special fissile materials

    International Nuclear Information System (INIS)

    Pelzer, Norbert

    2015-01-01

    Among all Treaties on the Foundation of the European Community, seemingly, the Euratom Treaty ist the most unobtrusive one having even nearly been declared dead occasionally. For the opponents of nuclear energy the treaty is a thorn in their side because it aims for the peaceful exploitation of nuclear energy. Actually, the treaty likewise aims for the protection of dangers of nuclear energy and encloses a bundle of collective control instruments. The protective purpose provides the community with a strong position in numerous fields towards nuclear energy users including the right to intervene in the operations of nuclear facilities. The communitie's position is further strengthened by the communitie's ownership on special fissile materials. The EAEC Treaty determines: 'Special fissile materials are owned by the community'. The material content of Euratom's ownership is limited by Article 87 of the EAEC Treaty: Unlimited right of use and consumption is granted to the properly possessors unless obligations of the Euratom Treaty oppose. Inherently, the community does not have these rights. It was asked what would be left to the owner Euratom if the properly possessor is entitled to unlimited right of use and even right of consumption.

  11. Advancing Material Models for Automotive Forming Simulations

    International Nuclear Information System (INIS)

    Vegter, H.; An, Y.; Horn, C.H.L.J. ten; Atzema, E.H.; Roelofsen, M.E.

    2005-01-01

    Simulations in automotive industry need more advanced material models to achieve highly reliable forming and springback predictions. Conventional material models implemented in the FEM-simulation models are not capable to describe the plastic material behaviour during monotonic strain paths with sufficient accuracy. Recently, ESI and Corus co-operate on the implementation of an advanced material model in the FEM-code PAMSTAMP 2G. This applies to the strain hardening model, the influence of strain rate, and the description of the yield locus in these models. A subsequent challenge is the description of the material after a change of strain path.The use of advanced high strength steels in the automotive industry requires a description of plastic material behaviour of multiphase steels. The simplest variant is dual phase steel consisting of a ferritic and a martensitic phase. Multiphase materials also contain a bainitic phase in addition to the ferritic and martensitic phase. More physical descriptions of strain hardening than simple fitted Ludwik/Nadai curves are necessary.Methods to predict plastic behaviour of single-phase materials use a simple dislocation interaction model based on the formed cells structures only. At Corus, a new method is proposed to predict plastic behaviour of multiphase materials have to take hard phases into account, which deform less easily. The resulting deformation gradients create geometrically necessary dislocations. Additional micro-structural information such as morphology and size of hard phase particles or grains is necessary to derive the strain hardening models for this type of materials.Measurements available from the Numisheet benchmarks allow these models to be validated. At Corus, additional measured values are available from cross-die tests. This laboratory test can attain critical deformations by large variations in blank size and processing conditions. The tests are a powerful tool in optimising forming simulations prior

  12. Continuous spray forming of functionally gradient materials

    International Nuclear Information System (INIS)

    McKechnie, T.N.; Richardson, E.H.

    1995-01-01

    Researchers at Plasma Processes Inc. have produced a Functional Gradient Material (FGM) through advanced vacuum plasma spray processing for high heat flux applications. Outlined in this paper are the manufacturing methods used to develop a four component functional gradient material of copper, tungsten, boron, and boron nitride. The FGM was formed with continuous gradients and integral cooling channels eliminating bondlines and providing direct heat transfer from the high temperature exposed surface to a cooling medium. Metallurgical and x-ray diffraction analyses of the materials formed through innovative VPS (vacuum plasma spray) processing are also presented. Applications for this functional gradient structural material range from fusion reactor plasma facing components to missile nose cones to boilers

  13. Special nuclear material inventory sampling plans

    International Nuclear Information System (INIS)

    Vaccaro, H.; Goldman, A.

    1987-01-01

    Since their introduction in 1942, sampling inspection procedures have been common quality assurance practice. The U.S. Department of Energy (DOE) supports such sampling of special nuclear materials inventories. The DOE Order 5630.7 states, Operations Offices may develop and use statistically valid sampling plans appropriate for their site-specific needs. The benefits for nuclear facilities operations include reduced worker exposure and reduced work load. Improved procedures have been developed for obtaining statistically valid sampling plans that maximize these benefits. The double sampling concept is described and the resulting sample sizes for double sample plans are compared with other plans. An algorithm is given for finding optimal double sampling plans that assist in choosing the appropriate detection and false alarm probabilities for various sampling plans

  14. Molten salt processes in special materials preparation

    International Nuclear Information System (INIS)

    Krishnamurthy, N.; Suri, A.K.

    2013-01-01

    As a class, molten salts are the largest collection of non aqueous inorganic solvents. On account of their stability at high temperature and compatibility to a number of process requirements, molten salts are considered indispensable to realize many of the numerous benefits of high temperature technology. They play a crucial role and form the basis for numerous elegant processes for the preparation of metals and materials. Molten salt are considered versatile heat transfer media and have led to the evolution of many interesting reactor concepts in fission and possibly in fusion. They also have been the basis of thinking for few novel processes for power generation. While focusing principally on the actual utilization of molten salts for a variety of materials preparation efforts in BARC, this lecture also covers a few of the other areas of technological applications together with the scientific basis for considering the molten salts in such situations. (author)

  15. Special from encapsulation for radioactive material shipments from Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Schaich, R.W.

    1980-01-01

    Special Form encapsulation has been used at Oak Ridge National Laboratory to ship radioactive solids for the past fifteen years. A family of inexpensive stainless steel containers has been developed and tested to meet the USA Department of Transportation (DOT) and the International Atomic Energy Agency (IAEA) regulations concerning radioactive material shipments as Special Form

  16. Detecting special nuclear material using muon-induced neutron emission

    Energy Technology Data Exchange (ETDEWEB)

    Guardincerri, Elena; Bacon, Jeffrey; Borozdin, Konstantin; Matthew Durham, J.; Fabritius II, Joseph [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Hecht, Adam [University of New Mexico, Albuquerque, NM 87131 (United States); Milner, Edward C. [Southern Methodist University, Dallas, TX 75205 (United States); Miyadera, Haruo; Morris, Christopher L. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Perry, John [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); University of New Mexico, Albuquerque, NM 87131 (United States); Poulson, Daniel [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

    2015-07-21

    The penetrating ability of cosmic ray muons makes them an attractive probe for imaging dense materials. Here, we describe experimental results from a new technique that uses neutrons generated by cosmic-ray muons to identify the presence of special nuclear material (SNM). Neutrons emitted from SNM are used to tag muon-induced fission events in actinides and laminography is used to form images of the stopping material. This technique allows the imaging of SNM-bearing objects tagged using muon tracking detectors located above or to the side of the objects, and may have potential applications in warhead verification scenarios. During the experiment described here we did not attempt to distinguish the type or grade of the SNM.

  17. 10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

  18. Special purpose materials. Annual progress report, October 1, 1979

    International Nuclear Information System (INIS)

    1980-04-01

    Fusion reactor materials problems other than the first-wall and blanket structural materials are investigated. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, grahite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. Radiation-induced conductivity of three forms of Al 2 O 3 was measured as a function of ionizing dose rate and temperature. Increases observed are large enough to affect performance of insulators under some fusion reactor operating conditions. Single-crystal MgAl 2 O 4 was shown to exhibit zero swelling when irradiated to approx. 2 x 10 26 n/m 2 at 925 and 1100 K. This ceramic is resistant to nucleation and growth of defect aggregates, and is not characterized by those microstructural conditions which lead to void formation and swelling in Al 2 O 3 . Fracture toughness of single-crystal Al 2 O 3 was significantly increased by elevated-temperature irradiation to approx. 2 x 10 26 n/m 2 , while that for MgAl 2 O 4 and Y 3 Al 5 O 12 showed little or no change. These results show that ceramics can retain their original resistance to crack propagation after high-dose neutron irradiation

  19. Some political issues related to future special nuclear materials production

    International Nuclear Information System (INIS)

    Peaslee, A.T. Jr.

    1981-08-01

    The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors

  20. Alloy-steel bolting materials for special applications

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This specification covers regular and special-quality alloy steel bolting materials which may be used for nuclear and other special applications. Bolting materials as used in the specification cover rolled or forged bars, rotary pierced or extruded seamless tubes, bored bars, or forged hollows from forged or rolled bar segments to be machined into bolts, studs, washers, and nuts. Several grades of steel are covered and supplementary requirements of an optional nature are provided for use when special quality is desired

  1. Special waste form lysimeters-arid. Annual report, 1985

    International Nuclear Information System (INIS)

    Walter, M.B.; Graham, M.J.

    1985-09-01

    The Special Waste Form Lysimeters-Arid program was initiated to determine typical source terms generated by commercial solidified low-level nuclear waste in an arid climate. Waste-form leaching tests are being conducted at a field facility at the Hanford site near Richland, Washington. A similar program is being conducted at a humid site. The field facility consists of 10 lysimeters placed around a central instrument caisson. The waste samples from boiling water and pressurized water reactors were emplaced in 1984, and the lysimeters are being monitored for movement of contaminants and water. Solidifying agents being tested include vinyl ester-styrene, bitumen, and cement. Laboratory leaching and geochemical modeling studies are being conducted to predict expected leach rates at the field site and to aid field-data interpretation. Small samples of the solidified waste forms were made for use in the laboratory leaching studies that include standard leach tests and leaching of solidified waste forms in soil columns. Complete chemical and radionuclide analyses are being conducted on the solid and liquid portions of the wastes. 2 refs

  2. Special Waste Form Lysimeters-Arid: annual report 1985

    International Nuclear Information System (INIS)

    Walter, M.B.; Graham, M.J.

    1986-01-01

    The Special Waste Form Lysimeters-Arid program was initiated to determine typical source terms generated by commercial solidified low-level nuclear waste in an arid climate. Waste-form leaching tests are being conducted at a field facility at the Hanford site near Richland, Washington. A similar program is being conducted at a humid site. The field facility consists of 10 lysimeters placed around a central instrument caisson. The waste samples from boiling water and pressurized water reactors were emplaced in 1984, and the lysimeters are being monitored for movement of contaminants and water. Solidifying agents being tested include vinyl ester-styrene, bitumen, and cement. Laboratory leaching and geochemical modeling studies are being conducted to predict expected leach rates at the field site and to aid field-data interpretation. Small samples of the solidified waste forms were made for use in the laboratory leaching studies that include standard leach tests and leaching of solidified waste forms in soil columns. Complete chemical and radionuclide analyses are being conducted on the solid and liquid portions of the wastes

  3. Special requirements for bolting material for nuclear and other special applications

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A specification that provides special requirements for bolting material for use in nuclear and other special applications is presented. The requirements of the specification are supplemental to the requirements of the basic material specifications and they include tempering, welding, elimination of surface defects, certification and identification, quality assurance and various examination methods

  4. Special metals - materials of modern technology

    International Nuclear Information System (INIS)

    Booss, H.J.

    1977-01-01

    This article is anether attempt to give a survey of special metals, their production, processing and application, as has been made in four previous articles. The article confines itself essentially to publications made in 12 German and 12 English journals, focussed on metallurgy, metallography, electrochemistry, and sections of electrical engineering. For the first time, some articles written in Russian have been included. (orig./IHOE) [de

  5. Report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1977-08-01

    Information concerning accounting for significant quantities of strategic special nuclear material (SSNM) in ERDA facilities is reported. Inventory difference data are provided for fiscal year 1976 for ERDA and ERDA contractor facilities that possessed significant quantities of SSNM

  6. General and special engineering materials science. Vol. 1

    International Nuclear Information System (INIS)

    Ondracek, G.; Voehringer, O.

    1983-04-01

    The present report about general and special engineering materials science is the result of lectures given by the authors in two terms in 1982 at Instituto Balseiro, San Carlos de Bariloche, the graduated college of the Universidad de Cuyo and Comision Nacional de Energia Atomica, Republica Argentina. These lectures were organised in the frame of the project ''nuclear engineering'' (ARG/78/020) of the United Nations Development Program (UNDP) by the International Atomic Energy Agency (IAEA). Some chapters of the report are written in English, others in Spanish. The report is subdivided into three volumes: Volume I treats general engineering materials science in 4 capital chapters on the structure of materials, the properties of materials, materials technology and materials testing and investigation supplemented by a selected detailed chapter about elasticity plasticity and rupture mechanics. Volume II concerns special engineering materials science with respect to nuclear materials under normal reactor operation conditions including reactor clad and structural materials, nuclear fuels and fuel elements and nuclear waste as a materials viewpoint. Volume III - also concerning special engineering materials science - considers nuclear materials with respect to off-normal (''accident'') reactor operation conditions including nuclear materials in loss-of-coolant accidents and nuclear materials in core melt accidents. (orig.) [de

  7. Optoelectronic inventory system for special nuclear material

    International Nuclear Information System (INIS)

    Sieradzki, F.H.

    1994-01-01

    In support of the Department of Energy's Dismantlement Program, the Optoelectronics Characterization and Sensor Development Department 2231 at Sandia National Laboratories/New Mexico has developed an in situ nonintrusive Optoelectronic Inventory System (OIS) that has the potential for application wherever periodic inventory of selected material is desired. Using a network of fiber-optic links, the OIS retrieves and stores inventory signatures from data storage devices (which are permanently attached to material storage containers) while inherently providing electromagnetic pulse immunity and electrical noise isolation. Photovoltaic cells (located within the storage facility) convert laser diode optic power from a laser driver to electrical energy. When powered and triggered, the data storage devices sequentially output their digital inventory signatures through light-emitting diode/photo diode data links for retrieval and storage in a mobile data acquisition system. An item's exact location is determined through fiber-optic network and software design. The OIS provides an on-demand method for obtaining acceptable inventory reports while eliminating the need for human presence inside the material storage facility. By using modularization and prefabricated construction with mature technologies and components, an OIS installation with virtually unlimited capacity can be tailored to the customer's requirements

  8. Special Purpose Materials annual progress report, October 1, 1979

    International Nuclear Information System (INIS)

    1980-04-01

    The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (> 10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits

  9. Enviromental Development Plan: special nuclear materials production

    International Nuclear Information System (INIS)

    1980-07-01

    This Environmental Development Plan includes the process steps and facilities necessary for the production of plutonium and tritium for Government needs and the production of some other radioactive materials that will be used for heat and radiation sources by domestic and international customers. The production reactors and the spent fuel processing plants and their effluents are discussed, but the defense wastes from them are treated in a separate EDP. The scope does not include transportation, decontamination and decommissioning, safeguards and security, or use of the SNM products

  10. Specialized equipment needs for the transportation of radioactive material

    International Nuclear Information System (INIS)

    Condrey, D.; Lambert, M.

    1998-01-01

    To ensure the safe and reliable transportation of radioactive materials and components, from both the front and back-end of the nuclear fuel cycle, a transport management company needs three key elements: specialized knowledge, training and specialized equipment. These three elements result, in part, from national and international regulations which require specialized handling of all radioactive shipments. While the reasons behind the first two elements are readily apparent, the role of specialized equipment is often not considered until too late shipment process even though it plays an integral part of any radioactive material transport. This paper will describe the specialized equipment needed to transport three of the major commodities comprising the bulk of international nuclear transports: natural uranium (UF6), low enriched uranium (UF6) and fresh nuclear fuel. (authors)

  11. A pneumatic transfer system for special form 252Cf

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Berry, S.M.; Grafwallner, E.G.; Hoggan, J.M.

    1996-09-01

    A pneumatic transfer system has been developed for use with series 100 Special Form 252 Cf. It was developed to reduce the exposure to personnel handling sources of 252 Cf with masses up to 150 microg by permitting remotely activated two-way transfer between the storage container and the irradiation position. The pneumatic transfer system also permits transfers for reproducible repetitive irradiation periods. In addition to the storage container equipped with quick-release fittings, the transfer system consists of an irradiation station, a control box with momentary contact switches to activate the air-pressure control valves and indicators to identify the location of the source, and connecting air hose and electrical wire. A source of 20 psig air and 110 volt electrical power are required for operation of the transfer system which can be easily moved and set up by one individual in 5 to 10 minutes. Tests have shown that rarely does a source become lodged in the transfer tubing, but two methods have been developed to handle incomplete transfers of the 252 Cf source. The first method consists of closing one air vent to allow a pressure impulse to propel the source to the opposite side. The second method applies to those 252 Cf capsules with a threaded or tapped end to which a small ferromagnetic piece can be attached; an incompletely transferred source in the transfer tube can then be guided to a position of safety by surrounding the transfer tubing containing the capsule with a horseshoe magnet attached to the end of a long pole

  12. Microchannel plate special nuclear materials sensor

    International Nuclear Information System (INIS)

    Feller, W.B.; White, P.L.; White, P.B.; Siegmund, O.H.W.; Martin, A.P.; Vallerga, J.V.

    2011-01-01

    Nova Scientific Inc., is developing for the Domestic Nuclear Detection Office (DNDO SBIR no. HSHQDC-08-C-00190), a solid-state, high-efficiency neutron detection alternative to 3 He gas tubes, using neutron-sensitive microchannel plates (MCPs) containing 10 B and/or Gd. This work directly supports DNDO development of technologies designed to detect and interdict nuclear weapons or illicit nuclear materials. Neutron-sensitized MCPs have been shown theoretically and more recently experimentally, to be capable of thermal neutron detection efficiencies equivalent to 3 He gas tubes. Although typical solid-state neutron detectors typically have an intrinsic gamma sensitivity orders of magnitude higher than that of 3 He gas detectors, we dramatically reduce gamma sensitivity by combining a novel electronic coincidence rejection scheme, employing a separate but enveloping gamma scintillator. This has already resulted in a measured gamma rejection ratio equal to a small 3 He tube, without in principle sacrificing neutron detection efficiency. Ongoing improvements to the MCP performance as well as the coincidence counting geometry will be described. Repeated testing and validation with a 252 Cf source has been underway throughout the Phase II SBIR program, with ongoing comparisons to a small commercial 3 He gas tube. Finally, further component improvements and efforts toward integration maturity are underway, with the goal of establishing functional prototypes for SNM field testing.

  13. Method of forming aluminum oxynitride material and bodies formed by such methods

    Science.gov (United States)

    Bakas, Michael P [Ammon, ID; Lillo, Thomas M [Idaho Falls, ID; Chu, Henry S [Idaho Falls, ID

    2010-11-16

    Methods of forming aluminum oxynitride (AlON) materials include sintering green bodies comprising aluminum orthophosphate or another sacrificial material therein. Such green bodies may comprise aluminum, oxygen, and nitrogen in addition to the aluminum orthophosphate. For example, the green bodies may include a mixture of aluminum oxide, aluminum nitride, and aluminum orthophosphate or another sacrificial material. Additional methods of forming aluminum oxynitride (AlON) materials include sintering a green body including a sacrificial material therein, using the sacrificial material to form pores in the green body during sintering, and infiltrating the pores formed in the green body with a liquid infiltrant during sintering. Bodies are formed using such methods.

  14. Special Issue: NextGen Materials for 3D Printing

    Directory of Open Access Journals (Sweden)

    Chee Kai Chua

    2018-04-01

    Full Text Available Only a handful of materials are well-established in three-dimensional (3D printing and well-accepted in industrial manufacturing applications. However, recent advances in 3D printable materials have shown potential for enabling numerous novel applications in the future. This special issue, consisting of 2 reviews and 10 research articles, intends to explore the possible materials that could define next-generation 3D printing.

  15. Annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1991-01-01

    This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1989 through March 31, 1990 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear material. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses was the included data. The data in this report have been prepared and reviewed by DOE contractors, field offices, and Headquarters. When necessary, special investigations have been performed in addition to these reviews: This ID data, explanations, reviews, and any additional special investigations, together with the absence of physical indications of any theft attempt, support a finding that no theft or diversion of significant quantities of strategic special nuclear material has occurred in DOE facilities during the twelve-month period covered by this report

  16. Radiation damage in natural materials: implications for radioactive waste forms

    International Nuclear Information System (INIS)

    Ewing, R.C.

    1981-01-01

    The long-term effect of radiation damage on waste forms, either crystalline or glass, is a factor in the evaluation of the integrity of waste disposal mediums. Natural analogs, such as metamict minerals, provide one approach for the evaluaton of radiation damage effects that might be observed in crystalline waste forms, such as supercalcine or synroc. Metamict minerals are a special class of amorphous materials which were initially crystalline. Although the mechanism for the loss of crystallinity in these minerals (mostly actinide-containing oxides and silicates) is not clearly understood, damage caused by alpha particles and recoil nuclei is critical to the metamictization process. The study of metamict minerals allows the evaluation of long-term radiation damage effects, particularly changes in physical and chemical properties such as microfracturing, hydrothermal alteration, and solubility. In addition, structures susceptible to metamictization share some common properties: (1) complex compositions; (2) some degree of covalent bonding, instead of being ionic close-packed MO/sub x/ structures; and (3) channels or interstitial voids which may accommodate displaced atoms or absorbed water. On the basis of these empirical criteria, minerals such as pollucite, sodalite, nepheline and leucite warrant careful scrutiny as potential waste form phases. Phases with the monazite or fluorite structures are excellent candidates

  17. General and special engineering materials science. Vol. 3

    International Nuclear Information System (INIS)

    Ondracek, G.; Hofmann, P.

    1983-04-01

    The report about general and special engineering materials science is the result of lectures given by the authors in two terms in 1982 at Instituto Balseiro, San Carlos de Bariloche, the graduated college of the Universidad de Cuyo and Comision Nacional de Energia Atomica, Republica Argentina. These lectures were organised in the frame of the project ''nuclear engineering'' (ARG/78/020) of the United Nations Development Program (UNDP) by the International Atomic Energy Agency (IAEA). Some chapters of the report are written in English, others in Spanish. The report is subdivided into three volumes. The present volume III concerns special engineering materials science and considers nuclear materials with respect to off-normal (''accident'') reactor operation conditions including nuclear materials in loss-of-coolant accident and nuclear materials in core melt accidents. (orig./IHOE) [de

  18. General and special engineering materials science. Vol. 2

    International Nuclear Information System (INIS)

    Anderko, K.; Kummerer, K.R.; Ondracek, G.

    1983-04-01

    The present report about general and special engineering materials science is the result of lectures given by the authors in two terms in 1982 at Instituto Balseiro, San Carlos de Bariloche, the graduated college of the Universidad de Cuyo and Comision Nacional de Energia Atomica, Republica Argentina. These lectures were organised in the frame of the project ''nuclear engineering'' (ARG/78/020) of the United Nations Development Program (UNDP) by the International Atomic Energy Agency (IAEA). Some chapters of the report are written in English, others in Spanish. The report is subdivided into three volumes. The present volume II concerns special engineering materials science with respect to nuclear materials under normal reactor operation conditions including 1. reactor clad and structural materials, 2. nuclear fuels and fuel elements, 3. nuclear waste as a materials viewpoint. (orig./IHOE) [de

  19. Leach test of six 192-iridium pellets based on the IAEA 'special form' test procedures

    International Nuclear Information System (INIS)

    Gordon, G.; Gerdingh, R.

    1981-07-01

    The designation 'special form' may be applied to indispersible solid radioactive material if the material meets the requirements of the tests described in the International Atomic Energy Agency Regulations for the Safe Transport of Radioactive Type Materials. This report presents the procedures and results of a leach test performed as specified in the regulations on 6 'as received' active 192-iridium pellets. Mechanical tests were not carried out prior to or following the leach test. The activity of each of the first 6 water baths was found to be between 2.3 and 12.6 μCi, (8.5 x 10 4 and 4.7 x 10 5 Bq) and of the second 6, between 1.3 to 6.0 μCi, (4.8 x 10 4 to 2.2 x 10 5 Bq) thus exceeding the allowable limit

  20. Smart material interfaces: a new form of physical interaction

    NARCIS (Netherlands)

    Chi, E.H.; Vyas, Dhaval; Poelman, Wim; Höök, K,; Nijholt, Antinus; De Bruijn, Arnoud

    2012-01-01

    Smart Material Interface (SMI) is the latest generation of user interface that makes use of engineered materials and leverages their special properties. SMIs are capable of changing their physical properties such as shape, size and color, and can be controlled under certain (external) conditions. We

  1. Active neutron technique for detecting attempted special nuclear material diversion

    International Nuclear Information System (INIS)

    Smith, G.W.; Rice, L.G. III.

    1979-01-01

    The identification of special nuclear material (SNM) diversion is necessary if SNM inventory control is to be maintained at nuclear facilities. (Special nuclear materials are defined for this purpose as either 235 U of 239 Pu.) Direct SNM identification by the detection of natural decay or fission radiation is inadequate if the SNM is concealed by appropriate shielding. The active neutron interrogation technique described combines direct SNM identification by delayed fission neutron (DFN) detection with implied SNM detection by the identification of materials capable of shielding SNM from direct detection. This technique is being developed for application in an unattended material/equipment portal through which items such as electronic instruments, packages, tool boxes, etc., will pass. The volume of this portal will be 41-cm wide, 53-cm high and 76-cm deep. The objective of this technique is to identify an attempted diversion of at least 20 grams of SNM with a measurement time of 30 seconds

  2. [Preface for special issue on bio-based materials (2016)].

    Science.gov (United States)

    Weng, Yunxuan

    2016-06-25

    Bio-based materials are new materials or chemicals with renewable biomass as raw materials such as grain, legume, straw, bamboo and wood powder. This class of materials includes bio-based polymer, biobased fiber, glycotechnology products, biobased rubber and plastics produced by biomass thermoplastic processing and basic biobased chemicals, for instance, bio-alcohols, organic acids, alkanes, and alkenes, obtained by bio-synthesis, bio-processing and bio-refinery. Owing to its environmental friendly and resource conservation, bio-based materials are becoming a new dominant industry taking the lead in the world scientific and technological innovation and economic development. An overview of bio-based materials development is reported in this special issue, and the industrial status and research progress of the following aspects, including biobased fiber, polyhydroxyalkanoates, biodegradable mulching film, bio-based polyamide, protein based biomedical materials, bio-based polyurethane, and modification and processing of poly(lactic acid), are introduced.

  3. Active and Passive Diagnostic Signatures of Special Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Myers, William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, Steven Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-26

    An overview will be given discussing signatures associated with special nuclear materials acquired using both active and passive diagnostic techniques. Examples of how technology advancements have helped improve diagnostic capabilities to meet the challenges of today’s applications will be discussed.

  4. 10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

  5. Considerations for sampling nuclear materials for SNM accounting measurements. Special nuclear material accountability report

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Upson, U.L.

    1978-05-01

    This report presents principles and guidelines for sampling nuclear materials to measure chemical and isotopic content of the material. Development of sampling plans and procedures that maintain the random and systematic errors of sampling within acceptable limits for SNM(Special Nuclear Materials) accounting purposes are emphasized

  6. Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

    Science.gov (United States)

    Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

    2009-01-27

    A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

  7. Investigation of Resistance to Mechanical Effect of Braille Formed on Different Materials

    Directory of Open Access Journals (Sweden)

    Ingrida VENYTĖ

    2014-06-01

    Full Text Available Qualitative analysis of stresses emerged in paperboard during Braille embossing, using specialized polarimetric equipment, was carried out. Resistance to mechanical effect of Braille dot surfaces, formed with different printing types on different materials (paper, paperboard, polymer, textile, Al foil was investigated. It was determined that Braille dot height change after period mechanical effect is different.

  8. Methods of Verification, Accountability and Control of Special Nuclear Material

    International Nuclear Information System (INIS)

    Stewart, J.E.

    1999-01-01

    This session demonstrates nondestructive assay (NDA) measurement, surveillance and analysis technology required to protect, control and account (MPC and A) for special nuclear materials (SNM) in sealed containers. These measurements, observations and analyses comprise state-of-the art, strengthened, SNM safeguards systems. Staff member specialists, actively involved in research, development, training and implementation worldwide, will present six NDA verification systems and two software tools for integration and analysis of facility MPC and A data

  9. Physical protection of facilities and special nuclear materials in france

    International Nuclear Information System (INIS)

    Jeanpierre, G.

    1980-01-01

    Physical protection of nuclear facilities and special nuclear materials is subject in France to a national governmental regulation which provides for the basic principles to be taken into account and the minimal level of protection deemed necessary. But the responsibility of implementation is left to the facility management and the resulting decentralization allows for maximum efficiency. All safeguards measures comply with the commitments taken at the international level by the French government

  10. Technology of forming a positive attitude to physical training students of special medical group

    Directory of Open Access Journals (Sweden)

    Mukhamediarov N.N.

    2013-04-01

    Full Text Available Defined effective technology stages of forming a positive attitude towards physical education of students in special medical groups, stimulate motivation, epistemologically, informative, content-procedural, analytical and adjustment. For each stage technology offered special tools: lectures, seminars, analysis articles, mini conference on improving technique, racing games, mini-competitions, diagnostic interviews, questionnaires, analysis of log data on attendance. Selected criteria forming positive attitudes towards physical education: theoretical and practical, formed groups for research: experimental and control, analyzed results introduction of technology, efficiency of the proposed technology and means forming a positive attitude towards physical education students in special medical groups.

  11. The first Polish conference: Special glasses and amorphous materials. Introduction

    International Nuclear Information System (INIS)

    1993-01-01

    The present issue brings a collection of papers submitted to the 1. Polish Conference on special glasses and amorphous materials, held on June 1993 at the University of Mining and Metallurgy in Cracow. It was a survey of the research topics and attainments of the research teams working in this referring to the nature of the glassy state of the matter and the relation between glasses and other amorphous materials, properties of these materials as well as modern methods of their synthesis both at low and high temperatures. Some of the results presented at the Conference have already found application in industry. Here belong, among others, the works on optic fibres. Several new materials which have been recently elaborated may also find interesting and new practical application. (author)

  12. Metallurgy and properties of plasma spray formed materials

    Science.gov (United States)

    Mckechnie, T. N.; Liaw, Y. K.; Zimmerman, F. R.; Poorman, R. M.

    1992-01-01

    Understanding the fundamental metallurgy of vacuum plasma spray formed materials is the key to enhancing and developing full material properties. Investigations have shown that the microstructure of plasma sprayed materials must evolve from a powder splat morphology to a recrystallized grain structure to assure high strength and ductility. A fully, or near fully, dense material that exhibits a powder splat morphology will perform as a brittle material compared to a recrystallized grain structure for the same amount of porosity. Metallurgy and material properties of nickel, iron, and copper base alloys will be presented and correlated to microstructure.

  13. Guide for the preparation of applications for special nuclear material licenses of less than critical mass quantities - July 1976

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This guide describes the type of information needed to evaluate an application for a specific license for receipt, possession, use, and transfer of special nuclear material. It is intended for applicants requesting authorization to possess and use up to 2000 grams of plutonium, total, in the form of sealed plutonium-beryllium neutron sources, and any special nuclear material in quantities and forms not sufficient to form a critical mass. The latter quantities are considered to be 350 grams of contained uranium-235, 200 grams of uranium-233, 200 grams of plutonium (in any form other than plutonium-beryllium neutron sources) or any combination of them

  14. Friction stir method for forming structures and materials

    Science.gov (United States)

    Feng, Zhili; David, Stan A.; Frederick, David Alan

    2011-11-22

    Processes for forming an enhanced material or structure are disclosed. The structure typically includes a preform that has a first common surface and a recess below the first common surface. A filler is added to the recess and seams are friction stir welded, and materials may be stir mixed.

  15. The Transport of Radioactive Materials under special arrangement

    International Nuclear Information System (INIS)

    Biaggio, A.L.; Vietri, J.R.L.

    1993-01-01

    The Agency's Regulations for the Safe Transport of Radioactive Material rule the international transport of these materials and provide the basis of national and regional regulations. The Regulations establish the technical, operational and administrative requirements which shall be accomplished to carry out the transport of radioactive materials (RAM). They also allow the transport in different conditions of those currently applicable and, in such cases, establish that the transport shall be made under special arrangement. To approve a transport under special arrangement the involved Competent Authority shall be satisfied that the alternative provisions are adequate to ensure that the overall level of safety in transport and in-transit storage is at least equivalent to that which would be provided if all the applicable requirements had been met (para. 2ll of the International Atomic Energy Agency Safety Series No. 6). This paper explains some difficulties the Argentine Competent. Authority has experienced trying by comparing the equivalence between the level of safety resulting from the compliance with current requirements and the overall level of safety which is provided by the application of alternative provisions. As most of the experience gained come from the transport of RAM by road, only this mode of transport is considered. (J.P.N.)

  16. Special nuclear material information, security classification guidance. Instruction

    International Nuclear Information System (INIS)

    Flickinger, A.

    1982-01-01

    The Instruction reissues DoD Instruction 5210.67, July 5, 1979, and provides security classification guidance for information concerning significant quantities of special nuclear material, other than that contained in nuclear weapons and that used in the production of energy in the reactor plant of nuclear-powered ships. Security classification guidance for these data in the latter two applications is contained in Joint DoE/DoD Nuclear Weapons Classification Guide and Joint DoE/DoD Classification Guide for the Naval Nuclear Propulsion Program

  17. Real-time inventory system for special nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Kuckertz, T.H.; Ethridge, C.D.; Nicholson, N.

    1979-01-01

    This paper describes a special purpose peripheral device for a minicomputer that can monitor SNM in vault storage in real time and give timely indication of any tampering with the material. This device, called a shelf monitor, is designed around a single-chip microcomputer, and can be manufactured in quantity for about $100. A typical system of shelf monitors controlled by a minicomputer is described. The minicomputer is used to acquire data associated with the weight and gamma activity of the sample of SNM under observation. Significant deviations in the weight and gamma activity are cause for a tampering alarm.

  18. Real-time inventory system for special nuclear material

    International Nuclear Information System (INIS)

    Kuckertz, T.H.; Ethridge, C.D.; Nicholson, N.

    1979-01-01

    This paper describes a special purpose peripheral device for a minicomputer that can monitor SNM in vault storage in real time and give timely indication of any tampering with the material. This device, called a shelf monitor, is designed around a single-chip microcomputer, and can be manufactured in quantity for about $100. A typical system of shelf monitors controlled by a minicomputer is described. The minicomputer is used to acquire data associated with the weight and gamma activity of the sample of SNM under observation. Significant deviations in the weight and gamma activity are cause for a tampering alarm

  19. Semiannual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1987-07-01

    This twentieth periodic semiannual report of unclassified Inventory Differences (ID's) covers the second six months of fiscal year 1986 (April 1, 1986, through September 30, 1986) for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Data for the Rocky Flats and Y-12 nuclear weapons production facilities are not included in the report in order to protect classified nuclear weapons information; however, classified ID data from these facilities receive the same scrutiny and analyses as the unclassified data

  20. Westinghouse Hanford Company special nuclear material vault storage study

    International Nuclear Information System (INIS)

    Borisch, R.R.

    1996-01-01

    Category 1 and 2 Special Nuclear Materials (SNM) require storage in vault or vault type rooms as specified in DOE orders 5633.3A and 6430.1A. All category 1 and 2 SNM in dry storage on the Hanford site that is managed by Westinghouse Hanford Co (WHC) is located in the 200 West Area at Plutonium Finishing Plant (PFP) facilities. This document provides current and projected SNM vault inventories in terms of storage space filled and forecasts available space for possible future storage needs

  1. Special issue on "Frontiers in Materials Science: Condensed matters"

    Science.gov (United States)

    Hoang, Nam-Nhat; Yamamoto, Tomoyuki; Pham, Duc-Thang

    2018-03-01

    This special issue includes the editor-invited and selected papers from 3rd International Symposium on Frontiers in Materials Science (FMS2016), held in Hanoi, Vietnam, from the 28th to 30th of September 2016, which coincided with the 65th anniversary of the Faculty of Physics, Hanoi University of Education. The FMS2016 is a continuation of a series of meetings starting from 2010. A first event was a bilateral Vietnamese-German meeting in Hanoi, Vietnam, in 2010, and the second one was held in Frankfurt, Germany, in 2011. The idea at that time was to initiate interactions between scientists from both countries and to further develop the field of materials science in Southeast Asia. After these successful bilateral meetings, a next step was taken by advancing the format of the symposium into an international event. In 2013, the 1st International Symposium on Frontiers in Materials Science (FMS2013) was successfully organized in Hanoi, which followed 2nd symposium, FMS2015, in Tokyo, in 2015. The FMS2016 continues this idea of providing an international forum for physicists, material scientists and chemists for discussing their latest results and the recent developments in the important field of materials science.

  2. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    DeAnn Long; Michael Murphy

    2008-01-01

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

  3. Special Nuclear Material Gamma-Ray Signatures for Reachback Analysts

    Energy Technology Data Exchange (ETDEWEB)

    Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, Steven Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-08-29

    These are slides on special nuclear material gamma-ray signatures for reachback analysts for an LSS Spectroscopy course. The closing thoughts for this presentation are the following: SNM materials have definite spectral signatures that should be readily recognizable to analysts in both bare and shielded configurations. One can estimate burnup of plutonium using certain pairs of peaks that are a few keV apart. In most cases, one cannot reliably estimate uranium enrichment in an analogous way to the estimation of plutonium burnup. The origin of the most intense peaks from some SNM items may be indirect and from ‘associated nuclides.' Indirect SNM signatures sometimes have commonalities with the natural gamma-ray background.

  4. Development of soft magnetic materials with special properties

    International Nuclear Information System (INIS)

    Mager, A.

    1979-01-01

    New steps in the development of soft magnetic alloys are based on a better understanding of the magnetizing processes in close connection with the development of magnetic forms and components for different applications. New result on the influence of crystal grains, inclusions, and mechanical stresses on the soft magnetic properties of Ni-Fe-alloys with ca. 50 to 75% Nickel-contents are given. Special soft magnetic alloys were developed and improved for low temperature applications, for small temperature coefficients, for different shapes of hysteresis loops, or for high wear resistance - and moreover forms, components, and basic designs of chokes for RFI suppression, of transformers for electronic power supplies, of transformers for ground-fault interrupters, and for magnetic shielding equipments. (orig.) 891 GSC/orig. 892 AV [de

  5. Internal transfers of special nuclear material - March 1975

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Paragraph 70.51(e) of 10 CFR Part 70 requires, with certain exceptions stated in the rule, that each licensee authorized to possess more than one effective kilogram of special nuclear material (SNM) maintain certain procedures. These procedures are to include: (1) records of the quantities of SNM added to or removed from the process; (2) documentation of all transfers of SNM between material-balance areas to show the identity and quantity of SNM transferred; (3) requirements for authorized signatures on each document used to record the transfer of SNM between material-balance areas; and (4) means for control of and accounting for internal transfer documents. Paragraph 70.58(e) requires licensees to establish, maintain, and follow a system for measuring the SNM transferred between material-balance areas and item-control areas. Paragraph 70.58(f) requires that licensees have a program that evaluates and controls the quality of their measurement system. Additionally, all licensees authorized to possess SNM must comply with paragraph 70.51(b) of 10 CFR Part 70. That rule requires licensees to keep records showing, among other things, the inventory of all SNM in their possession and its location. This guide sets forth acceptable methods for controlling and documenting transfers of SNM within a plant site in order to meet the requirements listed above

  6. Neutron interrogation system using high gamma ray signature to detect contraband special nuclear materials in cargo

    Science.gov (United States)

    Slaughter, Dennis R [Oakland, CA; Pohl, Bertram A [Berkeley, CA; Dougan, Arden D [San Ramon, CA; Bernstein, Adam [Palo Alto, CA; Prussin, Stanley G [Kensington, CA; Norman, Eric B [Oakland, CA

    2008-04-15

    A system for inspecting cargo for the presence of special nuclear material. The cargo is irradiated with neutrons. The neutrons produce fission products in the special nuclear material which generate gamma rays. The gamma rays are detecting indicating the presence of the special nuclear material.

  7. Detection of special nuclear materials with the associate particle technique

    International Nuclear Information System (INIS)

    Carasco, Cédric; Deyglun, Clément; Pérot, Bertrand; Eléon, Cyrille; Normand, Stéphane; Sannié, Guillaume; Boudergui, Karim; Corre, Gwenolé; Konzdrasovs, Vladimir; Pras, Philippe

    2013-01-01

    In the frame of the French trans-governmental R and D program against chemical, biological, radiological, nuclear and explosives (CBRN-E) threats, CEA is studying the detection of Special Nuclear Materials (SNM) by neutron interrogation with fast neutrons produced by an associated particle sealed tube neutron generator. The deuterium-tritium fusion reaction produces an alpha particle and a 14 MeV neutron almost back to back, allowing tagging neutron emission both in time and direction with an alpha particle position-sensitive sensor embedded in the generator. Fission prompt neutrons and gamma rays induced by tagged neutrons which are tagged by an alpha particle are detected in coincidence with plastic scintillators. This paper presents numerical simulations performed with the MCNP-PoliMi Monte Carlo computer code and with post processing software developed with the ROOT data analysis package. False coincidences due to neutron and photon scattering between adjacent detectors (cross talk) are filtered out to increase the selectivity between nuclear and benign materials. Accidental coincidences, which are not correlated to an alpha particle, are also taken into account in the numerical model, as well as counting statistics, and the time-energy resolution of the data acquisition system. Such realistic calculations show that relevant quantities of SNM (few kg) can be distinguished from cargo and shielding materials in 10 min acquisitions. First laboratory tests of the system under development in CEA laboratories are also presented.

  8. Special nuclear material radiation monitors for the 1980's

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1985-01-01

    During the two decades that automatic gamma-radiation monitors have been applied to detecting special nuclear material (SNM), little attention has been devoted to how well the monitors perform in plant environments. Visits to 11 DOE facilities revealed poor information flow between developers, manufacturers, and maintainers of SNM radiation monitors. To help users achieve best performance from their monitors or select new ones, Los Alamos National Laboratory developed a hand-held monitor user's guide, calibration manuals for some commercial SNM pedestrian monitors, and an application guide for SNM pedestrian monitors. In addition, Los Alamos evaluated new commercial SNM monitors, considered whether to apply neutron detection to SNM monitoring, and investigated the problem of operating gamma-ray SNM monitors in variable plutonium gamma-radiation fields. As a result, the performance of existing SNM monitors will improve and alternative monitoring methods will become commerciallly available during the 1980s. 9 refs., 6 figs., 1 tab

  9. Special cluster issue on tribocorrosion of dental materials

    Science.gov (United States)

    Mathew, Mathew T.; Stack, Margaret M.

    2013-10-01

    Tribocorrosion affects all walks of life from oil and gas conversion to biomedical materials. Wear can interact with corrosion to enhance it or impede it; conversely, corrosion can enhance or impede wear. The understanding of the interactions between physical and chemical phenomena has been greatly assisted by electrochemical and microscopic techniques. In dentistry, it is well recognized that erosion due to dissolution (a term physicists use to denote wear) of enamel can result in tooth decay; however, the effects of the oral environment, i.e. pH levels, electrochemical potential and any interactions due to the forces involved in chewing are not well understood. This special cluster issue includes investigations on the fundamentals of wear-corrosion interactions involved in simulated oral environments, including candidate dental implant and veneer materials. The issue commences with a fundamental study of titanium implants and this is followed by an analysis of the behaviour of commonly used temporomandibular devices in a synovial fluid-like environment. The analysis of tribocorrosion mechanisms of Ti6Al4V biomedical alloys in artificial saliva with different pHs is addressed and is followed by a paper on fretting wear, on hydroxyapatite-titanium composites in simulated body fluid, supplemented with protein (bovine serum albumin). The effects of acid treatments on tooth enamel, and as a surface engineering technique for dental implants, are investigated in two further contributions. An analysis of the physiological parameters of intraoral wear is addressed; this is followed by a study of candidate dental materials in common beverages such as tea and coffee with varying acidity and viscosity and the use of wear maps to identify the safety zones for prediction of material degradation in such conditions. Hence, the special cluster issue consists of a range of tribocorrosion contributions involving many aspects of dental tribocorrosion, from analysis of physiological

  10. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    Mike Murphy

    2008-01-01

    In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

  11. Selected topics in special nuclear materials safeguard system design

    International Nuclear Information System (INIS)

    King, L.L.; Thatcher, C.D.; Clarke, J.D.; Rodriguez, M.P.

    1991-01-01

    During the past two decades the improvements in circuit integration have given rise to many new applications in digital processing technology by continuously reducing the unit cost of processing power. Along with this increase in processing power a corresponding decrease in circuit volume has been achieved. Progress has been so swift that new classes of applications become feasible every 2 or 3 years. This is especially true in the application of proven new technology to special nuclear materials (SNM) safeguard systems. Several areas of application were investigated in establishing the performance requirements for the SNM safeguard system. These included the improvements in material control and accountability and surveillance by using multiple sensors to continuously monitor SNM inventory within the selected value(s); establishing a system architecture to provide capabilities needed for present and future performance requirements; and limiting operating manpower exposure to radiation. This paper describes two selected topics in the application of state-of-the-art, well-proven technology to SNM safeguard system design

  12. Molecular Environmental Science Using Synchrotron Radiation: Chemistry and Physics of Waste Form Materials. Final Report

    International Nuclear Information System (INIS)

    Lindle, Dennis W.

    2011-01-01

    Production of defense-related nuclear materials has generated large volumes of complex chemical wastes containing a mixture of radionuclides. The disposition of these wastes requires conversion of the liquid and solid-phase components into durable, solid forms suitable for long-term immobilization. Specially formulated glass compositions and ceramics such as pyrochlores and apatites are the main candidates for these wastes. An important consideration linked to the durability of waste-form materials is the local structure around the waste components. Equally important is the local structure of constituents of the glass and ceramic host matrix. Knowledge of the structure in the waste-form host matrices is essential, prior to and subsequent to waste incorporation, to evaluate and develop improved waste-form compositions based on scientific considerations. This project used the soft-x-ray synchrotron-radiation-based technique of near-edge x-ray-absorption fine structure (NEXAFS) as a unique method for investigating oxidation states and structures of low-Z elemental constituents forming the backbones of glass and ceramic host matrices for waste-form materials. In addition, light metal ions in ceramic hosts, such as titanium, are also ideal for investigation by NEXAFS in the soft-x-ray region. Thus, one of the main objectives was to understand outstanding issues in waste-form science via NEXAFS investigations and to translate this understanding into better waste-form materials, followed by eventual capability to investigate 'real' waste-form materials by the same methodology. We conducted several detailed structural investigations of both pyrochlore ceramic and borosilicate-glass materials during the project and developed improved capabilities at Beamline 6.3.1 of the Advanced Light Source (ALS) to perform the studies.

  13. Molecular Environmental Science Using Synchrotron Radiation: Chemistry and Physics of Waste Form Materials

    Energy Technology Data Exchange (ETDEWEB)

    Lindle, Dennis W.

    2011-04-21

    Production of defense-related nuclear materials has generated large volumes of complex chemical wastes containing a mixture of radionuclides. The disposition of these wastes requires conversion of the liquid and solid-phase components into durable, solid forms suitable for long-term immobilization. Specially formulated glass compositions and ceramics such as pyrochlores and apatites are the main candidates for these wastes. An important consideration linked to the durability of waste-form materials is the local structure around the waste components. Equally important is the local structure of constituents of the glass and ceramic host matrix. Knowledge of the structure in the waste-form host matrices is essential, prior to and subsequent to waste incorporation, to evaluate and develop improved waste-form compositions based on scientific considerations. This project used the soft-x-ray synchrotron-radiation-based technique of near-edge x-ray-absorption fine structure (NEXAFS) as a unique method for investigating oxidation states and structures of low-Z elemental constituents forming the backbones of glass and ceramic host matrices for waste-form materials. In addition, light metal ions in ceramic hosts, such as titanium, are also ideal for investigation by NEXAFS in the soft-x-ray region. Thus, one of the main objectives was to understand outstanding issues in waste-form science via NEXAFS investigations and to translate this understanding into better waste-form materials, followed by eventual capability to investigate “real” waste-form materials by the same methodology. We conducted several detailed structural investigations of both pyrochlore ceramic and borosilicate-glass materials during the project and developed improved capabilities at Beamline 6.3.1 of the Advanced Light Source (ALS) to perform the studies.

  14. 77 FR 36607 - Office of Hazardous Materials Safety Notice of Applications for Modification of Special Permit

    Science.gov (United States)

    2012-06-19

    ... modification of special permits (e.g. to provide for additional hazardous materials, packaging design changes... hazardous materials. 12102-M EQ Industrial 49 CFR 173.56(i); To modify the special Services, Inc. 173.56(b... 4.1. 13102-M Robertshaw Industrial 49 CFR 173.150(b); To modify the special Products dba 173.222(c...

  15. The specification and testing of radioactive sources designated as ''special form'' under the IAEA transport regulations

    International Nuclear Information System (INIS)

    Aston, D.; Bodimeade, A.H.; Hall, E.G.; Taylor, C.B.G.

    1982-01-01

    The object of this study is to remove some of the uncertainties associated with the application of the IAEA Regulations insofar as they apply to Special Form materials. The first part of this project involved a comparison of the ISO and IAEA Regulations. An analysis of the physical tests has been carried out. The second and most important part of the project involved an assessment of the leakage tests used to evaluate the capsules after each of the physical tests. The work has defined and confirmed by experiment the relationship between the IAEA and ISO impact and percussion tests. The practical application of the tests particularly with regard to specimen orientation will be aided by the data now available. The work has established the sensitivities of the primary volumetric leak test methods and practical procedures are outlined. Volumetric leak test methods, with sentivities approximately 10 - 5 mbar l/s, are considered to be more reliable in detecting leakage paths in capsules than methods using solid leachable or non-leachable radioactive contents. The work reported should assist in the updating and clarification and harmonisation of IAEA Safety Series Nos 6 and 37 and ISO 4919 and ISO TR 4826

  16. Biocidal Energetic Materials for the Destruction of Spore Forming Bacteria

    Science.gov (United States)

    2015-07-01

    agent (GA). During a reaction the GA generates nucleation sites that promote the formation of bubbles. As the reaction wave passes, the gas pockets...studies have shown iodine producing reactive materials are effective against spore forming bacteria, but are sensitive to the relative humidity in the...testing environment. Results from tests run in relative high humidity environments show a decreased ability of iodine to effectively neutralize

  17. Material forming apparatus using a directed droplet stream

    Science.gov (United States)

    Holcomb, David E.; Viswanathan, Srinath; Blue, Craig A.; Wilgen, John B.

    2000-01-01

    Systems and methods are described for rapidly forming precision metallic and intermetallic alloy net shape parts directly from liquid metal droplets. A directed droplet deposition apparatus includes a crucible with an orifice for producing a jet of material, a jet destabilizer, a charging structure, a deflector system, and an impact zone. The systems and methods provide advantages in that fully dense, microstructurally controlled parts can be fabricated at moderate cost.

  18. Technical criteria for terminating or reducing domestic safeguards on low-grade special nuclear material

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1996-01-01

    A graded table for terminating or reducing domestic safeguards has been developed for use by programs and facilities within the Department of Energy in decisions regarding the need for or levels of protection of low-grade nuclear materials. Contained in this table are technical criteria which can allow for complete removal of safeguards over many special nuclear material forms and concentrations of typical low-grade materials either currently located at generating or processing sites and materials which may arise from processing operations related to stabilization and disposition activities. In addition, these criteria include higher concentration levels which may warrant maintaining some level of (albeit reduced) security on low-grade materials while allowing reductions in materials control and accountability requirements. These reductions can range from complete removal of these materials from materials control and accountability requirements such as measurements, physical inventories and recordkeeping, to deferring these measurements and physical inventories until a time that either the material is removed from the site or resubmitted for processing. It is important to note that other conditions contained in current Departmental safeguards and security policy be met prior to safeguards termination or reduction

  19. Nuclear reactor structural material forming less radioactive corrosion product

    International Nuclear Information System (INIS)

    Nakazawa, Hiroshi.

    1988-01-01

    Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

  20. Estimation methods for process holdup of special nuclear materials

    International Nuclear Information System (INIS)

    Pillay, K.K.S.; Picard, R.R.; Marshall, R.S.

    1984-06-01

    The US Nuclear Regulatory Commission sponsored a research study at the Los Alamos National Laboratory to explore the possibilities of developing statistical estimation methods for materials holdup at highly enriched uranium (HEU)-processing facilities. Attempts at using historical holdup data from processing facilities and selected holdup measurements at two operating facilities confirmed the need for high-quality data and reasonable control over process parameters in developing statistical models for holdup estimations. A major effort was therefore directed at conducting large-scale experiments to demonstrate the value of statistical estimation models from experimentally measured data of good quality. Using data from these experiments, we developed statistical models to estimate residual inventories of uranium in large process equipment and facilities. Some of the important findings of this investigation are the following: prediction models for the residual holdup of special nuclear material (SNM) can be developed from good-quality historical data on holdup; holdup data from several of the equipment used at HEU-processing facilities, such as air filters, ductwork, calciners, dissolvers, pumps, pipes, and pipe fittings, readily lend themselves to statistical modeling of holdup; holdup profiles of process equipment such as glove boxes, precipitators, and rotary drum filters can change with time; therefore, good estimation of residual inventories in these types of equipment requires several measurements at the time of inventory; although measurement of residual holdup of SNM in large facilities is a challenging task, reasonable estimates of the hidden inventories of holdup to meet the regulatory requirements can be accomplished through a combination of good measurements and the use of statistical models. 44 references, 62 figures, 43 tables

  1. Phosphate bonded ceramics as candidate final-waste-form materials

    International Nuclear Information System (INIS)

    Singh, D.; Wagh, A.S.; Cunnane, J.; Sutaria, M.; Kurokawa, S.; Mayberry, J.

    1994-04-01

    Room-temperature setting phosphate-bonded ceramics were studied as candidate materials for stabilization of DOE low-level problem mixed wastes which cannot be treated by other established stabilization techniques. Phosphates of Mg, Mg-Na, Al and Zr were studied to stabilize ash surrogate waste containing RCRA metals as nitrates and RCRA organics. We show that for a typical loading of 35 wt.% of the ash waste, the phosphate ceramics pass the TCLP test. The waste forms have high compression strength exceeding ASTM recommendations for final waste forms. Detailed X-ray diffraction studies and differential thermal analyses of the waste forms show evidence of chemical reaction of the waste with phosphoric acid and the host matrix. The SEM studies show evidence of physical bonding. The excellent performance in the leaching tests is attributed to a chemical solidification and physical as well as chemical bonding of ash wastes in these phosphate ceramics

  2. 13 CFR 108.160 - Special rules for NMVC Companies formed as limited partnerships.

    Science.gov (United States)

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Special rules for NMVC Companies formed as limited partnerships. 108.160 Section 108.160 Business Credit and Assistance SMALL BUSINESS... of a limited partner pending SBA's written approval of such transfer or succession; and (4) You must...

  3. Convergence criterion for branched contіnued fractions of the special form with positive elements

    Directory of Open Access Journals (Sweden)

    D. I. Bodnar

    2017-07-01

    Full Text Available In this paper the problem of convergence of the important type of a multidimensional generalization of continued fractions, the branched continued fractions with independent variables, is considered. This fractions are an efficient apparatus for the approximation of multivariable functions, which are represented by multiple power series. When variables are fixed these fractions are called the branched continued fractions of the special form. Their structure is much simpler then the structure of general branched continued fractions. It has given a possibility to establish the necessary and sufficient conditions of convergence of branched continued fractions of the special form with the positive elements. The received result is the multidimensional analog of Seidel's criterion for the continued fractions. The condition of convergence of investigated fractions is the divergence of series, whose elements are continued fractions. Therefore, the sufficient condition of the convergence of this fraction which has been formulated by the divergence of series composed of partial denominators of this fraction, is established. Using the established criterion and Stieltjes-Vitali Theorem the parabolic theorems of branched continued fractions of the special form with complex elements convergence, is investigated. The sufficient conditions gave a possibility to make the condition of convergence of the branched continued fractions of the special form, whose elements lie in parabolic domains.

  4. 15 CFR Appendix I to Part 700 - Form BIS-999-Request for Special Priorities Assistance

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Form BIS-999-Request for Special Priorities Assistance I Appendix I to Part 700 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) BUREAU OF INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE NATIONAL...

  5. Safety regulation for the design approval of special form radioactive sources

    International Nuclear Information System (INIS)

    Cho, Woon-Kap

    2009-01-01

    Several kinds of special form radioactive sources for industrial, medical applications are being produced in Korea. Special form radioactive sources should meet strict safety requirements specified in the domestic safety regulations and the design of the sources should be certified by the regulatory authority, the Ministry of Education, Science and Technology (MEST). Several safety tests such as impact, percussion, heating, and leak tests are performed on the sources according to the domestic regulations and the international safety standards such as ANSI N542-1977 and ISO 2919-1999(E). As a regulatory expert body, Korea Institute of Nuclear Safety (KINS) assesses various types of application documents, such as safety analysis report, quality assurance program, and other documents evidencing fulfillment of requirements for design approval of the special form radioactive sources, submitted by a legal person who intends to produce special form radioactive sources and then reports the assessment result to MEST. A design approval certificate is issued to the applicant by MEST on the basis of a technical evaluation report presented by KINS.

  6. Superheated emulsions for the detection of special nuclear material

    International Nuclear Information System (INIS)

    D’Errico, Francesco; Di Fulvio, Angela

    2011-01-01

    A novel solution for the detection and smuggling interdiction of special nuclear materials is presented here consisting of large detector modules which contain superheated emulsions and which are readout with an optical approach. The detectors can be produced to be fully sensitive to prompt fission neutrons and totally insensitive to the interrogation beam, whether X-rays or neutrons below a chosen energy threshold. Therefore, the detectors are able to operate while the selected interrogation beam is on and they will only pick up the signal from fission neutrons. A position-sensitive readout mechanism is used in our design, relying on the scattering of light by neutron-induced bubbles. A beam of coherent light crosses the active area of the detector, and local variations in scattered light due to the presence of bubbles are detected in real time by arrays of silicon planar photodiodes affixed along the whole length of the detector. The system may offer a variety of advantages compared to current approaches, such as the possibility of simultaneous irradiation and detection, i.e. a 100% duty cycle, without requiring complex signal analysis, and high signal-to-noise ratio, minimizing costly nuisance alarms, thanks to its inherent insensitivity to photons.

  7. Tamper and radiation resistant instrumentation for safeguarding special nuclear materials

    International Nuclear Information System (INIS)

    Parsons, B.B.; Wells, J.L.

    1977-01-01

    A tamper-resistant liquid level/accountability instrumentation system for safeguards use has been developed and tested. The tests demonstrate the accuracy of liquid level measurement using TDR (Time Domain Reflectometry) techniques and the accuracy of differential pressure and temperature measurements utilizing a custom designed liquid level sensor probe. The calibrated liquid level, differential pressure, and temperature data provide sufficient information to accurately determine volume, density, and specific gravity. Test solutions used include ordinary tap water, diluted nitric acid in varying concentrations, and diluted uranium trioxide also in varying concentrations. System operations and preliminary test results conducted at the General Electric Midwest Fuel Recovery Plant and the National Bureau of Standards, respectively, suggest that the system will provide the safeguards inspector with an additional tool for real-time independent verification of normal operations and special nuclear materials accountancy data for chemical reprocessing plants. This paper discusses the system design concepts, including a brief description of the tamper and radiation resistant features, the preliminary test results, and the significance of the work

  8. Special Nuclear Material Detection with a Water Cherenkov based Detector

    International Nuclear Information System (INIS)

    Sweany, M.; Bernstein, A.; Bowden, N.; Dazeley, S.; Svoboda, R.

    2008-01-01

    Fission events from Special Nuclear Material (SNM), such as highly enriched uranium or plutonium, produce a number of neutrons and high energy gamma-rays. Assuming the neutron multiplicity is approximately Poissonian with an average of 2 to 3, the observation of time correlations between these particles from a cargo container would constitute a robust signature of the presence of SNM inside. However, in order to be sensitive to the multiplicity, one would require a high total efficiency. There are two approaches to maximize the total efficiency; maximizing the detector efficiency or maximizing the detector solid angle coverage. The advanced detector group at LLNL is investigating one way to maximize the detector size. We are designing and building a water Cerenkov based gamma and neutron detector for the purpose of developing an efficient and cost effective way to deploy a large solid angle car wash style detector. We report on our progress in constructing a larger detector and also present preliminary results from our prototype detector that indicates detection of neutrons

  9. Tests with ceramic waste form materials made by pressureless consolidation

    International Nuclear Information System (INIS)

    Lewis, M. A.; Hash, M. C.; Hebden, A. S.; Ebert, W. L.

    2002-01-01

    A multiphase waste form referred to as the ceramic waste form (CWF) will be used to immobilize radioactively contaminated salt wastes recovered after the electrometallurgical treatment of spent sodium-bonded nuclear fuel. The CWF is made by first occluding salt in zeolite and then encapsulating the zeolite in a borosilicate binder glass. A variety of surrogate CWF materials were made using pressureless consolidation (PC) methods for comparison with CWF consolidated using a hot isostatic press (HIP) method and to study the effects of glass/zeolite batching ratio and processing conditions on the physical and chemical properties of the resulting materials. The data summarized in this report will also be used to support qualification of the PC CWF for disposal in the proposed federal high-level radioactive waste repository at Yucca Mountain. The phase composition and microstructure of HIP CWF and PC CWF are essentially identical: both are composed of about 70% sodalite, 25% binder glass, and a 5% total of inclusion phases (halite, nepheline, and various oxides and silicates). The primary difference is that PC CWF materials have higher porosities than HIP CWFs. The product consistency test (PCT) that was initially developed to monitor homogeneous glass waste forms was used to measure the chemical durabilities of the CWF materials. Series of replicate tests with several PC CWF materials indicate that the PCT can be conducted with the same precision with CWF materials as with borosilicate glasses. Short-term (7-day) PCTs were used to evaluate the repeatability of making the PC CWF and the effects of the glass/zeolite mass ratio, process temperature, and processing time on the chemical durability. Long-term (up to 1 year) PCTs were used to compare the durabilities of HIP and PC CWFs and to estimate the apparent solubility limit for the PC CWF that is needed for modeling. The PC and HIP CWF materials had similar disabilities, based on the release of silicon in long

  10. Strategic special nuclear material Inventory Differences. Semiannual report, April 1-September 30, 1984

    International Nuclear Information System (INIS)

    1985-07-01

    This sixteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1984 (April 1, 1984, through September 30, 1984), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material (SSNM). Inventory Differences are simply the differences between the amount of material shown in the accounting records and the amount of material reported in the physical inventory. These differences are generally due to errors in estimating material in unmeasurable form at the time of an inventory, unmeasurable holdup in equipment, measurement imprecisions, inaccuracies in initial determinations of SSNM produced or used in nuclear reactors, and inventory or bookkeeping errors. Both DOE and contractors operating DOE facilities carefully maintain, analyze, and investigate ID data. Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

  11. Method of forming a continuous polymeric skin on a cellular foam material

    Science.gov (United States)

    Duchane, David V.; Barthell, Barry L.

    1985-01-01

    Hydrophobic cellular material is coated with a thin hydrophilic polymer skin which stretches tightly over the outer surface of the foam but which does not fill the cells of the foam, thus resulting in a polymer-coated foam structure having a smoothness which was not possible in the prior art. In particular, when the hydrophobic cellular material is a specially chosen hydrophobic polymer foam and is formed into arbitrarily chosen shapes prior to the coating with hydrophilic polymer, inertial confinement fusion (ICF) targets of arbitrary shapes can be produced by subsequently coating the shapes with metal or with any other suitable material. New articles of manufacture are produced, including improved ICF targets, improved integrated circuits, and improved solar reflectors and solar collectors. In the coating method, the cell size of the hydrophobic cellular material, the viscosity of the polymer solution used to coat, and the surface tensin of the polymer solution used to coat are all very important to the coating.

  12. Porous silicon based anode material formed using metal reduction

    Science.gov (United States)

    Anguchamy, Yogesh Kumar; Masarapu, Charan; Deng, Haixia; Han, Yongbong; Venkatachalam, Subramanian; Kumar, Sujeet; Lopez, Herman A.

    2015-09-22

    A porous silicon based material comprising porous crystalline elemental silicon formed by reducing silicon dioxide with a reducing metal in a heating process followed by acid etching is used to construct negative electrode used in lithium ion batteries. Gradual temperature heating ramp(s) with optional temperature steps can be used to perform the heating process. The porous silicon formed has a high surface area from about 10 m.sup.2/g to about 200 m.sup.2/g and is substantially free of carbon. The negative electrode formed can have a discharge specific capacity of at least 1800 mAh/g at rate of C/3 discharged from 1.5V to 0.005V against lithium with in some embodiments loading levels ranging from about 1.4 mg/cm.sup.2 to about 3.5 mg/cm.sup.2. In some embodiments, the porous silicon can be coated with a carbon coating or blended with carbon nanofibers or other conductive carbon material.

  13. Policy statement--emergency information forms and emergency preparedness for children with special health care needs.

    Science.gov (United States)

    2010-04-01

    Children with chronic medical conditions rely on complex management plans for problems that cause them to be at increased risk for suboptimal outcomes in emergency situations. The emergency information form (EIF) is a medical summary that describes medical condition(s), medications, and special health care needs to inform health care providers of a child's special health conditions and needs so that optimal emergency medical care can be provided. This statement describes updates to EIFs, including computerization of the EIF, expanding the potential benefits of the EIF, quality-improvement programs using the EIF, the EIF as a central repository, and facilitating emergency preparedness in disaster management and drills by using the EIF.

  14. Design of special purpose products made of nanomodified collagen-containing materials with radio-frequency discharge

    Science.gov (United States)

    Makhotkina, L. Yu; Sharifullin, S. N.

    2016-06-01

    Research results shows that RF-plasma treatment increases the adhesion of the coating film to the leather uppers and resistance to abrasion and repeated bending of uppers, which define the ability of material to preserve its consumer properties and characterize longer safety of special purpose footwear form during its wearing.

  15. Material Recover and Waste Form Development--2016 Accomplishments

    Energy Technology Data Exchange (ETDEWEB)

    Todd, Terry A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Vienna, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Paviet, Patricia [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-12-01

    The Material Recovery and Waste Form Development (MRWFD) Campaign under the U.S. Department of Energy (DOE) Fuel Cycle Technologies (FCT) Program is responsible for developing advanced separation and waste form technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress (April 2010). This MRWFD accomplishments report summarizes the results of the research and development (R&D) efforts performed within MRWFD in Fiscal Year (FY) 2016. Each section of the report contains an overview of the activities, results, technical point of contact, applicable references, and documents produced during the FY. This report briefly outlines campaign management and integration activities but primarily focuses on the many technical accomplishments of FY 2016. The campaign continued to use an engineering-driven, science-based approach to maintain relevance and focus.

  16. Fissile material disposition program final immobilization form assessment and recommendation

    International Nuclear Information System (INIS)

    Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H.

    1997-01-01

    Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy's Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations

  17. Secondary organic material formed by methylglyoxal in aqueous aerosol mimics

    Directory of Open Access Journals (Sweden)

    N. Sareen

    2010-02-01

    Full Text Available We show that methylglyoxal forms light-absorbing secondary organic material in aqueous ammonium sulfate and ammonium nitrate solutions mimicking tropospheric aerosol particles. The kinetics were characterized using UV-Vis spectrophotometry. The results suggest that the bimolecular reaction of methylglyoxal with an ammonium or hydronium ion is the rate-limiting step for the formation of light-absorbing species, with kNH4+II=5×10−6 M−1 min−1 and kH3O+II≤10−3 M−1 min−1. Evidence of aldol condensation products and oligomeric species up to 759 amu was found using chemical ionization mass spectrometry with a volatilization flow tube inlet (Aerosol-CIMS. Tentative identifications of carbon-nitrogen species and a sulfur-containing compound were also made using Aerosol-CIMS. Aqueous solutions of methylglyoxal, with and without inorganic salts, exhibit significant surface tension depression. These observations add to the growing body of evidence that dicarbonyl compounds may form secondary organic material in the aerosol aqueous phase, and that secondary organic aerosol formation via heterogeneous processes may affect seed aerosol properties.

  18. Fourth annual progress report on special-purpose materials for magnetically confined fusion reactors

    International Nuclear Information System (INIS)

    1982-08-01

    The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. The Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits

  19. Forming artificial soils from waste materials for mine site rehabilitation

    Science.gov (United States)

    Yellishetty, Mohan; Wong, Vanessa; Taylor, Michael; Li, Johnson

    2014-05-01

    Surface mining activities often produce large volumes of solid wastes which invariably requires the removal of significant quantities of waste rock (overburden). As mines expand, larger volumes of waste rock need to be moved which also require extensive areas for their safe disposal and containment. The erosion of these dumps may result in landform instability, which in turn may result in exposure of contaminants such as trace metals, elevated sediment delivery in adjacent waterways, and the subsequent degradation of downstream water quality. The management of solid waste materials from industrial operations is also a key component for a sustainable economy. For example, in addition to overburden, coal mines produce large amounts of waste in the form of fly ash while sewage treatment plants require disposal of large amounts of compost. Similarly, paper mills produce large volumes of alkaline rejected wood chip waste which is usually disposed of in landfill. These materials, therefore, presents a challenge in their use, and re-use in the rehabilitation of mine sites and provides a number of opportunities for innovative waste disposal. The combination of solid wastes sourced from mines, which are frequently nutrient poor and acidic, with nutrient-rich composted material produced from sewage treatment and alkaline wood chip waste has the potential to lead to a soil suitable for mine rehabilitation and successful seed germination and plant growth. This paper presents findings from two pilot projects which investigated the potential of artificial soils to support plant growth for mine site rehabilitation. We found that pH increased in all the artificial soil mixtures and were able to support plant establishment. Plant growth was greatest in those soils with the greatest proportion of compost due to the higher nutrient content. These pot trials suggest that the use of different waste streams to form an artificial soil can potentially be used in mine site rehabilitation

  20. Numerical Forming Simulations and Optimisation in Advanced Materials

    International Nuclear Information System (INIS)

    Huetink, J.; Boogaard, A. H. van den; Geijselears, H. J. M.; Meinders, T.

    2007-01-01

    With the introduction of new materials as high strength steels, metastable steels and fibre reinforced composites, the need for advanced physically valid constitutive models arises. In finite deformation problems constitutive relations are commonly formulated in terms the Cauchy stress as a function of the elastic Finger tensor and an objective rate of the Cauchy stress as a function of the rate of deformation tensor. For isotropic materials models this is rather straightforward, but for anisotropic material models, including elastic anisotropy as well as plastic anisotropy, this may lead to confusing formulations. It will be shown that it is more convenient to define the constitutive relations in terms of invariant tensors referred to the deformed metric. Experimental results are presented that show new combinations of strain rate and strain path sensitivity. An adaptive through- thickness integration scheme for plate elements is developed, which improves the accuracy of spring back prediction at minimal costs. A procedure is described to automatically compensate the CAD tool shape numerically to obtain the desired product shape. Forming processes need to be optimized for cost saving and product improvement. Until recently, a trial-and-error process in the factory primarily did this optimization. An optimisation strategy is proposed that assists an engineer to model an optimization problem that suits his needs, including an efficient algorithm for solving the problem

  1. Methods of generalizing and classifying layer structures of a special form

    Energy Technology Data Exchange (ETDEWEB)

    Viktorova, N P

    1981-09-01

    An examination is made of the problem of classifying structures represented by weighted multilayer graphs of special form with connections between the vertices of each layer. The classification of structures of such a form is based on the construction of resolving sets of graphs as a result of generalization of the elements of the training sample of each class and the testing of whether an input object is isomorphic (with allowance for the weights) to the structures of the resolving set or not. 4 references.

  2. Pharmaceutical solvates, hydrates and amorphous forms: A special emphasis on cocrystals.

    Science.gov (United States)

    Healy, Anne Marie; Worku, Zelalem Ayenew; Kumar, Dinesh; Madi, Atif M

    2017-08-01

    Active pharmaceutical ingredients (APIs) may exist in various solid forms, which can lead to differences in the intermolecular interactions, affecting the internal energy and enthalpy, and the degree of disorder, affecting the entropy. Differences in solid forms often lead to differences in thermodynamic parameters and physicochemical properties for example solubility, dissolution rate, stability and mechanical properties of APIs and excipients. Hence, solid forms of APIs play a vital role in drug discovery and development in the context of optimization of bioavailability, filing intellectual property rights and developing suitable manufacturing methods. In this review, the fundamental characteristics and trends observed for pharmaceutical hydrates, solvates and amorphous forms are presented, with special emphasis, due to their relative abundance, on pharmaceutical hydrates with single and two-component (i.e. cocrystal) host molecules. Copyright © 2017 Elsevier B.V. All rights reserved.

  3. Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

    International Nuclear Information System (INIS)

    Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

    2017-01-01

    Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

  4. 75 FR 2163 - Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment...

    Science.gov (United States)

    2010-01-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 72-8; NRC-2010-0011] Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment Application for the Calvert Cliffs... Constellation Energy (Constellation) to amend its Special Nuclear Material License No. SNM-2505, under the...

  5. 10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

    Science.gov (United States)

    2010-01-01

    ... and maintain a measurement system which assures that all quantities in the material accounting records...) In each inventory period, control total material control and accounting measurement uncertainty so... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special...

  6. Development of rare earth regenerator materials in fine wire form

    International Nuclear Information System (INIS)

    Wong, T.; Seuntjens, J.M.

    1997-01-01

    The use of rare earth metals, both in the pure and alloyed state, have been examined for use as regenerators in cryocooler applications and as the working material in active magnetic refrigerators. In both applications there is a requirement for the rare earth material to have a constant and uniform cross section, an average size on the order of 50-200 microns in diameter, and low levels of impurities. Existing powder production methods have drawbacks such as oxygen contamination, non-uniform size, inconsistent cross sections, and low production yields. A novel approach for the production of rare earth metals and alloys in fine wire form has been developed. This is accomplished by assembling a copperjacket and niobium barrier around a RE ingot, extruding the assembly, and reducing it with standard wire drawing practices. Strand anneals are utilized between drawing passes when necessary in order to recrystallize the RE core and restore ductility. The copperjacket is removed by chemical means at final size, leaving the Nb barrier in place as a protective coating. This process has been applied to gadolinium, dysprosium and a GdDy alloy

  7. Material Recovery and Waste Form Development FY 2015 Accomplishments Report

    Energy Technology Data Exchange (ETDEWEB)

    Todd, Terry Allen [Idaho National Lab. (INL), Idaho Falls, ID (United States); Braase, Lori Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-11-01

    The Material Recovery and Waste Form Development (MRWFD) Campaign under the U.S. Department of Energy (DOE) Fuel Cycle Technologies (FCT) Program is responsible for developing advanced separation and waste form technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. The FY 2015 Accomplishments Report provides a highlight of the results of the research and development (R&D) efforts performed within the MRWFD Campaign in FY-14. Each section contains a high-level overview of the activities, results, technical point of contact, applicable references, and documents produced during the fiscal year. This report briefly outlines campaign management and integration activities, but primarily focuses on the many technical accomplishments made during FY-15. The campaign continued to utilize an engineering driven-science-based approach to maintain relevance and focus. There was increased emphasis on development of technologies that support near-term applications that are relevant to the current once-through fuel cycle.

  8. 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

  9. Accounting systems for special nuclear material control. Technical report

    International Nuclear Information System (INIS)

    Korstad, P.A.

    1980-05-01

    Nuclear material accounting systems were examined and compared to financial double-entry accounting systems. Effective nuclear material accounting systems have been designed using the principles of double-entry financial accounting. The modified double-entry systems presently employed are acceptable if they provide adequate control over the recording and summarizing of transactions. Strong internal controls, based on principles of financial accounting, can help protect nuclear materials and produce accurate, reliable accounting data. An electronic data processing system can more accurately maintain large volumes of data and provide management with more current, reliable information

  10. Mechanisms of hydrogen induced delayed cracking in hydride forming materials

    International Nuclear Information System (INIS)

    Dutton, R.; Nuttall, K.; Puls, M.P.; Simpson, L.A.

    1977-01-01

    Mechanisms which have been formulated to describe delayed hydrogen cracking in hydride-forming metals are reviewed and discussed. Particular emphasis is placed on the commercial alloy Zr--2.5% Nb (Cb) which is extensively used in nuclear reactor core components. A quantitative model for hydrogen cracking in this material is presented and compared with available experimental data. The kinetics of crack propagation are controlled by the growth of hydrides at the stressed crack tip by the diffusive ingress of hydrogen into this region. The driving force for the diffusion flux is provided by the local stress gradient which interacts with both hydrogen atoms in solution and hydrogen atoms being dissolved and reprecipitated at the crack tip. The model is developed using concepts of elastoplastic fracture mechanics. Stage I crack growth is controlled by hydrides growing in the elastic stress gradient, while Stage II is controlled by hydride growth in the plastic zone at the crack tip. Recent experimental observations are presented which indicate that the process occurs in an intermittent fashion; hydride clusters accumulate at the crack tip followed by unstable crack advance and subsequent crack arrest in repeated cycles

  11. Mechanisms of hydrogen induced delayed cracking in hydride forming materials

    International Nuclear Information System (INIS)

    Dutton, R.; Nuttall, K.; Puls, M.P.; Simpson, L.A.

    1977-01-01

    Mechanisms which have been formulated to describe delayed hydrogen cracking in hydride-forming metals are reviewed and discussed. Particular emphasis is placed on the commercial alloy Zr-2.5 pct Nb which is extensively used in nuclear reactor core components. A quantitative model for hydrogen cracking in this material is presented and compared with available experimental data. The kinetics of crack propagation are controlled by the growth of hydrides at the stressed crack tip by the diffusive ingress of hydrogen into this region. The driving force for the diffusion flux is provided by the local stress gradient which interacts with both hydrogen atoms in solution and hydrogen atoms being dissolved and reprecipitated at the crack tip. The model is developed using concepts of elastoplastic fracture mechanics. Stage I crack growth is controlled by hydrides growing in the elastic stress gradient, while Stage II is controlled by hydride growth in the plastic zone at the crack tip. Recent experimental observations are presented which indicate that the process occurs in an intermittent fashion; hydride clusters accumulate at the crack tip followed by unstable crack advance and subsequent crack arrest in repeated cycles. 55 refs., 6 figs

  12. Recycled materials in geotechnical applications. Geotechnical special publication No. 79

    Energy Technology Data Exchange (ETDEWEB)

    Vipulanandan, C.; Elton, D.J. [eds.

    1998-07-01

    Recycled materials have the potential for use in a variety of geotechnical and geoenvironmental applications. This proceedings contains 15 papers on field applications and laboratory testing related to recycled materials. Papers cover: geotechnics of industrial by-products; paper mill sludge for landfill cover; mitigation of void development under bridge approach slabs using rubber tire chips; tire shreds as lightweight fill for embankments and retaining walls; performance of a highway embankment and hydraulic barriers constructed using waste foundry sand, and recycled materials; lagoon-stored lime for embankment; construction and demolition debris for base and subbase applications; fly ash for fill, pavement, earth structures and aggregate; compaction of contaminated soils-reuse as a road base material; and database on beneficial reuse of foundry by-products; and more.

  13. Real-Time Characterization of Special Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Walston, Sean [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Candy, Jim [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chambers, Dave [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chandrasekaran, Hema [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Snyderman, Neal [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-04

    When confronting an item that may contain nuclear material, it is urgently necessary to determine its characteristics. Our goal is to provide accurate information with high-con dence as rapidly as possible.

  14. Strategy of radioactive waste management of special materials

    International Nuclear Information System (INIS)

    Bruecher, H.; Merz, E.

    1986-11-01

    Special attention is being paid to the treatment and disposal of the volatile radionuclides tritium, carbon-14, krypton-85, and iodine-129 arising from reprocessing of spent nuclear fuel. This is shown by a large number of investigations on this subject as well as the 1983 recommendation of the German Radiation Protection Commission. In the present study, recent investigations on these four nuclides have been analysed, and it has been tried to draw conclusions for the realisation of the management concept for these radionuclides. (orig.) [de

  15. The choice of nuclear material measurement strategy in bulk-form in material balance area

    International Nuclear Information System (INIS)

    Smirnov, V.M.; Sergeev, S.A.; Kirsanov, V.S.

    1999-01-01

    Concepts have been defined such as Shipment batch, Technological batch, and Accounting batch, it has been found that Shipment and Technological batches should be formed through the arrangement of group of measured Accounting batches. The strategy for nuclear material (NM) measurement based on the Accounting batch is shown to give a possibility to use the advantages for the accounting purposes: ensure safeguards of non-diversion of NM at quantitative (numerical) level, which is a higher grade of safeguards compared to the systems of accounting and control now in force of the US and EURATOM; ensure a guaranteed accuracy and reliability (confidence level) when making up NM balance in Material Balance Area (MBA) and at Federal level, which has been realized only in part in the NM control and accounting systems. Strategy of NM measurement for MBAs counting NM in bulk form has been proposed [ru

  16. Test Report of Special Form Qualification Testing for the ORNL U ZipCan

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, Oscar A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-09-01

    This test report describes the special form testing activities performed on the two ZiPCans. One prototype test unit was subjected to the tests stipulated by 10 CFR 71.75 (d)(1)(i), ISO 2919:1999(E) Class 4 impact test, along with the leak rate test specified in 49 CFR 173.469(a)(4)(i). The other test unit was subjected to a leak rate test as specified in 173.469(a)(4)(i) and a heat test as specified in 49 CFR 173.469 (b)(4). Each test unit was leak tested before and after these respective tests. The leak rate tests performed were helium back-pressure tests and bubble tests, as specified in ANSI N14.5-2014.The measured leak rates were converted to standard condition leak rates as specified in ASTM E 493. The determined standardized leak rates from the test and calculation for both test units met the requirements for special form certification.

  17. Mandatory special or dedicated trains for radioactive materials shipments evidence shows they're not needed

    International Nuclear Information System (INIS)

    Goodman, L.S.; Garrison, R.F.; Harmon, L.H.

    1988-01-01

    The rejection of mandatory special or dedicated trains by all responsible Federal agencies for transportation of radioactive materials in shielded casks has a long history. Working with the railroads and the National Academy of Sciences, the ICC adopted standards for transporting radioactive materials in regular freight trains in the mid 1940's. The standards rested primarily on ensuring the integrity of the radioactive materials packaging. AEC, then NRC and DOT, followed the ICC lead, supplementing the licensing rules for casks with a series of performance or stress tests. At no time did these agencies require special trains or special routing for rail casks. Mandatory special trains have too many disadvantages without any proven safety benefit to be worth their high cost to the shipper. The ICC, in a series of litigated cases, found that given the strength of the casks, mandatory special trains were wasteful transportation and an unreasonable railroad practice

  18. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    Libby, R.A.; Segal, J.E.; Stanbro, W.D.; Davis, C.

    1995-08-01

    This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials.

  19. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

    International Nuclear Information System (INIS)

    Libby, R.A.; Segal, J.E.; Stanbro, W.D.; Davis, C.

    1995-08-01

    This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials

  20. {sup 3}He detector analysis of some special shielding materials

    Energy Technology Data Exchange (ETDEWEB)

    Avdic, S; Pesic, M [Boris Kidric, Institute of Nuclear Sciences, Beograd (Yugoslavia); Marinkovic, P [ETF Belgrade Univ. (Yugoslavia)

    1990-07-01

    The shielding properties of commercial materials of reactor Experiments, Inc. (R/X) were analyzed at the facility which includes bare heavy water experimental reactor RB with external neutron converter ENC, The fast neutron spectrum measurements in energy range from 1 MeV to 10 MeV was performed using ORTEC semiconductor neutron detector with He{sup 3} in diode coincidence arrangement. The neutron spectra have been evaluated from measured pulse-height distribution using numerical code HE3 for computation of detector efficiency in a collimated neutron beam. The neutron dose rates behind ENC with and without sample R/X material were determined using cubic spline interpolation routine for calculating the corresponding flux-dose rate conversion factors. Satisfactory shielding properties of the examined material in a fast neutron field in measurements and calculations are demonstrated. (author)

  1. Introduction to Special Edition (of the Journal of Nuclear Materials Management) on Reducing the Threat from Radioactive Materials

    International Nuclear Information System (INIS)

    Mladineo, Stephen V.

    2007-01-01

    Introductory article for special edition of the JOURNAL OF NUCLEAR MATERIALS MANAGEMENT outlining the Institute of Nuclear Materials Management Nonproliferation and Arms Control Technical Division. In particular the International Nuclear and Radiological Security Standing Committee and its initial focus covering four topical areas--Radiological Threat Reduction, Nuclear Smuggling and Illicit Trafficking, Countering Nuclear Terrorism, and Radiological Terrorism Consequence Management

  2. Vulnerability Analysis Considerations for the Transportation of Special Nuclear Material

    International Nuclear Information System (INIS)

    Nicholson, Lary G.; Purvis, James W.

    1999-01-01

    The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access

  3. Special Issue: 15 Years of SU8 as MEMS Material

    Directory of Open Access Journals (Sweden)

    Arnaud Bertsch

    2015-06-01

    Full Text Available In 1997, the first paper using SU-8 as a material for microfabrication was published [1], demonstrating the interest of this negative photoresist for the near-UV structuration of thick layers and the manufacturing of high aspect-ratio components.[...

  4. Growing a Primary Science Specialism: Assembling People, Places, Materials and Ideas

    Science.gov (United States)

    Lynch, Julianne; Frankel, Nadine; McCarthy, Kerry; Sharp, Lindy

    2015-01-01

    This paper derives from the authors' experiences of the development of a successful science specialism implemented in a large primary school in regional Victoria, Australia, since 2012. We discuss how diverse resources--people, spaces, equipment, materials and ideas--were brought together to support a science specialism that focuses on positioning…

  5. 10 CFR 70.20a - General license to possess special nuclear material for transport.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF... transport. (a) A general license is issued to any person to possess formula quantities of strategic special...

  6. Accurate anisotropic material modelling using only tensile tests for hot and cold forming

    Science.gov (United States)

    Abspoel, M.; Scholting, M. E.; Lansbergen, M.; Neelis, B. M.

    2017-09-01

    Accurate material data for simulations require a lot of effort. Advanced yield loci require many different kinds of tests and a Forming Limit Curve (FLC) needs a large amount of samples. Many people use simple material models to reduce the effort of testing, however some models are either not accurate enough (i.e. Hill’48), or do not describe new types of materials (i.e. Keeler). Advanced yield loci describe the anisotropic materials behaviour accurately, but are not widely adopted because of the specialized tests, and data post-processing is a hurdle for many. To overcome these issues, correlations between the advanced yield locus points (biaxial, plane strain and shear) and mechanical properties have been investigated. This resulted in accurate prediction of the advanced stress points using only Rm, Ag and r-values in three directions from which a Vegter yield locus can be constructed with low effort. FLC’s can be predicted with the equations of Abspoel & Scholting depending on total elongation A80, r-value and thickness. Both predictive methods are initially developed for steel, aluminium and stainless steel (BCC and FCC materials). The validity of the predicted Vegter yield locus is investigated with simulation and measurements on both hot and cold formed parts and compared with Hill’48. An adapted specimen geometry, to ensure a homogeneous temperature distribution in the Gleeble hot tensile test, was used to measure the mechanical properties needed to predict a hot Vegter yield locus. Since for hot material, testing of stress states other than uniaxial is really challenging, the prediction for the yield locus adds a lot of value. For the hot FLC an A80 sample with a homogeneous temperature distribution is needed which is due to size limitations not possible in the Gleeble tensile tester. Heating the sample in an industrial type furnace and tensile testing it in a dedicated device is a good alternative to determine the necessary parameters for the FLC

  7. Special purpose materials: an assessment of needs and the role of these materials in the national program

    International Nuclear Information System (INIS)

    Gold, R.E.; Clinard, F.W. Jr.; Davis, J.W.

    1978-01-01

    The scope of activities of the Task Group on Special Purpose Materials includes those materials requirements not specifically addressed by the other OFE materials task groups. These materials can be organized according to seven broad materials applications or functions which appear to be generic to all magnetically confined fusion reactor concepts. These are breeding materials, coolants, materials for tritium service, graphite and silicon carbide, electrical insulators and ceramics, heat-sink materials, and magnet materials. The present paper describes the importance of each of these areas of materials technology, outlines major problems or areas of uncertainty, and reviews past and current contributions to our state of understanding as it may relate to fusion power applications

  8. The work of art as a manifestation of form: Formalistic materialism in the theory of art

    Directory of Open Access Journals (Sweden)

    Popović Radovan

    2015-01-01

    Full Text Available The basic purpose of this paper is to point out and theoretically illuminate the key moments of transformation and re-constitution of the art theory during the first half of XIX century, taking as its point of departure the role and influence of Organicism as a philosophico-reflexive basis, gnoseological postulate and methodological pattern. Sedlmayr's attempt at foundation of a comparative morphology of architectural styles, taking into account the three constitutive building elements as analytical tools of study of concrete-historical manifestations of style: material structure (building materials, technique and intended usability, is a matter of particular attention of the following analysis. Regarding Viollet-le-Duc, the stress is on the interpretation of his conception of architectural form as the application of logically founded general laws of statics and construction, with a special emphasis on his thesis of logical and purposely-rational correspondence of the outer form and the functional structure of the interior. Finally, an attempt is made at the clarification of the revival of Viollet-le-Duc's explanatory pattern within the dynamic and subjectivistic conceptual transformations of form in Fiedler's, von Hildebrandt's and Focillon's theoretical conceptions.

  9. Special-purpose materials for magnetically confined fusion reactors. Third annual progress report

    International Nuclear Information System (INIS)

    1981-11-01

    The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits

  10. A material model for aluminium sheet forming at elevated temperatures

    NARCIS (Netherlands)

    van den Boogaard, Antonius H.; Werkhoven, R.J.; Bolt, P.J.

    2001-01-01

    In order to accurately simulate the deep drawing or stretching of aluminum sheet at elevated temperatures, a model is required that incorporates the temperature and strain-rate dependency of the material. In this paper two models are compared: a phenomenological material model in which the

  11. Sirenomelia (mermaid syndrome): an infant from parents who used a special form of snuff.

    Science.gov (United States)

    Taghavi, M M; Jafari Naveh, H R; Shariati, M; Morteza Zade, F

    2009-05-01

    We report the first case of a fetus with sirenomelia or mermaid syndrome, whose Afghanian parents were heavy user of a special form of snuff. The case was diagnosed as a mermaid syndrome but some of the features were common to both symmelia dipus and symmelia apus, for example, the single lower extremity had the normal femur, tibia and fibula, but the single foot was rotated medially. The digestive tube ended to a massive closed saclike structure and the anus was absence. The external genital organs were rudiment and the normal testes were undescended. Aorta was divided to branches, such that the external iliac arteries were very small in comparison to the internal iliac arteries. Inferior Vena cava was placed on to the left side of the aorta and unlike the majority of reported mermaid syndrome, the bladder was present. So, the researchers believe that the present case is a rare variant of the mermaid syndrome.

  12. An enhanced search methodology for special nuclear materials

    International Nuclear Information System (INIS)

    Carichner, S.

    1996-06-01

    This report is an overview of the first phase of work done to use data fusion to improve the search process for weaponizable radioactive materials. Various methods were examined to provide a system-level optimization to the problem. Data fusion signal- processing techniques using sensor counts and sensor position information with reasonable computation time showed an initial four- fold improvement in the overall search system performance compared to optimal processing without knowledge of sensor position. With the inclusion of data visualization techniques, a centralized search controller has access to information that improves the main search parameters: range, search time, and search confidence. The improvement is significant enough to justify the next phase of work which includes: adding neutron sensor data, investigating the position location system, and further tests and refinements of the system

  13. Material Recovery and Waste Form Development FY 2014 Accomplishments Report

    Energy Technology Data Exchange (ETDEWEB)

    Braase, Lori [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    Develop advanced nuclear fuel cycle separation and waste management technologies that improve current fuel cycle performance and enable a sustainable fuel cycle, with minimal processing, waste generation, and potential for material diversion.

  14. 78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2013-06-27

    ... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

  15. Microcomputer based shelf system to monitor special nuclear materials in storage

    International Nuclear Information System (INIS)

    Nicholson, N.; Kuckertz, T.H.; Ethridge, C.D.

    1980-01-01

    Diversion of special nuclear material has become a matter of grave concern in recent years. Large quantities of this material are kept in long-term storage and must be inventoried periodically, resulting in a time-consuming activity that exposes personnel to additional radiation. A system that provides continuous surveillance of stored special nuclear materials has been developed. A shelf monitor has been designed using a single component microcomputer to collect data from a Geiger Muller tube that monitors gamma emissions and a scale that monitors the total weight of the special nuclear material and its container. A network of these shelf monitors reports their acquired data to a minicomputer for analysis and storage. Because a large number of these monitors is likely to be needed in most storage facilities, one objective of this program has been to develop a low cost but reliable monitor

  16. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1981-08-01

    This eighth periodic semiannual report of inventory differences covers the second six months of fiscal year 1980 (April 1, 1980, through September 30, 1980), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material. Strategic special nuclear material is plutonium or uranium-233 or uranium-235 in material whose uranium-235 content is 20 percent or greater (known as highly enriched uranium). A significant quantity is either 2 kilograms of plutonium or uranium-233 or 5 kilograms of uranium-235 in highly enriched uranium or the appropriate weighted combination. All Inventory Differences reported here have been analyzed, investigated when necessary, and resolved. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic special nuclear material has occurred

  17. TRU waste form studies with special reference to iron-enriched basalt: 1980. Annual report

    International Nuclear Information System (INIS)

    Flinn, J.E.; Henslee, S.P.; Kelsey, P.V. Jr.

    1981-06-01

    Material studies were performed on iron-enriched basalt (IEB) as a waste form containment medium for transuranic wastes. Specimens from laboratory scale, as well as large scale melts, were used in the evaluation. The studies included melting and casting, slag-refractory interaction, slag fruit assessments, volatility of sodium salts from IEB melts, chemical and structure homogeneity, metallic dissolution tests, physical properties, and devitrification associated with the development of mineral phases. In addition, durability tests, which included leaching and mechanical behavior, were performed

  18. Special quasirandom structures for gadolinia-doped ceria and related materials

    KAUST Repository

    Wang, Hao

    2012-01-01

    Gadolinia doped ceria in its doped or strained form is considered to be an electrolyte for solid oxide fuel cell applications. The simulation of the defect processes in these materials is complicated by the random distribution of the constituent atoms. We propose the use of the special quasirandom structure (SQS) approach as a computationally efficient way to describe the random nature of the local cation environment and the distribution of the oxygen vacancies. We have generated two 96-atom SQS cells describing 9% and 12% gadolinia doped ceria. These SQS cells are transferable and can be used to model related materials such as yttria stabilized zirconia. To demonstrate the applicability of the method we use density functional theory to investigate the influence of the local environment around a Y dopant in Y-codoped gadolinia doped ceria. It is energetically favourable if Y is not close to Gd or an oxygen vacancy. Moreover, Y-O bonds are found to be weaker than Gd-O bonds so that the conductivity of O ions is improved. © 2012 the Owner Societies.

  19. Molecular environmental science using synchrotron radiation: Chemistry and physics of waste form materials

    International Nuclear Information System (INIS)

    Lindle, Dennis W.; Shuh, David K.

    2005-01-01

    Production of defense-related nuclear materials has generated large volumes of complex chemical wastes containing a mixture of radionuclides. The disposition of these wastes requires conversion of the liquid and solid-phase components into durable, solid forms suitable for long-term immobilization [1]. Specially formulated glass compositions, many of which have been derived from glass developed for commercial purposes, and ceramics such as pyrochlores and apatites, will be the main recipients for these wastes. The performance characteristics of waste-form glasses and ceramics are largely determined by the loading capacity for the waste constituents (radioactive and non-radioactive) and the resultant chemical and radiation resistance of the waste-form package to leaching (durability). There are unique opportunities for the use of near-edge soft-x-ray absorption fine structure (NEXAFS) spectroscopy to investigate speciation of low-Z elements forming the backbone of waste-form glasses and ceramics. Although nuclear magnetic resonance (NMR) is the primary technique employed to obtain speciation information from low-Z elements in waste forms, NMR is incompatible with the metallic impurities contained in real waste and is thus limited to studies of idealized model systems. In contrast, NEXAFS can yield element-specific speciation information from glass constituents without sensitivity to paramagnetic species. Development and use of NEXAFS for eventual studies of real waste glasses has significant implications, especially for the low-Z elements comprising glass matrices [5-7]. The NEXAFS measurements were performed at Beamline 6.3.1, an entrance-slitless bend-magnet beamline operating from 200 eV to 2000 eV with a Hettrick-Underwood varied-line-space (VLS) grating monochromator, of the Advanced Light Source (ALS) at LBNL. Complete characterization and optimization of this beamline was conducted to enable high-performance measurements

  20. Molecular environmental science using synchrotron radiation:Chemistry and physics of waste form materials

    Energy Technology Data Exchange (ETDEWEB)

    Lindle, Dennis W.; Shuh, David K.

    2005-02-28

    Production of defense-related nuclear materials has generated large volumes of complex chemical wastes containing a mixture of radionuclides. The disposition of these wastes requires conversion of the liquid and solid-phase components into durable, solid forms suitable for long-term immobilization [1]. Specially formulated glass compositions, many of which have been derived from glass developed for commercial purposes, and ceramics such as pyrochlores and apatites, will be the main recipients for these wastes. The performance characteristics of waste-form glasses and ceramics are largely determined by the loading capacity for the waste constituents (radioactive and non-radioactive) and the resultant chemical and radiation resistance of the waste-form package to leaching (durability). There are unique opportunities for the use of near-edge soft-x-ray absorption fine structure (NEXAFS) spectroscopy to investigate speciation of low-Z elements forming the backbone of waste-form glasses and ceramics. Although nuclear magnetic resonance (NMR) is the primary technique employed to obtain speciation information from low-Z elements in waste forms, NMR is incompatible with the metallic impurities contained in real waste and is thus limited to studies of idealized model systems. In contrast, NEXAFS can yield element-specific speciation information from glass constituents without sensitivity to paramagnetic species. Development and use of NEXAFS for eventual studies of real waste glasses has significant implications, especially for the low-Z elements comprising glass matrices [5-7]. The NEXAFS measurements were performed at Beamline 6.3.1, an entrance-slitless bend-magnet beamline operating from 200 eV to 2000 eV with a Hettrick-Underwood varied-line-space (VLS) grating monochromator, of the Advanced Light Source (ALS) at LBNL. Complete characterization and optimization of this beamline was conducted to enable high-performance measurements.

  1. Smart polymeric materials in forms of fiber and film

    International Nuclear Information System (INIS)

    Sugo, Takanobu

    1998-01-01

    Chemical grafting: graft polymerization is a powerful technology to append novel functionality to base fibers, clothes, felts, films and others, while maintaining their original properties. As shown in Figure 1, while a gardener may use a pair of shears to cut the branch, to cut the molecular branch of a polymeric material, one can utilize the radiation energy. Effective utilization of the radiation energy can proceed to a novel reaction that is impossible for other conventional methods and develop a new material bearing outstanding functions. This technology is named radiation-induced graft polymerization (RIGP). In this article, the present research and development of novel functional polymeric materials by radiation-induced graft polymerization is described. The felt of intertwined fibers has been widely used as a filter to remove particles from air but not toxic gaseous compounds. However, by RIGP, one can transform the felt into a high functional filter that will absorb the toxic gaseous compounds while removing particles simultaneously. As a result, the RIGP technology, which is impossible by conventional technology, has enabled the development of a novel functional material that produce highly pure air. Commercialization of this filter for applications in a semiconductor manufacturing facility and as an air purifier is under process. Moreover, this filter can also be used to produce highly purified water by removing toxic heavy metals. Commercially available polyethylene films are also been transform into conductive separators by RIGP to increase the lifetime of a battery by more than five-fold. (J.P.N)

  2. Magnetic modification of diamagnetic agglomerate forming powder materials

    Czech Academy of Sciences Publication Activity Database

    Šafařík, Ivo; Baldíková, Eva; Pospíšková, K.; Šafaříková, Miroslava

    2016-01-01

    Roč. 29, December (2016), s. 169-171 ISSN 1674-2001 Institutional support: RVO:60077344 Keywords : magnetic modification * magnetic separation * powdered material * magnetic iron oxide * microwave assisted synthesis Subject RIV: BM - Solid Matter Physics ; Magnetism Impact factor: 2.621, year: 2016

  3. Alpha damage in non-reference waste form matrix materials

    International Nuclear Information System (INIS)

    Burnay, S.G.

    1987-05-01

    Although bitumen is the matrix material currently used for European α-bearing intermediate level waste streams, polymer and polymer-modified cement matrices could have advantages over bitumen for such wastes. Two organic matrix systems have been studied - an epoxide resin, and an epoxide modified cement. Alpha irradiations were carried out by incorporating 241 Am at approx. 0.9 Ci/l. Comparisons have been made with unirradiated material and with materials which had been γ-irradiated to the same dose as the α-irradiated samples. Measurements were made of dimensional changes, mechanical properties and the leaching behaviour of 241 Am and 137 Cs. A limited amount of swelling (< 3%) was observed in α-irradiated epoxide resin; none was observed in the epoxide modified cement. Gamma irradiation to 300 kGy has no significant effect on the mechanical properties of either system. However, alpha irradiation to the same dose produced significant changes in flexural strength, an increase for the polymer and a decrease for the polymer-cement. Leaching in these systems was found to be a diffusion-controlled process; alpha irradiation to approx. 250 kGy has little effect on the leaching behaviour of either system. (author)

  4. U.S. N.R.C. special safeguards study on nuclear material control and accounting

    International Nuclear Information System (INIS)

    Smith, G.D.

    1976-01-01

    In Feb. 1975, NRC directed that an effort be made to determine a safeguards program for Pu recycle. This paper summarizes results of individual contractor evaluations of upgrading material control and accounting concepts as applied to strategically important special nuclear material and describes staff interpretations of these results as applied to future high-throughput fuel-cycle facilities. Real-time material control, design for physical inventory, Pu isotopics control and calorimetry, and material control and accounting for highly enriched uranium fuel materials were the concepts studied. 1 table, 15 references

  5. Dual phase magnetic material component and method of forming

    Science.gov (United States)

    Dial, Laura Cerully; DiDomizio, Richard; Johnson, Francis

    2017-04-25

    A magnetic component having intermixed first and second regions, and a method of preparing that magnetic component are disclosed. The first region includes a magnetic phase and the second region includes a non-magnetic phase. The method includes mechanically masking pre-selected sections of a surface portion of the component by using a nitrogen stop-off material and heat-treating the component in a nitrogen-rich atmosphere at a temperature greater than about 900.degree. C. Both the first and second regions are substantially free of carbon, or contain only limited amounts of carbon; and the second region includes greater than about 0.1 weight % of nitrogen.

  6. Odontoblasts: Specialized hard-tissue-forming cells in the dentin-pulp complex.

    Science.gov (United States)

    Kawashima, Nobuyuki; Okiji, Takashi

    2016-07-01

    Odontoblasts are specialized cells that produce dentin and exhibit unique morphological characteristics; i.e., they extend cytoplasmic processes into dentinal tubules. While osteoblasts, which are typical hard-tissue-forming cells, are generated from mesenchymal stem cells during normal and pathological bone metabolism, the induction of odontoblasts only occurs once during tooth development, and odontoblasts survive throughout the lives of healthy teeth. During the differentiation of odontoblasts, signaling molecules from the inner enamel epithelium are considered necessary for the differentiation of odontoblast precursors, i.e., peripheral dental papilla cells. If odontoblasts are destroyed by severe external stimuli, such as deep caries, the differentiation of dental pulp stem cells into odontoblast-like cells is induced. Various bioactive molecules, such as non-collagenous proteins, might be involved in this process, although the precise mechanisms responsible for odontoblast differentiation have not been fully elucidated. Recently, our knowledge about the other functional activities of odontoblasts (apart from dentin formation) has increased. For example, it has been suggested that odontoblasts might act as nociceptive receptors, and surveillance cells that detect the invasion of exogenous pathogens. The regeneration of the dentin-pulp complex has recently gained much attention as a promising future treatment modality that could increase the longevity of pulpless teeth. Finally, congenital dentin anomalies, which are concerned with the disturbance of odontoblast functions, are summarized. © 2016 Japanese Teratology Society.

  7. Microcapsulated rare earth - nickel hydride-forming materials

    International Nuclear Information System (INIS)

    Ishikawa, H.; Oguro, K.; Kato, A.; Suzuki, H.; Ishii, E.

    1985-01-01

    Fine particles of hydride-forming alloys such as LaNi/sub 5/ and MmNi/sub 4.5/Mn/sub 0.5/ (MM : mischmetal) were coated with metallic copper thin layer by chemical plating method. Hydrogen storage capacities of alloys were not appreciably affected by the plating treatment. The capsulated alloy powders were easily pressed into pellets. The pellets obtained had high thermal conductivity and porosity enough to permeate hydrogen, leading to fast reaction kinetics. These were able to withstand more than 5,000 repeated hydriding-dehydriding cycles without disintegrating

  8. Method of forming capsules containing a precise amount of material

    Science.gov (United States)

    Grossman, M.W.; George, W.A.; Maya, J.

    1986-06-24

    A method of forming a sealed capsule containing a submilligram quantity of mercury or the like, the capsule being constructed from a hollow glass tube, by placing a globule or droplet of the mercury in the tube. The tube is then evacuated and sealed and is subsequently heated so as to vaporize the mercury and fill the tube therewith. The tube is then separated into separate sealed capsules by heating spaced locations along the tube with a coiled heating wire means to cause collapse spaced locations there along and thus enable separation of the tube into said capsules. 7 figs.

  9. A method for assay of special nuclear material in high level liquid waste streams

    International Nuclear Information System (INIS)

    Venkata Subramani, C.R.; Swaminathan, K.; Asuvathraman, R.; Kutty, K.V.G.

    2003-01-01

    The assay of special nuclear material in the high level liquid waste streams assumes importance as this is the first stage in the extraction cycle and considerable losses of plutonium could occur here. This stream contains all the fission products as also the minor actinides and hence normal nuclear techniques cannot be used without prior separation of the special nuclear material. This paper presents the preliminary results carried out using wavelength dispersive x-ray fluorescence as part of the developmental efforts to assay SNM in these streams by instrumental techniques. (author)

  10. Reality of dielectric materials in special environment with radiation and others

    International Nuclear Information System (INIS)

    1993-01-01

    In this report, the results of investigation by the expert committee on the title problem in the Institute of Electrical Engineers of Japan from April, 1989 to March, 1992 are summarized. The objectives were to collect the data on the deterioration of dielectric and insulation materials in the special environment including radiation, to investigate the deterioration mechanism, and to grasp the state of development of the materials which can withstand special environment. The actual conditions of temperature, humidity and radiation in nuclear reactors, nuclear fuel cycle facilities, spaceships, accelerator facilities and nuclear fusion experiment facilities are reported. As the new materials which can withstand special environment, the properties of aromatic engineering plastics such as polyimide, PEEK and others, no-halogen incombustible materials, thermoplastic polyurethane, ethylene propylene rubber, cross-linked polyethylene, ceramics, high temperature superconductors, fiber-reinforced composite materials, silica glass and quartz optical fibers are shown. The factors of material deterioration, the method of forecasting lifetime and the examples are explained. The new methods of measuring material properties such as ion microprobe, positron annihilation, scanning tunnel microscopes, optical detection magnetic resonance and so on are explained. (K.I.)

  11. Machinable glass-ceramics forming as a restorative dental material.

    Science.gov (United States)

    Chaysuwan, Duangrudee; Sirinukunwattana, Krongkarn; Kanchanatawewat, Kanchana; Heness, Greg; Yamashita, Kimihiro

    2011-01-01

    MgO, SiO(2), Al(2)O(3), MgF(2), CaF(2), CaCO(3), SrCO(3), and P(2)O(5) were used to prepare glass-ceramics for restorative dental materials. Thermal properties, phases, microstructures and hardness were characterized by DTA, XRD, SEM and Vickers microhardness. Three-point bending strength and fracture toughness were applied by UTM according to ISO 6872: 1997(E). XRD showed that the glass crystallized at 892°C (second crystallization temperature+20°C) for 3 hrs consisted mainly of calcium-mica and fluorapatite crystalline phases. Average hardness (3.70 GPa) closely matched human enamel (3.20 GPa). The higher fracture toughness (2.04 MPa√m) combined with the hardness to give a lower brittleness index (1.81 µm(-1/2)) which indicates that they have exceptional machinability. Bending strength results (176.61 MPa) were analyzed by Weibull analysis to determine modulus value (m=17.80). Machinability of the calcium mica-fluorapatite glass-ceramic was demonstrated by fabricating with CAD/CAM.

  12. Decree 2805 by means of which the National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, is established

    International Nuclear Information System (INIS)

    1979-01-01

    This Decree has for object to establish a National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, under the supervision of the National Council for the Nuclear Industry Development. Its aims are to account nuclear materials, to control nuclear activities, to preserve and control nuclear information, to keep technical relationship with specialized organizations, and to garant nuclear safeguards [es

  13. Report on {open_quotes}audit of internal controls over special nuclear materials{close_quotes}

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The Department of Energy (Department) is responsible for safeguarding a significant amount of plutonium, uranium-233 and enriched uranium - collectively referred to as special nuclear materials - stored in the United States. The Department`s office of Nonproliferation and National Security has overall management cognizance for developing policies for safeguarding these materials, while other Headquarters program offices have {open_quotes}landlord{close_quotes} responsibilities for the sites where the materials are stored, and the Department`s operations and field offices provide onsite management of contractor operations. The Department`s management and operating contractors, under the direction of the Department, safeguard and account for the special nuclear material stored at Department sites.

  14. Special purpose materials for the fusion reactor environment: a technical assessment

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-02-01

    This technology assessment considers the following areas: (1) breeding materials, (2) coolants, (3) tritium barriers, (4) graphite and silicon carbide, (5) ceramics, (6) heat-sink materials, and (7) magnet materials. Some questions and analyses forming the assessment are described. (MOW)

  15. The SNM Scanner: A Non-invasive Protocol for Effective Monitoring of Special Nuclear Material Inventories

    International Nuclear Information System (INIS)

    Lanier, R G; Dauffy, L S; Hodge, A M

    2004-01-01

    We suggest a system of monitoring special nuclear material inventories which uses simple mathematical techniques to compare the gross features of emitted gamma-ray spectra. In this report we develop the techniques necessary to make such spectral comparisons and describe their application. We also apply these ideas and develop inventory confirmation results using a room-temperature CdTe detector in a real nuclear-material inventory environment

  16. Special conditions for the application of coating materials in nuclear power plants

    International Nuclear Information System (INIS)

    Boetius, I.

    1980-01-01

    Proceeding from the special conditions for the application of coating materials in nuclear power plants the following factors influencing the decontamination of surface coatings are discussed from the point of view of radiation protection: abrasion resistance, waterproofness, mechanical and adhesion strength, and permeability. For practical use it is recommended to test the surface tightness of coatings with radiation-exposed specimens

  17. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1983-07-01

    This report covers data for the period from April 1, 1982, through September 30, 1982, and includes accounting corrections for data from earlier periods. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic special nuclear material has occurred

  18. 75 FR 27205 - Hazardous Materials: Incorporation of Special Permits Into Regulations

    Science.gov (United States)

    2010-05-14

    ... specially designed radiation detectors containing a Division 2.2 (non-flammable gas) material under a new.... Radiation Detectors Radiation detectors are used for measuring the intensity of ionizing radiation. The... visual inspection of the rupture disc in a non-reclosing pressure relief device of a rail tank car...

  19. 75 FR 57830 - Office of Hazardous Materials Safety; Notice of Applications for Modification of Special Permit

    Science.gov (United States)

    2010-09-22

    ... permits (e.g. to provide for additional hazardous materials, packaging design changes, additional mode of... special permit Application No. Docket No. Applicant affected thereof 7951-M ConAgra Foods, 49 CFR To... outer packaging when no other means of transportation exist. 14953-M Applied 49 CFR To modify the...

  20. Reference materials for nondestructive assay of special nuclear material. Volume 1. Uranium oxide plus graphite powder

    International Nuclear Information System (INIS)

    Sprinkle, J.K.; Likes, R.N.; Parker, J.L.; Smith, H.A.

    1983-10-01

    This manual describes the fabrication of reference materials for use in gamma-ray-based nondestructive assay of low-density uranium-bearing samples. The sample containers are 2-l bottles. The reference materials consist of small amounts of UO 2 spread throughout a graphite matrix. The 235 U content ranges from 0 to 100 g. The manual also describes the far-field assay procedure used with low-resolution detectors

  1. RETIMAC: a real-time material control concept for strategic special nuclear material

    International Nuclear Information System (INIS)

    Shea, T.E.

    1975-01-01

    As one possible means to upgrade licensee safeguards systems, the NRC is exploring a real-time material control concept. The concept incorporates process controls, material containment provisions, and extensive instrumentation. Plants incorporating this concept would be better able to prevent, deter, and detect diversion, and to assure that diversion has not gone undetected. A substantial methods development, evaluation, and preliminary standards development program is under way to develop the basis for future policy decisions

  2. Einstein in matrix form exact derivation of the theory of special and general relativity without tensors

    CERN Document Server

    Ludyk, Günter

    2013-01-01

    This book is an introduction to the theories of Special and General Relativity. The target audience are physicists, engineers and applied scientists who are looking for an understandable introduction to the topic - without too much new mathematics. The fundamental equations of Einsteins theory of Special and General Relativity are derived using matrix calculus, without the help of tensors. This feature makes the book special and a valuable tool for scientists and engineers with no experience in the field of tensor calculus. In part I the foundations of Special Relativity are developed, part II describes the structure and principle of General Relativity. Part III explains the Schwarzschild solution of spherical body gravity and examines the "Black Hole" phenomenon. Any necessary mathematical tools are user friendly provided, either directly in the text or in the appendices.

  3. Einstein in matrix form. Exact derivation of the theory of special and general relativity without tensors

    Energy Technology Data Exchange (ETDEWEB)

    Ludyk, Guenter [Bremen Univ. (Germany). Physics and Electrical Engineering

    2013-11-01

    Derives the fundamental equations of Einstein's theory of special and general relativity using matrix calculus, without the help of tensors. Provides necessary mathematical tools in a user-friendly way, either directly in the text or in the appendices. Appendices contain an introduction to classical dynamics as a refresher of known fundamental physics. Rehearses vector and matrix calculus, differential geometry, and some special solutions of general relativity in the appendices. This book is an introduction to the theories of Special and General Relativity. The target audience are physicists, engineers and applied scientists who are looking for an understandable introduction to the topic - without too much new mathematics. The fundamental equations of Einsteins theory of Special and General Relativity are derived using matrix calculus, without the help of tensors. This feature makes the book special and a valuable tool for scientists and engineers with no experience in the field of tensor calculus. In part I the foundations of Special Relativity are developed, part II describes the structure and principle of General Relativity. Part III explains the Schwarzschild solution of spherical body gravity and examines the ''Black Hole'' phenomenon. Any necessary mathematical tools are user friendly provided, either directly in the text or in the appendices.

  4. Einstein in matrix form. Exact derivation of the theory of special and general relativity without tensors

    International Nuclear Information System (INIS)

    Ludyk, Guenter

    2013-01-01

    Derives the fundamental equations of Einstein's theory of special and general relativity using matrix calculus, without the help of tensors. Provides necessary mathematical tools in a user-friendly way, either directly in the text or in the appendices. Appendices contain an introduction to classical dynamics as a refresher of known fundamental physics. Rehearses vector and matrix calculus, differential geometry, and some special solutions of general relativity in the appendices. This book is an introduction to the theories of Special and General Relativity. The target audience are physicists, engineers and applied scientists who are looking for an understandable introduction to the topic - without too much new mathematics. The fundamental equations of Einsteins theory of Special and General Relativity are derived using matrix calculus, without the help of tensors. This feature makes the book special and a valuable tool for scientists and engineers with no experience in the field of tensor calculus. In part I the foundations of Special Relativity are developed, part II describes the structure and principle of General Relativity. Part III explains the Schwarzschild solution of spherical body gravity and examines the ''Black Hole'' phenomenon. Any necessary mathematical tools are user friendly provided, either directly in the text or in the appendices.

  5. 41 CFR 102-37.575 - Is there a special form for holding agencies to process donations?

    Science.gov (United States)

    2010-07-01

    ... for holding agencies to process donations? 102-37.575 Section 102-37.575 Public Contracts and Property... PROPERTY 37-DONATION OF SURPLUS PERSONAL PROPERTY Donations to Public Bodies in Lieu of Abandonment/Destruction § 102-37.575 Is there a special form for holding agencies to process donations? There is no...

  6. Internal nasal floor configuration in Homo with special reference to the evolution of Neandertal facial form.

    Science.gov (United States)

    Franciscus, Robert G

    2003-06-01

    The presence of a steeply sloping or depressed nasal floor within the nasal cavity of Neandertals is frequently mentioned as a likely specialization or autapomorphy. The depressed nasal floor has also been seen as contributing to a relatively more capacious nasal cavity in Neandertals, which is tied to cold-climate respiratory adaptation and energetics. These observations have been limited largely to a relatively few intact crania, and the character states associated with this trait have not been as precisely codified or analyzed as those published for Plio-Pleistocene hominins (McCollum et al., 1993, J. Hum. Evol. 24, 87; McCollum, 2000, Am. J. Phys. Anthrop. 112, 275). This study examines the internal nasal floor topography in complete crania and isolated maxillae in European, west Asian, and African fossil Homo (n=158) including 25 Neandertals, and a wide range of recent humans from Europe, the Near East, and Africa (n=522). The configuration of the internal nasal floor relative to the nasal cavity entrance is codified as: 1) level, forming a smooth continuous plane; 2) sloped or mildly stepped; or 3) bilevel with a pronounced vertical depression. The frequency of these nasal floor configurations, and their relationship to both nasal margin cresting patterning and a comprehensive set of nasofacial metrics is examined. Neandertals show a high frequency of the bilevel (depressed) configuration in both adults and subadults (80%), but this configuration is also present in lower frequencies in Middle Pleistocene African, Late Pleistocene non-Neandertal (Skhul, Qafzeh), and European Later Upper Paleolithic samples (15%-50%). The bilevel configuration is also present in lower frequencies (ca. 10%) in all recent human samples, but attains nearly 20% in some sub-Saharan African samples. Across extinct and extant Homo (excluding Neandertals), internal nasal floor configuration is not associated with piriform aperture nasal margin patterning, but the two are strongly

  7. Composite materials and bodies including silicon carbide and titanium diboride and methods of forming same

    Science.gov (United States)

    Lillo, Thomas M.; Chu, Henry S.; Harrison, William M.; Bailey, Derek

    2013-01-22

    Methods of forming composite materials include coating particles of titanium dioxide with a substance including boron (e.g., boron carbide) and a substance including carbon, and reacting the titanium dioxide with the substance including boron and the substance including carbon to form titanium diboride. The methods may be used to form ceramic composite bodies and materials, such as, for example, a ceramic composite body or material including silicon carbide and titanium diboride. Such bodies and materials may be used as armor bodies and armor materials. Such methods may include forming a green body and sintering the green body to a desirable final density. Green bodies formed in accordance with such methods may include particles comprising titanium dioxide and a coating at least partially covering exterior surfaces thereof, the coating comprising a substance including boron (e.g., boron carbide) and a substance including carbon.

  8. 76 FR 51324 - Hazardous Materials: Incorporating Rail Special Permits Into the Hazardous Materials Regulations

    Science.gov (United States)

    2011-08-18

    ... through use of electronic data interchange (EDI). The IVOHMA states ``differences in hazard communication... and on the possible effects EDI may have on distributing hazardous materials shipping paper... consider the use of EDI in other modes of transport in a future rulemaking. Petition No. P-1567 PHMSA...

  9. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1984-07-01

    This fourteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1983 (April 1, 1983 through September 30, 1983), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material (SSNM). Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

  10. Integration Strategy for Free-form Lithium Ion Battery: Material, Design to System level Applications

    KAUST Repository

    Kutbee, Arwa T.

    2017-10-31

    Power supply in any electronic system is a crucial necessity. Especially so in fully compliant personalized advanced healthcare electronic self-powered systems where we envision seamless integration of sensors and actuators with data management components in a single freeform platform to augment the quality of our healthcare, smart living and sustainable future. However, the status-quo energy storage (battery) options require packaging to protect the indwelling toxic materials against harsh physiological environment and vice versa, compromising its mechanical flexibility, conformability and wearability at the highest electrochemical performance. Therefore, clean and safe energy storage solutions for wearable and implantable electronics are needed to replace the commercially used unsafe lithium-ion batteries. This dissertation discusses a highly manufacturable integration strategy for a free-form lithium-ion battery towards a genuine mechanically compliant wearable system. We sequentially start with the optimization process for the preparation of all solid-state material comprising a ‘’Lithium-free’’ lithium-ion microbattery with a focus on thin film texture optimization of the cathode material. State of the art complementary metal oxide semiconductor technology was used for the thin film based battery. Additionally, this thesis reports successful development of a transfer-less scheme for a flexible battery with small footprint and free form factor in a high yield production process. The reliable process for the flexible lithium-ion battery achieves an enhanced energy density by three orders of magnitude compared to the available rigid ones. Interconnection and bonding procedures of the developed batteries are discussed for a reliable back end of line process flexible, stretchable and stackable modules. Special attention is paid to the advanced bonding, handling and packaging strategies of flexible batteries towards system-level applications. Finally, this

  11. Rattling nucleons: New developments in active interrogation of special nuclear material

    International Nuclear Information System (INIS)

    Runkle, Robert C.; Chichester, David L.; Thompson, Scott J.

    2012-01-01

    Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

  12. On-site transportation and handling of uranium-233 special nuclear material: Preliminary hazards and accident analysis. Final

    International Nuclear Information System (INIS)

    Solack, T.; West, D.; Ullman, D.; Coppock, G.; Cox, C.

    1995-01-01

    U-233 Special Nuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 Special Nuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards

  13. Materials interactions test methods to measure radionuclide release from waste forms under repository-relevant conditions

    International Nuclear Information System (INIS)

    Strickert, R.G.; Erikson, R.L.; Shade, J.W.

    1984-10-01

    At the request of the Basalt Waste Isolation Project, the Materials Characterization Center has collected and developed a set of procedures into a waste form compliance test method (MCC-14.4). The purpose of the test is to measure the steady-state concentrations of specified radionuclides in solutions contacting a waste form material. The test method uses a crushed waste form and basalt material suspended in a synthetic basalt groundwater and agitated for up to three months at 150 0 C under anoxic conditions. Elemental and radioisotopic analyses are made on filtered and unfiltered aliquots of the solution. Replicate experiments are performed and simultaneous tests are conducted with an approved test material (ATM) to help ensure precise and reliable data for the actual waste form material. Various features of the test method, equipment, and test conditions are reviewed. Experimental testing using actinide-doped borosilicate glasses are also discussed. 9 references, 2 tables

  14. 10 CFR 73.25 - Performance capabilities for physical protection of strategic special nuclear material in transit.

    Science.gov (United States)

    2010-01-01

    ... strategic special nuclear material in transit. 73.25 Section 73.25 Energy NUCLEAR REGULATORY COMMISSION... Transit § 73.25 Performance capabilities for physical protection of strategic special nuclear material in transit. (a) To meet the general performance objective and requirements of § 73.20 an in-transit physical...

  15. 10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

  16. Survey of special nuclear material vehicle monitors for domestic and international safeguards

    International Nuclear Information System (INIS)

    Fehlau, P.E.; Atwater, H.F.; Caldwell, J.T.; Shunk, E.R.

    1979-01-01

    Special nuclear materials vehicle monitors, including gateside vehicle monitors, hand-held personnel-vehicle monitors, and a new tunnel monitor concept for very large vehicles, are discussed. The results of a comparison of effectiveness of monitors for domestic application are presented. The results of calculations and small scale prototype measurements are given for a tunnel-like neutron monitor for monitoring at the perimeter of an enrichment plant subjected to International Safeguards

  17. Intelligent data-acquisition instrumentation for special nuclear material assay data analysis

    International Nuclear Information System (INIS)

    Ethridge, C.D.

    1980-01-01

    The Detection, Surveillance, Verification, and Recovery Group of the Los Alamos Scientific Laboratory Energy Division/Nuclear Safeguards Programs is now utilizing intelligent data-acquisition instrumentation for assay data analysis of special nuclear material. The data acquisition and analysis are enabled by the incorporation of a number-crunching microprocessor sequenced by a single component microcomputer. Microcomputer firmware establishes the capability for processing the computation of several selected functions and also the ability of instrumentation self-diagnostics

  18. Special Issue: 14th International Symposium on Novel and Nano Materials

    Science.gov (United States)

    Kim, Woo-Byoung; Choa, Yong-Ho; Ahn, Hyo-Jin; Park, Il-Kyu

    2017-09-01

    This Special Issue of Applied Surface Science is intended to provide a collection of peer-reviewed contributions presented at the 14th International Symposium on Novel Nano Materials (ISNNM) held in Budapest, Hungary as one of the most beautiful cities in Europe from July 3 to July 8, 2016. All selected papers underwent the regular peer review process as set by the journal of Applied Surface Science and its publisher (Elsevier).

  19. State-of-the-art review of materials properties of nuclear waste forms

    International Nuclear Information System (INIS)

    Mendel, J.E.; Nelson, R.D.; Turcotte, R.P.; Gray, W.J.; Merz, M.D.; Roberts, F.P.; Weber, W.J.; Westsik, J.H. Jr.; Clark, D.E.

    1981-04-01

    The Materials Characterization Center (MCC) was established at the Pacific Northwest Laboratory to assemble a standardized nuclear waste materials data base for use in research, systems and facility design, safety analyses, and waste management decisions. This centralized data base will be provided through the means of a Nuclear Waste Materials Handbook. The first issue of the Handbook will be published in the fall of 1981 in looseleaf format so that it can be updated as additional information becomes available. To ensure utmost reliability, all materials data appearing in the Handbook will be obtained by standard procedures defined in the Handbook and approved by an independent Materials Review Board (MRB) comprised of materials experts from Department of Energy laboratories and from universities and industry. In the interim before publication of the Handbook there is need for a report summarizing the existing materials data on nuclear waste forms. This review summarizes materials property data for the nuclear waste forms that are being developed for immobilization of high-level radioactive waste. It is intended to be a good representation of the knowledge concerning the properties of HLW forms as of March 1981. The table of contents lists the following topics: introduction which covers waste-form categories, and important waste-form materials properties; physical properties; mechanical properties; chemical durability; vaporization; radiation effects; and thermal phase stability

  20. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D., E-mail: mencarini@ieav.cta.b, E-mail: alexdc@ieav.cta.b [Instituto de Estudos Avancados (IEAv/CTA), Sao Jose dos Campos, SP (Brazil)

    2011-07-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  1. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1979-01-01

    This report provides and explains the generally small differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1977, through March 31, 1978, and includes accounting corrections for data from earlier periods. The data and explanations, together with the absence of physical indications of any theft attempt, support a finding that during this period no theft or diversion of a significant amount of strategic special nuclear material has occurred

  2. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    International Nuclear Information System (INIS)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D.

    2011-01-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  3. Project plan remove special nuclear material from PFP project plutonium finishing plant; TOPICAL

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617,Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  4. Project plan remove special nuclear material from PFP project plutonium finishing plant

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  5. On new classes of solutions of nonlinear partial differential equations in the form of convergent special series

    Science.gov (United States)

    Filimonov, M. Yu.

    2017-12-01

    The method of special series with recursively calculated coefficients is used to solve nonlinear partial differential equations. The recurrence of finding the coefficients of the series is achieved due to a special choice of functions, in powers of which the solution is expanded in a series. We obtain a sequence of linear partial differential equations to find the coefficients of the series constructed. In many cases, one can deal with a sequence of linear ordinary differential equations. We construct classes of solutions in the form of convergent series for a certain class of nonlinear evolution equations. A new class of solutions of generalized Boussinesque equation with an arbitrary function in the form of a convergent series is constructed.

  6. Some new high energy materials and their formulations for specialized applications

    Energy Technology Data Exchange (ETDEWEB)

    Agrawal, Jai Prakash [Directorate of Materials, DRDO HQrs, ' B' Wing, Sena Bhavan, New Delhi - 110 011 (India)

    2005-10-01

    Energetic materials form an integral part of most weapon systems and a large number of new high-energy materials: thermally stable explosives, high-performance explosives, melt-castable explosives, insensitive high explosives and energetic binders have been reported in the literature in recent years. Some explosive formulations based on these new energetic materials are also vaguely reported. This paper examines these materials and their formulations from the point of view of stability, reliability, safety and specific applications. (Abstract Copyright [2005], Wiley Periodicals, Inc.)

  7. Material Considerations for Fused-Filament Fabrication of Solid Dosage Forms

    Directory of Open Access Journals (Sweden)

    Evert Fuenmayor

    2018-04-01

    Full Text Available Material choice is a fundamental consideration when it comes to designing a solid dosage form. The matrix material will ultimately determine the rate of drug release since the physical properties (solubility, viscosity, and more of the material control both fluid ingress and disintegration of the dosage form. The bulk properties (powder flow, concentration, and more of the material should also be considered since these properties will influence the ability of the material to be successfully manufactured. Furthermore, there is a limited number of approved materials for the production of solid dosage forms. The present study details the complications that can arise when adopting pharmaceutical grade polymers for fused-filament fabrication in the production of oral tablets. The paper also presents ways to overcome each issue. Fused-filament fabrication is a hot-melt extrusion-based 3D printing process. The paper describes the problems encountered in fused-filament fabrication with Kollidon® VA64, which is a material that has previously been utilized in direct compression and hot-melt extrusion processes. Formulation and melt-blending strategies were employed to increase the printability of the material. The paper defines for the first time the essential parameter profile required for successful 3D printing and lists several pre-screening tools that should be employed to guide future material formulation for the fused-filament fabrication of solid dosage forms.

  8. The Effects of Plastic Anisotropy in Warm and Hot Forming of Magnesium Sheet Materials

    Science.gov (United States)

    Taleff, Eric M.; Antoniswamy, Aravindha R.; Carpenter, Alexander J.; Yavuz, Emre

    Mg alloy sheet materials often exhibit plastic anisotropy at room temperature as a result of the limited slip systems available in the HCP lattice combined with a commonly strong basal texture. Less well studied is plastic anisotropy developed at the elevated temperatures associated with warm and hot forming. At these elevated temperatures, particularly above 200°C, the activation of additional slip systems significantly increases ductility. However, plastic anisotropy is also induced at elevated temperatures by a strong crystallographic texture, and it can require an accounting in material constitutive models to achieve accurate forming simulations. The type and degree of anisotropy under these conditions depend on both texture and deformation mechanism. The current understanding of plastic anisotropy in Mg AZ31B and ZEK100 sheet materials at elevated temperatures is reviewed in this article. The recent construction of material forming cases is also reviewed with strategies to account for plastic anisotropy in forming simulations.

  9. Analysis of material flow in metal forming processes by using computer simulation and experiment with model material

    International Nuclear Information System (INIS)

    Kim, Heon Young; Kim, Dong Won

    1993-01-01

    The objective of the present study is to analyze material flow in the metal forming processes by using computer simulation and experiment with model material, plasticine. A UBET program is developed to analyze the bulk flow behaviour of various metal forming problems. The elemental strain-hardening effect is considered in an incremental manner and the element system is automatically regenerated at every deforming step in the program. The material flow behaviour in closed-die forging process with rib-web type cavity are analyzed by UBET and elastic-plastic finite element method, and verified by experiments with plasticine. There were good agreements between simulation and experiment. The effect of corner rounding on material flow behavior is investigated in the analysis of backward extrusion with square die. Flat punch indentation process is simulated by UBET, and the results are compared with that of elastic-plastic finite element method. (Author)

  10. Yucca Mountain project canister material corrosion studies as applied to the electrometallurgical treatment metallic waste form

    International Nuclear Information System (INIS)

    Keiser, D.D.

    1996-11-01

    Yucca Mountain, Nevada is currently being evaluated as a potential site for a geologic repository. As part of the repository assessment activities, candidate materials are being tested for possible use as construction materials for waste package containers. A large portion of this testing effort is focused on determining the long range corrosion properties, in a Yucca Mountain environment, for those materials being considered. Along similar lines, Argonne National Laboratory is testing a metallic alloy waste form that also is scheduled for disposal in a geologic repository, like Yucca Mountain. Due to the fact that Argonne's waste form will require performance testing for an environment similar to what Yucca Mountain canister materials will require, this report was constructed to focus on the types of tests that have been conducted on candidate Yucca Mountain canister materials along with some of the results from these tests. Additionally, this report will discuss testing of Argonne's metal waste form in light of the Yucca Mountain activities

  11. INNOVATIVE FORMS SUPPORTING SAFE METHODS OF WORK IN SAFETY ENGINEERING FOR THE DEVELOPMENT OF INTELLIGENT SPECIALIZATIONS

    Directory of Open Access Journals (Sweden)

    Anna GEMBALSKA-KWIECIEŃ

    2016-10-01

    Full Text Available The article discusses innovative forms of participation of employees in the work safety system. It also presents the advantages of these forms of employees’ involvement. The aim of empirical studies was the analysis of their behavior and attitude towards health and safety at work. The issues considered in the article have a significant impact on the improvement of methods of prevention related to work safety and aided the creation of a healthy society.

  12. Introduction to the special issue on the technical status of materials for a fusion reactor

    Science.gov (United States)

    Stork, D.; Zinkle, S. J.

    2017-09-01

    Materials determine in a fundamental way the performance and environmental attractiveness of a fusion reactor: through the size (power fluxes to the divertor, neutron fluxes to the first wall); economics (replacement lifetime of critical in-vessel components, thermodynamic efficiency through operating temperature etc); plasma performance (erosion by plasma fluxes to the divertor surfaces); robustness against off-normal accidents (safety); and the effects of post-operation radioactivity on waste disposal and maintenance. The major philosophies and methodologies used to formulate programmes for the development of fusion materials are outlined, as the basis for other articles in this special issue, which deal with the fundamental understanding of the issues regarding these materials and their technical status and prospects for development.

  13. Evaluating safeguards effectiveness against protracted theft of special nuclear material by insiders

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Sicherman, A.

    1991-01-01

    The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling special nuclear material (SNM) evaluate their effectiveness against protracted theft of SNM. Protracted theft means repeated thefts of small quantities of material to accumulate a goal quantity. In this paper the authors discuss issues regarding the evaluation of safeguards and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the timely detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts

  14. Magnetized strange quark matter in f(R, T) gravity with bilinear and special form of time varying deceleration parameter

    Science.gov (United States)

    Sahoo, P. K.; Sahoo, Parbati; Bishi, Binaya K.; Aygün, Sezgin

    2018-04-01

    In this paper, we have studied homogeneous and anisotropic locally rotationally symmetric (LRS) Bianchi type-I model with magnetized strange quark matter (MSQM) distribution and cosmological constant Λ in f(R, T) gravity where R is the Ricci scalar and T the trace of matter source. The exact solutions of the field equations are obtained under bilinear and special form of time varying deceleration parameter (DP). Firstly, we have considered two specific forms of bilinear DP with a single parameter of the form: q = α(1-t)/1+t and q = -αt/1+t, which leads to the constant or linear nature of the function based on the constant α. Second one is the special form of the DP as q = - 1 + β/1+aβ. From the results obtained here, one can observe that in the early universe magnetic flux has more effects and it reduces gradually in the later stage. For t → ∞, we get p → -Bc and ρ → Bc. The behaviour of strange quark matter along with magnetic epoch gives an idea of accelerated expansion of the universe as per the observations of the type Ia Supernovae.

  15. Computer Simulation of Material Flow in Warm-forming Bimetallic Components

    Science.gov (United States)

    Kong, T. F.; Chan, L. C.; Lee, T. C.

    2007-05-01

    Bimetallic components take advantage of two different metals or alloys so that their applicable performance, weight and cost can be optimized. However, since each material has its own flow properties and mechanical behaviour, heterogeneous material flows will occur during the bimetal forming process. Those controls of process parameters are relatively more complicated than forming single metals. Most previous studies in bimetal forming have focused mainly on cold forming, and less relevant information about the warm forming has been provided. Indeed, changes of temperature and heat transfer between two materials are the significant factors which can highly influence the success of the process. Therefore, this paper presents a study of the material flow in warm-forming bimetallic components using finite-element (FE) simulation in order to determine the suitable process parameters for attaining the complete die filling. A watch-case-like component made of stainless steel (AISI-316L) and aluminium alloy (AL-6063) was used as the example. The warm-forming processes were simulated with the punch speeds V of 40, 80, and 120 mm/s and the initial temperatures of the stainless steel TiSS of 625, 675, 725, 775, 825, 875, 925, 975, and 1025 °C. The results showed that the AL-6063 flowed faster than the AISI-316L and so the incomplete die filling was only found in the AISI-316L region. A higher TiSS was recommended to avoid incomplete die filling. The reduction of V is also suggested because this can save the forming energy and prevent the damage of tooling. Eventually, with the experimental verification, the results from the simulation were in agreement with those of the experiments. On the basis of the results of this study, engineers can gain a better understanding of the material flow in warm-forming bimetallic components, and be able to determine more efficiently the punch speed and initial material temperature for the process.

  16. AN ALTERNATIVE HOST MATRIX BASED ON IRON PHOSPHATE GLASSES FOR THE VITRIFICATION OF SPECIALIZED WASTE FORMS

    International Nuclear Information System (INIS)

    Day, Delbert D.

    2000-01-01

    As mentioned above, the overall goal of this research project was to collect the scientific information essential to develop iron phosphate glass based nuclear wasteforms. The specific objectives of the project were: (1) Investigate the structure of binary iron phosphate glasses and it's dependence on the composition and melting atmosphere: Understand atomic arrangements and nature of the bonding. Establish structure-property relationships. Determine the compositions and melting conditions which optimize the critical properties of the base glass. (2) Understand the structure of iron phosphate wasteforms and it's dependence on the composition and melting atmosphere: Investigate how the waste elements are bonded and coordinated within the glass structure. Establish structure-property relationships for the waste glasses. Determine the compositions and melting atmosphere for which the critical properties of the waste forms would be optimum. (3) Determine the role(s) played by the valence states of iron ions and it's dependence on the composition and melting atmosphere: Understand the different roles of iron(II) and iron(III) ions in determining the critical properties of the base glass and the waste forms. Investigate how the iron valence and its significance depend on the composition and melting atmosphere. (4) Investigate glass forming and crystallization processes of the iron phosphate glasses and their waste forms: Understand the dependence of the glass forming and crystallization characteristics on overall glass composition and valence states of iron ions. Identify the products of devitrification and investigate the critical properties of these crystalline compounds which may adversely affect the chemical and physical properties of the waste forms

  17. Materials Characterization Center meeting on impact testing of waste forms. Summary report

    International Nuclear Information System (INIS)

    Merz, M.D.; Atteridge, D.; Dudder, G.

    1981-10-01

    A meeting was held on March 25-26, 1981 to discuss impact test methods for waste form materials to be used in nuclear waste repositories. The purpose of the meeting was to obtain guidance for the Materials Characterization Center (MCC) in preparing the MCC-10 Impact Test Method to be approved by the Materials Review Board. The meeting focused on two essential aspects of the test method, namely the mechanical process, or impact, used to effect rapid fracture of a waste form and the analysis technique(s) used to characterize particulates generated by the impact

  18. Evaluating safeguards effectiveness against protracted theft of special nuclear material by insiders

    International Nuclear Information System (INIS)

    Al-Ayat, R.; Sicherman, A.

    1991-01-01

    The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling special nuclear material (SNM) evaluate their effectiveness against provided theft of SNMProtracted theft means repeated thefts of small quantities of material to accumulate a goal quanfity. To evaluate the safeguards effectiveness against pro thefts, one must addresses several issues: (1) defining relevant time frames for various threat scenarios and delayed detection safeguards: (2) identifying which safeguards come into play more than once because of repeated adversary actions or because of periodic occurrence during the theft time frame (e.g., daily administrative check on presence of material): (3) considering whether the second and subsequent applications of safeguards are different in effectiveness from the first; (4)synthesizing how physical security, material control, and material accountability safeguards combine to provide protection against protracted theft scenarios. In this paper we discuss these issues and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the ''timely'' detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts

  19. Special waste-form lysimeters-arid: Three-year monitoring report

    International Nuclear Information System (INIS)

    Jones, T.L.; Serne, R.J.; Toste, A.P.

    1988-04-01

    Regulations governing the disposal of commercial low-level waste require all liquid waste to be solidified before burial. Most waste must be solidified into a rigid matrix such as cement or plastic to prevent waste consolidation and site slumping after burial. These solidification processes affect the rate at which radionuclides and other solutes are released into the soil. In 1983, a program was initiated at Pacific Northwest Laboratory to study the release of waste from samples of low-level radioactive waste that had been commercially solidified. The primary method used by this program is to bury sample waste forms in field lysimeters and monitor leachate composition from the release and transport of solutes. The lysimeter facility consists of 10 lysimeters, each containing one sample of solidified waste. Five different waste forms are being tested, allowing duplicate samples of each one to be evaluated. The samples were obtained from operating nuclear power plants and are actual waste forms routinely generated at these facilities. All solidification was accomplished by commercial processes. Sample size is a partially filled 210-L drum. All containers were removed prior to burial leaving the bare waste form in contact with the lysimeter soil. 11 refs., 14 figs., 16 tabs

  20. A Stochastic Imaging Technique for Spatio-Spectral Characterization of Special Nuclear Material

    Science.gov (United States)

    Hamel, Michael C.

    Radiation imaging is advantageous for detecting, locating and characterizing special nuclear material (SNM) in complex environments. A dual-particle imager (DPI) has been designed that is capable of detecting gamma-ray and neutron signatures from shielded SNM. The system combines liquid organic and NaI(Tl) scintillators to form a combined Compton and neutron scatter camera. Effective image reconstruction of detected particles is a crucial component for maximizing the performance of the system; however, a key deficiency exists in the widely used list-mode maximum-likelihood estimation-maximization (MLEM) image reconstruction technique. The steady-state solution produced by this iterative method will have poor quality compared to solutions produced with fewer iterations. A stopping condition is required to achieve a better solution but these conditions fail to achieve maximum image quality. Stochastic origin ensembles (SOE) imaging is a good candidate to address this problem as it uses Markov chain Monte Carlo to reach a stochastic steady-state solution that has image quality comparable to the best MLEM solution. The application of SOE to the DPI is presented in this work. SOE was originally applied in medical imaging applications with no mechanism to isolate spectral information based on location. This capability is critical for non-proliferation applications as complex radiation environments with multiple sources are often encountered. This dissertation extends the SOE algorithm to produce spatially dependent spectra and presents experimental result showing that the technique was effective for isolating a 4.1-kg mass of weapons grade plutonium (WGPu) when other neutron and gamma-ray sources were present. This work also demonstrates the DPI as an effective tool for localizing and characterizing highly enriched uranium (HEU). A series of experiments were performed with the DPI using a deuterium-deuterium (DD) and deuterium-tritium (DT) neutron generator, as well as

  1. A data communications systems for tamper-protected special nuclear materials (SNM) inventory management

    International Nuclear Information System (INIS)

    Hurkamp, A.C.

    1995-01-01

    The Department of Energy (D.O.E.) is responsible for the long term storage and protection of large quantities of Special Nuclear Material (SNM). This material is stored within individual containers located in vaults. Security measures are required to ensure that the SNM remains within the canisters where it is stored and that it is not disturbed in any manner. Conventional security and inventory techniques are manpower intensive and often require exposure to radiation hazards. The Purpose of this D.O.E sponsored project is to develop a cost effective system to monitor Special Nuclear Materials that, when fielded, would result in an extension of manual inventory cycles at a wide variety of SNM storage locations. The system consists of a computer, radio frequency interrogator, and individual miniaturized radio frequency transponders (tags) that are co-located with individual SNM containers. Each tag can perform SNM inventory, tamper alarm, and multiple sensor data transmission to the interrogator under the control of software designed by the user. SNM custodians can customize the system by their choice of packaging, software, and sensors. When implemented in accordance with current department of energy (D.O.E.) Policy on SNM inventory extension, the system has the potential to qualify for maximum extension times thus saving considerable resources through reduction of radiation exposure

  2. A novel method to assay special nuclear materials by measuring prompt neutrons from polarized photofission

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, J.M., E-mail: mueller@tunl.duke.edu [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States); Ahmed, M.W. [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States); Department of Mathematics and Physics, North Carolina Central University, Durham, NC 27707 (United States); Weller, H.R. [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States)

    2014-08-01

    A novel method of measuring the enrichment of special nuclear material is presented. Recent photofission measurements using a linearly polarized γ-ray beam were performed on samples of {sup 232}Th, {sup 233,235,238}U, {sup 237}Np, and {sup 239,240}Pu. Prompt neutron polarization asymmetries, defined to be the difference in the prompt neutron yields parallel and perpendicular to the plane of beam polarization divided by their sum, were measured. It was discovered that the prompt neutron polarization asymmetries differed significantly depending on the sample. Prompt neutrons from photofission of even–even (non-fissile) targets had significant polarization asymmetries (∼0.2 to 0.5), while those from odd-A (generally fissile) targets had polarization asymmetries close to zero. This difference in the polarization asymmetries could be exploited to measure the fissile versus non-fissile content of special nuclear materials, and potentially to detect the presence of fissile material during active interrogation. The proposed technique, its expected performance, and its potential applicability are discussed.

  3. A novel method to assay special nuclear materials by measuring prompt neutrons from polarized photofission

    International Nuclear Information System (INIS)

    Mueller, J.M.; Ahmed, M.W.; Weller, H.R.

    2014-01-01

    A novel method of measuring the enrichment of special nuclear material is presented. Recent photofission measurements using a linearly polarized γ-ray beam were performed on samples of 232 Th, 233,235,238 U, 237 Np, and 239,240 Pu. Prompt neutron polarization asymmetries, defined to be the difference in the prompt neutron yields parallel and perpendicular to the plane of beam polarization divided by their sum, were measured. It was discovered that the prompt neutron polarization asymmetries differed significantly depending on the sample. Prompt neutrons from photofission of even–even (non-fissile) targets had significant polarization asymmetries (∼0.2 to 0.5), while those from odd-A (generally fissile) targets had polarization asymmetries close to zero. This difference in the polarization asymmetries could be exploited to measure the fissile versus non-fissile content of special nuclear materials, and potentially to detect the presence of fissile material during active interrogation. The proposed technique, its expected performance, and its potential applicability are discussed

  4. Acquisition of material properties in production for sheet metal forming processes

    International Nuclear Information System (INIS)

    Heingärtner, Jörg; Hora, Pavel; Neumann, Anja; Hortig, Dirk; Rencki, Yasar

    2013-01-01

    In past work a measurement system for the in-line acquisition of material properties was developed at IVP. This system is based on the non-destructive eddy-current principle. Using this system, a 100% control of material properties of the processed material is possible. The system can be used for ferromagnetic materials like standard steels as well as paramagnetic materials like Aluminum and stainless steel. Used as an in-line measurement system, it can be configured as a stand-alone system to control material properties and sort out inapplicable material or as part of a control system of the forming process. In both cases, the acquired data can be used as input data for numerical simulations, e.g. stochastic simulations based on real world data

  5. Special training for drivers of vehicles carrying radioactive materials in Germany

    International Nuclear Information System (INIS)

    Ridder, K.

    1993-01-01

    In Germany drivers of vehicles carrying radioactive materials have to undergo special training since midyear 1991. Training is organized in a modular system, which means that the driver can customize his dangerous goods training programme by combining several modules. The contents of the training programme, its organization and supervision as well as the means for checking the successful completion of the programme can be seen from the slides. This paper will close with an outlook on the European development, considering the framework set by the regulations of the Economic Commission for Europe (ECE) and the European Community (EC). (J.P.N.)

  6. Computer-based accountability system (Phase I) for special nuclear materials at Argonne-West

    International Nuclear Information System (INIS)

    Ingermanson, R.S.; Proctor, A.E.

    1982-05-01

    An automated accountability system for special nuclear materials (SNM) is under development at Argonne National Laboratory-West. Phase I of the development effort has established the following basic features of the system: a unique file organization allows rapid updating or retrieval of the status of various SNM, based on batch numbers, storage location, serial number, or other attributes. Access to the program is controlled by an interactive user interface that can be easily understood by operators who have had no prior background in electronic data processing. Extensive use of structured programming techniques make the software package easy to understand and to modify for specific applications. All routines are written in FORTRAN

  7. Design and realization on function of pre-forming and continuous winding for HT-7U special winding machine

    International Nuclear Information System (INIS)

    Yu Jie; Gao Daming; Wen Jun; Zhu Wenhua; Cheng Leping; Tao Yuming

    2000-05-01

    The winding machine is one of the critical facilities for R and D of HT-7U construction. The machine mainly consists of five parts, CICC pay-off spool, a four-rollers straightening assembly, a four-roller forming/bending assembly, continuous winding structure and CNC control system with three-axis CNC control. The facility is needed for CICC magnet fabrication of HT-7U. The main requirements of the winding machine are: continuous winding to reduce number of joints inside the coils; pre-forming CICC conductor to avoid winding with tension; suitable for all TF and PF coils within the scope of various coil shape and dimension limit; improving the configuration tolerance, specially flatness of the CICC conductor. The author emphasizes on the design and realization on function of Pre-forming and Continuous Winding for HT-7U special winding machine. The winding machine with high accuracy has just been developed and applied to the construction of HT-7U model coils

  8. An overview of high thermal conductive hot press forming die material development

    Directory of Open Access Journals (Sweden)

    A.R. Zulhishamuddin

    2015-12-01

    Full Text Available Most of the automotive industries are using high strength steel components, which are produced via hot press forming process. This process requires die material with high thermal conductivity that increases cooling rate during simultaneous quenching and forming stage. Due to the benefit of high quenching rate, thermal conductive die materials were produced by adding carbide former elements. This paper presents an overview of the modification of alloying elements in tool steel for high thermal conductivity properties by transition metal elements addition. Different types of manufacturing processes involved in producing high thermal conductive materials were discussed. Methods reported were powder metallurgy hot press, direct metal deposition, selective laser melting, direct metal laser sintering and spray forming. Elements likes manganese, nickel, molybdenum, tungsten and chromium were proven to increase thermal conductivity properties. Thermal conductivity properties resulted from carbide network presence in the steel microstructure. To develop feasible and low cost hot press forming die material, casting of Fe-based alloy with carbide former composition can be an option. Current thermal conductivity properties of hot press forming die material range between 25 and 66 W/m.K. The wide range of thermal conductivity varies the mechanical properties of the resulting components and lifetime of HPF dies.

  9. Thermal performance study of form-stable composite phase change material with polyacrylic

    Science.gov (United States)

    Kee, Shin Yiing; Munusamy, Yamuna; Ong, Kok Seng; Chee, Swee Yong; Sanmuggam, Shimalaa

    2017-04-01

    Phase change material (PCM) is one of the most popular and widely used as thermal energy storage material because it is able to absorb and release a large amount of latent heat during a phase change process over a narrow temperature range. In this work, the form-stable composite PCM was prepared by blending of PMMA and myristic acid in different weight percentage. PMMA was used as a supporting material while myristic acid was used as PCM. Theoretically, PCM can be encapsulated in the support material after blending. However, a small amount of liquid PCMs can leak out from supporting material due to the volume change in phase change process. Therefore, a form-stable composite PCM with polyacrylic coating was studied. Leakage test was carried out to determine the leakage percentage of the form-stable composite PCM. Fourier transform infrared spectroscopy (FTIR) was used to characterize the chemical compatibility of the form-stable PCM composite while differential scanning calorimetry (DSC) was used to study the melting, freezing point and the latent heat of melting and freezing for the form-stable composite PCM.

  10. Glass fiber sensors for detecting special nuclear materials at portal and monitor stations

    International Nuclear Information System (INIS)

    Hull, C.D.; Seymour, R.; Crawford, T.; Bliss, M.; Craig, R.A.

    2001-01-01

    Nuclear Safeguards and Security Systems LLC (NucSafe) participated in the Illicit Trafficking Radiation Assessment Program (ITRAP) recently conducted by the Austrian Research Center, Seibersdorf (ARCS) for IAEA, INTERPOL, and the World Customs Organization (IAEA, in press). This presentation reviews ITRAP test results of NucSafe instrumentation. NucSafe produces stationary, mobile, and hand-held systems that use neutron and gamma ray sensors to detect Special Nuclear Materials (SNM). Neutron sensors are comprised of scintillating glass fibers (trade name 'PUMA' for Pu Materials Analysis), which provide several advantages over 3 He and 10 BF 3 tubes. PUMA 6 Li glass fiber sensors offer greater neutron sensitivity and dynamic counting range with significantly less microphonic susceptibility than tubes, while eliminating transport and operational hazards. PUMA sensors also cost less per active area than gas tubes, which is important since rapid neutron detection at passenger, freight, and vehicle portals require large sensor areas to provide the required sensitivity

  11. INFLUENCE OF HIGH-ENERGY FORMING ON THE BEHAVIOR OF MATERIALS (EINFLUSS DER HOCHENERGIEUMFORMUNG AUF DAS WERKSTOFFVERHALTEN),

    Science.gov (United States)

    MATERIAL FORMING, METALS), (*METALS, MECHANICAL PROPERTIES), EXPLOSIVE FORMING, ELECTROFORMING, HYDROFORMING (MECHANICAL), IRON, STEEL, NICKEL, NIOBIUM, TENSILE PROPERTIES, TANTALUM, DEFORMATION, EAST GERMANY.

  12. Physical protection of special nuclear materials in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1987-01-01

    Measures to protect special nuclear materials in West Germany are based on a relatively likely average threat and not on the less-likely but maximum credible threat. The reason is to avoid the costs of maintaining a very high level of security that is seldom needed. The concept of delayed action, which divides the responsibility for security between private protection forces and local police forces, would be insufficient in the event of the maximum credible threat. In principle, sufficient security is possible only when the facilities and transports are constantly protected by a police force large enough to deal with the maximum credible threat without assistance from outside. They must also be adequately armed to avert all possible attackers, and they must be paid by the licensees. The threat of an insider(s) diverting special nuclear material can be addressed only by strengthening the scope and depth of the checks on applicants and employees and the permanent work controls. It is recognized, however, that such security measures may not be compatible with constitutional civil liberties

  13. Lateral spread as a special form of soil movement in Dolina area in municipality Puconci

    Directory of Open Access Journals (Sweden)

    Magda Čarman

    2014-07-01

    Full Text Available The paper presents a particular form of soil instability, which is rarely observed in Slovenia. This is a lateral spread of the soil, which appeared some years ago in the central part of Dolina area in the municipality of Puconci. The area is mainly build up from clay and sandy sediments of the Pannonian Sea, predominantly Pliocene age. A significant damage of building has begun several years ago. According to data from research carried out, we suggest that the flat area is disintegrated into individual blocks, moving in different directions. These led to such extensive damage to buildings. Possible cause could be erosion of Dolinski stream at the eastern edge of the area or seismic survey (blasting, vibrations, which were carried out here about 20 years ago. Determination the exact cause of the formation of the soil lateral spread, its extent and dynamics, remain a challenge for the future.

  14. Nickel-based materials and high-alloy, special stainless steels. 2. new rev. and enl. ed.

    International Nuclear Information System (INIS)

    Heubner, U.; Brill, U.; Hoffmann, T.; Jasner, M.; Kirchheiner, R.; Koecher, R.; Richter, H.; Rockel, M.; White, F.

    1993-01-01

    The book is intended as a source of information on nickel-based materials and special stainless steels and apart from the up-to-date materials data presents information on recent developments and knowledge gained, so that it may be a valuable aid to materials engineers looking for cost-effective resolutions of their materials problems in the chemical process industry, power plant operation, and high-temperature applications. The book presents eight individual contributions entitled as follows: (1) Nickel-base alloys and high-alloy, special stainless steels. - Materials survey and data sheets (Ulrich Heubner). (2) Corrosion of nickel-base alloys and special stainless steels (Manfred Rockel). (3) Welding of nickel-base alloys and high-alloy, special stainless steels (Theo Hoffmann). (4) High-temperature resistant materials (Ulrich Brill). (5) Application and processing of nickel-base materials in the chemical process industry and in pollution abatement equipment (Reiner Koecher). (6) Selected examples of applications of nickel-base materials in chemical plant (Manfred Jasner, Frederick White). (7) Applications of nickel-base alloys and special stainless steels in power plant. (8) The use of nickel-base alloys and stainless steels in pollution abatement processes (R. Kirchheiner). (orig./MM). 151 figs., 226 refs [de

  15. Preparation and thermal properties of form stable paraffin phase change material encapsulation

    International Nuclear Information System (INIS)

    Liu Xing; Liu Hongyan; Wang Shujun; Zhang Lu; Cheng Hua

    2006-01-01

    Paraffin waxes are cheap and have moderate thermal energy storage density but low thermal conductivity and, hence, require large surface area to be used in energy storage. Form stable paraffin phase change materials (PCM) in which paraffin serves as a latent heat storage material and polyolefins act as a supporting material, because of paraffin leakage, are required to be improved. The form stable paraffin PCM in the present paper was encapsulated in an inorganic silica gel polymer successfully by in situ polymerization. The differential scanning calorimeter (DSC) was used to measure its thermal properties. At the same time, the Washburn equation, which measures the wetting properties of powder materials, was used to test the hydrophilic-lipophilic properties of the PCMs. The result indicated that the enthalpy of the microencapsulated PCMs was reduced little, while their hydrophilic properties were enhanced largely

  16. Investigation of special capsule technologies for material in-pile irradiation test and development plan in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Cho, M. S.; Son, J. M.; Kim, D. S.; Park, S. J.; Cho, Y. G.; Seo, C. K.; Kang, Y. H. [KAERI, Taejon (Korea, Republic of)

    2002-10-01

    In-pile test for several materials such as Zr alloy, stainless steel, Cr-Ni steel etc. which are used as structural material of the advanced reactor and KNGR(Korea Next Generation Reactor) like SMART, is necessary to produce the design data for developing new reactor materials. Advanced countries like USA, Europe and Japan etc. are not only performing the simple irradiation test for materials, but developing many kinds of special capsule to perform in-pile test having special purpose. For the special test items of fuel rod, fission products, total heat generation, swelling, deformation, sweep gas, temperature ramping and BOCA etc. are being actively concerned. There are capsules measuring creep, fatigue, crack growth, and controlling fluence etc. for special irradiation test of materials. In addition, the advanced countries are developing several instrument technologies suitable for the special capsules. In HANARO, non-instrumented, instrumented material capsules and non-instrumented fuel capsule have been developed and they have been utilized in the irradiation test for users, and creep capsule loading single specimen was made and is planned to test in the reactor soon. For some forthcoming years, special capsules not only measuring creep deformation with multi-specimens, fatigue, controlling fluence but crack propagation and gas sweep considering the requirements of users will be developed in HANARO.

  17. Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging.

    Science.gov (United States)

    Rose, P B; Erickson, A S; Mayer, M; Nattress, J; Jovanovic, I

    2016-04-18

    Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as "searching for a needle in a haystack" because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material's areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

  18. Palmitic acid/polypyrrole composites as form-stable phase change materials for thermal energy storage

    International Nuclear Information System (INIS)

    Silakhori, Mahyar; Metselaar, Hendrik Simon Cornelis; Mahlia, Teuku Meurah Indra; Fauzi, Hadi; Baradaran, Saeid; Naghavi, Mohammad Sajad

    2014-01-01

    Highlights: • A novel phase change composite of palmitic acid–polypyrrole(PA–PPy) was fabricated. • Thermal properties of PA–PPy are characterized in different mass ratios of PA–PPy. • Thermal cycling test showed that form stable PCM had a favorable thermal reliability. - Abstract: In this study a novel palmitic acid (PA)/polypyrrole (PPy) form-stable PCMs were readily prepared by in situ polymerization method. PA was used as thermal energy storage material and PPy was operated as supporting material. Form-stable PCMs were investigated by SEM (scanning electron microscopy) and FTIR (Fourier transform infrared spectrometer) analysis that illustrated PA Particles were wrapped by PPy particles. XRD (X-ray diffractometer) was used for crystalline phase of PA/PPy composites. Thermogravimetry analysis (TGA) and differential scanning calorimetry (DSC) were used for investigating Thermal stability and thermal energy storage properties of prepared form-stable PCMs. According to the obtained results the form stable PCMs exhibited favorable thermal stability in terms of their phase change temperature. The form-stable PCMs (79.9 wt% loading of PA) were considered as the highest loading PCM with desirable latent heat storage of 166.3 J/g and good thermal stability. Accelerated thermal cycling tests also showed that form stable PCM had an acceptable thermal reliability. As a consequence of acceptable thermal properties, thermal stability and chemical stability, we can consider the new kind of form stable PCMs for low temperature solar thermal energy storage applications

  19. Forms of international movement of capital with special emphasis on the PPP and concessions

    Directory of Open Access Journals (Sweden)

    Šovran Sanja

    2016-01-01

    Full Text Available The state has always cooperated with the private sector in order to implement various activities in the best interest of public. The first models of public-private partnerships (PPP appeared at the time of the Roman Empire in the context of public works in construction of public baths, markets and ports. Contemporary international movement of capital is a phenomenon that has existed for over a century. When discussing the PPP in modern day terms, the expansion of private involvement in the public sector starts in the 1970s and the 1980s of the previous century, in public infrastructure projects and in most developed economies. The primary purpose of these arrangements is to reduce expenditures in state budgets, but also to achieve faster and better execution of work, reduce risk and efficiently manage the projects. This paper will briefly present the evolution of PPPs and concessions, with an emphasis on understanding money and capital throughout the evolution of PPP, contemporary forms of movement of capital, as well as equity in terms of globalization. The subject of this paper are also examples of the important PPPs and concessions from the construction of the Suez Canal until today.

  20. Investigation of waste form materials suitable for immobilizing actinide elements in high-level waste

    International Nuclear Information System (INIS)

    Hayakawa, Issei; Kamizono, Hiroshi

    1992-07-01

    The microstructure of waste form materials suitable for immobilizing actinide elements can be classified into the following two categories. (1) Actinide elements are immobilized in an crystallized matrix after the formation of solid solution or compounds. (2) Actinide elements are immobilized in a durable material by encapsulation. Based on crystal chemistry, durability data, phase diagrams, compositions of natural minerals, eleven oxide compounds and one non-oxide compound are pointed out to be new candidates included in category (1). The other survey on material compositions, manufacturing conditions and feasibility shows that SiC, glassy carbon, ZrO 2 , Ti-O-Si-C ceramics are preferable matrix materials included in category (2). Polymers and fine powders are suitable as starting materials for the encapsulation of actinide elements because of their excellent sinterability. (author) 50 refs

  1. Decree of 4 November 1982 on conditions for notification of possession of special fissile materials and source materials and for keeping accounts thereof

    International Nuclear Information System (INIS)

    1982-01-01

    This Decree lays down a detailed procedure for notification of the possession and accounting of special fissile materials and source materials. The Decree was made in pursuance of Decree No. 185 of 13 February 1964 of the President of the Republic concerning radiation protection and licensing procedures. (NEA) [fr

  2. Modeling of hydrogen storage in hydride-forming materials : statistical thermodynamics

    NARCIS (Netherlands)

    Ledovskikh, A.; Danilov, D.; Rey, W.J.J.; Notten, P.H.L.

    2006-01-01

    A new lattice gas model has been developed, describing the hydrogen storage in hydride-forming materials. This model is based on the mean-field theory and Bragg-Williams approximation. To describe first-order phase transitions and two-phase coexistence regions, a binary alloy approach has been

  3. Effect of Bottoming on Material Property during Sheet Forming Process through Finite Element Method

    Science.gov (United States)

    Akinlabi, Stephen A.; Fatoba, Olawale S.; Mashinini, Peter M.; Akinlabi, Esther T.

    2018-03-01

    Metal forming is one of the conventional manufacturing processes of immense relevance till date even though modern manufacturing processes have evolved over the years. It is a known fact that material tends to return or spring back to its original form during forming or bending. The phenomena have been well managed through its application in various manufacturing processes by compensating for the spring back through overbending and bottoming. Overbending is bending the material beyond the desired shape to allow the material to spring back to the expected shape. Bottoming, on the other hand, is a process of undergoing plastic deformation at the point of bending. This study reports on the finite element analysis of the effect of bottoming on the material property during the sheet forming process with the aim of optimising the process. The result of the analysis revealed that the generated plastic strains are in the order between 1.750e00-1 at the peak of the bending and 3.604e00-2, which was at the early stage of the bending.

  4. MM99.70 - MODELS FOR FRICTION AND MATERIAL STRESS STRAIN HARDENING IN COLD FORMING

    DEFF Research Database (Denmark)

    Eriksen, Morten

    1999-01-01

    and tool temperature for four different combination of basic material, conversion layer and lubricant. Furthermore flow stress curves for aluminium, steel and stainless steel are given at varying slug temperatures in the range which can be reached in cold forming (25-200C).The documentation is divided...

  5. Materials characterization center workshop on the irradiation effects in nuclear waste forms

    International Nuclear Information System (INIS)

    Roberts, F.P.; Turcotte, R.P.; Weber, W.J.

    1981-01-01

    The Workshop on Irradiation Effects in Nuclear Waste Forms sponsored by the Materials Characterization Center (MCC) brought together experts in radiation damage in materials and waste-management technology to review the problems associated with irradiation effects on waste-form integrity and to evaluate standard methods for generating data to be included in the Nuclear Waste Materials Handbook. The workshop reached the following conclusions: the concept of Standard Test for the Effects of Alpha-Decay in Nuclear Waste Solids, (MCC-6) for evaluating the effects of alpha decay is valid and useful, and as a result of the workshop, modifications to the proposed procedure will be incorpoated in a revised version of MCC-6; the MCC-6 test is not applicable to the evaluation of radiation damage in spent fuel; plutonium-238 is recommended as the dopant for transuranic and defense high-level waste forms, and when high doses are required, as in the case of commercial high-level waste forms, 244 Cm can be used; among the important property changes caused by irradiation are those that lead to greater leachability, and additionally, radiolysis of the leachant may increase leach rates; research is needed in this area; ionization-induced changes in physical properties can be as important as displacement damage in some materials, and a synergism is also likely to exist from the combined effects of ionization and displacement damage; and the effect of changing the temperature and dose rates on property changes induced by radiation damage needs to be determined

  6. An advanced material model for aluminum sheet forming at elevated temperatures

    NARCIS (Netherlands)

    Kurukuri, S.; Miroux, Alexis; Ghosh, Manojit; van den Boogaard, Antonius H.; Oñate, E.; Owen, D.R.J; Suárez, B.

    2009-01-01

    A physically-based material model according to Nes is used to simulate the warm forming of Al-Mg-Si sheet. This model incorporates the influence of the temperature and strain rate on the flow stress and on the hardening rate based on storage and dynamic recovery of dislocations. The effect of size

  7. On screening for Special Nuclear Materials (SNMs) with X-ray diffraction

    International Nuclear Information System (INIS)

    Harding, G.

    2010-01-01

    A novel detection technique employing X-ray diffraction (XRD) to screen for Special Nuclear Materials (SNMs), in particular for uranium, has been recently proposed. It is based on the interesting fact that uranium (and incidentally, plutonium) has a non-cubic lattice structure, in contrast to all other non-SNM, high-density elements of the Periodic Table. The principle of this screening technique is briefly elucidated by comparing the XRD lines of uranium with those of lead, a material of high atomic number (Z) commonly found in container traffic. Several physical conditions that must be satisfied to enable XRD for SNM screening are considered. To achieve adequate penetration, both of suspicious high-Z materials and their containers, photon energies of 1 MeV and above must be employed. Implications from partial coherence theory for the XRD measurement geometry at such photon energies are presented. The question of multiple scatter degradation of the coherent scatter signal is addressed. Technological considerations relevant to performing XRD at 1 MeV, particularly regarding the radiation source and detector, are discussed. A novel secondary aperture scheme permitting high energy XRD is presented. It is concluded that the importance of the application and the prospect of its feasibility are sufficient to warrant experimental verification.

  8. An activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a costeffective manner

  9. Activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.; Reigle, D.L.; Valente, A.D.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a cost-effective manner. 3 references, 1 figure, 1 table

  10. 10 CFR 73.73 - Requirement for advance notice and protection of export shipments of special nuclear material of...

    Science.gov (United States)

    2010-01-01

    ... shipments of special nuclear material of low strategic significance. 73.73 Section 73.73 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Records and Reports § 73.73... Incident Response, using any appropriate method listed in § 73.4; (2) Assure that the notification will be...

  11. Special training for drivers of vehicles carrying radioactive materials in Germany

    International Nuclear Information System (INIS)

    Ridder, K.

    1992-01-01

    No rule, not even the best, serves its purpose if it is not complied with just because it is not known. In Europe, and in Germany particularly, this has been accepted wisdom for 12 years. With respect to the greater risk emanating form tank-vehicles, and in the aftermath of a tank-vehicle accident due to the driver's error in Spain 1987 (Los Alfaques) that killed more than 200 persons, tank-vehicle drivers had to undergo special training since midyear 1991. Training is organised in a modular system, which means that the driver can customise his dangerous goods training programme by combining several modules. The contents of the training programme, its organisation and supervision as well as the means for checking the successful completion of the programme are shown. (Author)

  12. Study on polyethylene glycol/epoxy resin composite as a form-stable phase change material

    International Nuclear Information System (INIS)

    Fang Yutang; Kang Huiying; Wang Weilong; Liu Hong; Gao Xuenong

    2010-01-01

    Form-stable polyethylene glycol (PEG)/epoxy resin (EP) composite as a novel phase change material (PCM) was prepared using casting molding method. In this new material, PEG acts as the latent heat storage material and EP polymer serves as the supporting material, which provides structural strength and prevents the leakage of the melted PEG. The structure and morphology of the novel composite were observed using Fourier transformation infrared spectroscope (FTIR) and scanning electronic microscope (SEM). The thermo-mechanical property and transition behavior were characterized by polarizing optical microscope (POM), static thermo-mechanical analysis (TMA) and differential scanning calorimeter (DSC). The experimental results show that, as a result of the physical tangled function of the epoxy resin carrier to the PEG segment, the composite macroscopically presents the solid-solid phase change characteristic.

  13. Finite element analysis and optimization of process parameters during stamp forming of composite materials

    International Nuclear Information System (INIS)

    Venkatesan, S; Kalyanasundaram, S

    2010-01-01

    In the manufacture of parts for high performance structures using composite materials, the quality and robustness of the parts is of utmost importance. The quality of the produced parts depends largely on the process parameters and manufacturing methodologies. This study presents the use of a temperature dependant orthotropic material for a coupled structural-thermal analysis of the stamp forming process. The study investigated the effects of process parameters such as pre-heat temperature, blank holder force and process time on the formability of composite materials. Temperature was found to be the dominant factor governing the formability of the composite material while higher blank holder forces were deemed to be important for achieving high quality of the parts manufactured. Finally, an optimum set of parameters was used to compare the simulations with experimental results using an optical strain measurement system.

  14. Indirect Versus Direct Heating of Sheet Materials: Superplastic Forming and Diffusion Bonding Using Lasers

    Science.gov (United States)

    Jocelyn, Alan; Kar, Aravinda; Fanourakis, Alexander; Flower, Terence; Ackerman, Mike; Keevil, Allen; Way, Jerome

    2010-06-01

    Many from within manufacturing industry consider superplastic forming (SPF) to be ‘high tech’, but it is often criticized as too complicated, expensive, slow and, in general, an unstable process when compared to other methods of manipulating sheet materials. Perhaps, the fundamental cause of this negative perception of SPF, and also of diffusion bonding (DB), is the fact that the current process of SPF/DB relies on indirect sources of heating to produce the conditions necessary for the material to be formed. Thus, heat is usually derived from the electrically heated platens of hydraulic presses, to a lesser extent from within furnaces and, sometimes, from heaters imbedded in ceramic moulds. Recent evaluations of these isothermal methods suggest they are slow, thermally inefficient and inappropriate for the process. In contrast, direct heating of only the material to be formed by modern, electrically efficient, lasers could transform SPF/DB into the first choice of designers in aerospace, automotive, marine, medical, architecture and leisure industries. Furthermore, ‘variable temperature’ direct heating which, in theory, is possible with a laser beam(s) may provide a means to control material thickness distribution, a goal of enormous importance as fuel efficient, lightweight structures for transportation systems are universally sought. This paper compares, and contrasts, the two systems and suggests how a change to laser heating might be achieved.

  15. A special form of SPD covariance matrix for interpretation and visualization of data manipulated with Riemannian geometry

    Science.gov (United States)

    Congedo, Marco; Barachant, Alexandre

    2015-01-01

    Currently the Riemannian geometry of symmetric positive definite (SPD) matrices is gaining momentum as a powerful tool in a wide range of engineering applications such as image, radar and biomedical data signal processing. If the data is not natively represented in the form of SPD matrices, typically we may summarize them in such form by estimating covariance matrices of the data. However once we manipulate such covariance matrices on the Riemannian manifold we lose the representation in the original data space. For instance, we can evaluate the geometric mean of a set of covariance matrices, but not the geometric mean of the data generating the covariance matrices, the space of interest in which the geometric mean can be interpreted. As a consequence, Riemannian information geometry is often perceived by non-experts as a "black-box" tool and this perception prevents a wider adoption in the scientific community. Hereby we show that we can overcome this limitation by constructing a special form of SPD matrix embedding both the covariance structure of the data and the data itself. Incidentally, whenever the original data can be represented in the form of a generic data matrix (not even square), this special SPD matrix enables an exhaustive and unique description of the data up to second-order statistics. This is achieved embedding the covariance structure of both the rows and columns of the data matrix, allowing naturally a wide range of possible applications and bringing us over and above just an interpretability issue. We demonstrate the method by manipulating satellite images (pansharpening) and event-related potentials (ERPs) of an electroencephalography brain-computer interface (BCI) study. The first example illustrates the effect of moving along geodesics in the original data space and the second provides a novel estimation of ERP average (geometric mean), showing that, in contrast to the usual arithmetic mean, this estimation is robust to outliers. In

  16. Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1998 edition

    International Nuclear Information System (INIS)

    1998-08-01

    The information contained in this report is given in six tables. Tables 1 to 4 present administrative data including issue and expiration dates, package identification, package serial numbers, modes for which the package/shipments approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6 shows the certificates reported to the IAEA Secretariat by each participating Member State

  17. Development of special radiation shielding concretes using natural local materials and evaluation of their shielding characteristics

    International Nuclear Information System (INIS)

    Kharita, M. H.; Takeyeddin, M.; Al-Nassri, M.; Yousef, S.

    2008-01-01

    Concrete is one of the most important materials used for radiation shielding in facilities containing radioactive sources and radiation generating machines. The concrete shielding properties may vary depending on the composite of the concrete. Aggregates is the largest constituent (about 70-80% of the total weight of normal concrete). The aim of this work is to develop special concrete with good shielding properties for gamma and neutrons, using natural local materials. For this reason two types of typical concrete widely used in Syria (in Damascus and Aleppo) and four other types of concrete, using aggregates from different regions, have been prepared. The shielding properties of these six types were studied for gamma ray (from Cs-137 and Co-60 sources)and for neutrons (from am-Be source). A reduction of about 10% in the HVL was obtained for the concrete from Damascus in comparison with that from Aleppo, for both neutrons and gammas. One of the other four types of concrete (from Rajo site, mostly Hematite), was found to further reduce the HVL by about 10% for both neutrons and gamma rays.(author)

  18. Colorimetric determination of a paracetamole in raw material and in pharmaceutical dosage forms

    International Nuclear Information System (INIS)

    Usifoh, C.O; Adelusi, S.A.; Adebambo, R.F.

    2002-01-01

    A rapid, accurate and simple method is proposed for the determination of p-acetaminophen (paracetamole) in raw material, tablets and syrups. The method is based on measuring the intensity of the yellow color that developed when acute acetaminophen is allowed to react with p-dimethylaminobenzaldehyde in 2M HCl after heating. The color which absorbs in the visible region of gamma 450 nm is stable for several hours and the intensity is directly proportional to the concentration of the drug, that is, Beer lambert law is obeyed. The method can be used to analyse paracetamole in raw material and in pharmaceutical dosage forms. (author)

  19. Ways of decision of problem of forming for the cadets of the special qualities, need the militiaman to successful counteract against the armed attack

    Directory of Open Access Journals (Sweden)

    Bondarenko V.V.

    2010-10-01

    Full Text Available Directions of forming of the special qualities of workers of militia are certain. Information is systematized about the real collisions of workers of militia with criminals. Conformities to law are rotined in the conduct of a be out for scalps criminal. The necessity of development and perfection of the special qualities of workers of militia is exposed. The terms of the hidden attack of criminal are considered. The necessity of mastering of knowledge is rotined about preparatory motions of the armed criminal. Directions of perfection of the special physical and psychical qualities, forming of abilities and skills of implementation of receptions of disarmament, are resulted.

  20. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 1: Summary of exercise

    International Nuclear Information System (INIS)

    Libby, R.A.; Davis, C.; Segal, J.E.; Stanbro, W.D.

    1995-08-01

    In a September 1993 address to the United Nations General Assembly, President Clinton announced a new nonproliferation and export control policy that established a framework for US efforts to prevent the proliferation of weapons of mass destruction. The new policy proposed that the US undertake a comprehensive approach to the growing accumulation of fissile material. One of the key elements was for the US to support a special nuclear materials (SNM) multilateral convention prohibiting the production of highly enriched uranium (HEU) or plutonium for nuclear explosives purposes or outside of international safeguards. This policy is often referred to as the President's Cutoff Initiative or the Fissile Material Cutoff Treaty (FMCT). Because both the US Department of Energy (DOE) and foreign reprocessing facilities similar to PUREX will likely to be inspected under a FMCT, the DOE Office of Arms Control and Nonproliferation, Negotiations and Analysis Division (DOE/NN-41) tasked Pacific Northwest Laboratory (PNL) to perform an information gathering exercise, the PUREX Exercise, using the Plutonium-Uranium Extraction (PUREX) Plant located on the Hanford Site in Washington State. PUREX is a former production reactor fuel reprocessing plant currently undergoing a transition to a ''decontamination and decommissioning (D ampersand D) ready'' mode. The PUREX Exercise was conducted March 29--30, 1994, to examine aspects of the imposition of several possible cutoff regimes and to study verification of non-production of SNM for nuclear weapons purposes or outside of safeguards. A follow-up activity to further examine various additional verification regimes was held at Los Alamos National Laboratory (LANL) on May 10, 1994

  1. Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Paul, J. N.; Chin, M. R.; Sjoden, G. E. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

    2013-07-01

    A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

  2. On the material properties of shell plate formed by line heating

    Directory of Open Access Journals (Sweden)

    Hyung Kyun Lim

    2017-01-01

    Full Text Available This paper is concerned with investigating the plastic material properties of steel plate formed by line heating method, and is aimed at implementing more rational design considering the accidental limit states such as collision or grounding. For the present study, line heating test for marine grade steel plate has been carried out with varying plate thickness and heating speed, and then microscopic examination and tensile test have been carried out. From the microscopic, it is found that the grain refined zones like ferrite and pearlite are formed all around the heat affected zone. From the tensile test results, it is seen that yield strength, tensile strength, fracture strain, hardening exponent and strength coefficient vary with plate thickness and heat input quantity. The formulae relating the material properties and heat input parameter should be, therefore, derived for the design purpose considering the accidental impact loading. This paper ends with describing the extension of the present study.

  3. Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

    Energy Technology Data Exchange (ETDEWEB)

    Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

    2012-07-01

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an

  4. 76 FR 454 - Hazardous Materials Transportation: Revisions of Special Permits Procedures

    Science.gov (United States)

    2011-01-05

    ... special permits. The HMR generally are performance-oriented regulations that provide the regulated... forbidden for transportation by aircraft except under a special permit (see Columns 9A and 9B in the table...

  5. Materials for Pharmaceutical Dosage Forms: Molecular Pharmaceutics and Controlled Release Drug Delivery Aspects

    Directory of Open Access Journals (Sweden)

    Patrick P. DeLuca

    2010-09-01

    Full Text Available Controlled release delivery is available for many routes of administration and offers many advantages (as microparticles and nanoparticles over immediate release delivery. These advantages include reduced dosing frequency, better therapeutic control, fewer side effects, and, consequently, these dosage forms are well accepted by patients. Advances in polymer material science, particle engineering design, manufacture, and nanotechnology have led the way to the introduction of several marketed controlled release products and several more are in pre-clinical and clinical development.

  6. High-fidelity MCNP modeling of a D-T neutron generator for active interrogation of special nuclear material

    International Nuclear Information System (INIS)

    Katalenich, Jeff; Flaska, Marek; Pozzi, Sara A.; Hartman, Michael R.

    2011-01-01

    Fast and robust methods for interrogation of special nuclear material (SNM) are of interest to many agencies and institutions in the United States. It is well known that passive interrogation methods are typically sufficient for plutonium identification because of a relatively high neutron production rate from 240 Pu . On the other hand, identification of shielded uranium requires active methods using neutron or photon sources . Deuterium-deuterium (2.45 MeV) and deuterium-tritium (14.1 MeV) neutron-generator sources have been previously tested and proven to be relatively reliable instruments for active interrogation of nuclear materials . In addition, the newest generators of this type are small enough for applications requiring portable interrogation systems. Active interrogation techniques using high-energy neutrons are being investigated as a method to detect hidden SNM in shielded containers . Due to the thickness of some containers, penetrating radiation such as high-energy neutrons can provide a potential means of probing shielded SNM. In an effort to develop the capability to assess the signal seen from various forms of shielded nuclear materials, University of Michigan Neutron Science Laboratory's D-T neutron generator and its shielding were accurately modeled in MCNP. The generator, while operating at nominal power, produces approximately 1x10 10 neutrons/s, a source intensity which requires a large amount of shielding to minimize the dose rates around the generator. For this reason, the existing shielding completely encompasses the generator and does not include beam ports. Therefore, several MCNP simulations were performed to estimate the yield of uncollided 14.1-MeV neutrons from the generator for active interrogation experiments. Beam port diameters of 5, 10, 15, 20, and 25 cm were modeled to assess the resulting neutron fluxes. The neutron flux outside the beam ports was estimated to be approximately 2x10 4 n/cm 2 s.

  7. Process for forming a homogeneous oxide solid phase of catalytically active material

    Science.gov (United States)

    Perry, Dale L.; Russo, Richard E.; Mao, Xianglei

    1995-01-01

    A process is disclosed for forming a homogeneous oxide solid phase reaction product of catalytically active material comprising one or more alkali metals, one or more alkaline earth metals, and one or more Group VIII transition metals. The process comprises reacting together one or more alkali metal oxides and/or salts, one or more alkaline earth metal oxides and/or salts, one or more Group VIII transition metal oxides and/or salts, capable of forming a catalytically active reaction product, in the optional presence of an additional source of oxygen, using a laser beam to ablate from a target such metal compound reactants in the form of a vapor in a deposition chamber, resulting in the deposition, on a heated substrate in the chamber, of the desired oxide phase reaction product. The resulting product may be formed in variable, but reproducible, stoichiometric ratios. The homogeneous oxide solid phase product is useful as a catalyst, and can be produced in many physical forms, including thin films, particulate forms, coatings on catalyst support structures, and coatings on structures used in reaction apparatus in which the reaction product of the invention will serve as a catalyst.

  8. Improvements in or relating to the production of metal-containing material in particulate form

    International Nuclear Information System (INIS)

    Woodhead, J.L.; Scott, K.T.B.; Ball, P.W.

    1977-01-01

    The process described refers mainly to production of the material in the form of very small spheres. It comprises forming a metal compound-containing gel precipitate by mixing a solution or sol of the metal compound with a soluble organic polymer and contacting the mixture with a precipitating reagent to precipitate the metal as an insoluble compound bound with the polymer. The precipitate is then subjected in the liquid phase to a breaking down and dispersing process to produce an intermediate product suitable for spray drying, and the intermediate product is spray dried to form the particulate product. The breaking down and dispersing process may be performed by means of a colloid mill or vibratory stirrer. Examples of application of the process are described. (U.K.)

  9. Dual Neutral Particle Beam Interrogation of Intermodal Shipping Containers for Special Nuclear Material

    Science.gov (United States)

    Keith, Rodney Lyman

    Intermodal shipping containers entering the United States provide an avenue to smuggle unsecured or stolen special nuclear material (SNM). The only direct method fielded to indicate the presence of SNM is by passive photon/neutron radiation detection. Active interrogation using neutral particle beams to induce fission in SNM is a method under consideration. One by-product of fission is the creation of fragments that undergo radioactive decay over a time period on the order of tens of seconds after the initial event. The "delayed" gamma-rays emitted from these fragments over this period are considered a hallmark for the presence of SNM. A fundamental model is developed using homogenized cargos with a SNM target embedded at the center and computationally interrogated using simultaneous neutron and photon beams. Findings from analysis of the delayed gamma emissions from these experiments are intended to mitigate the effects of poor quality information about the composition and disposition of suspect cargo before examination in an active interrogation portal.

  10. Development of a re-brazeable containment system for special nuclear material storage and transport

    International Nuclear Information System (INIS)

    Pierce, J.D.; Stephens, J.J.; Walker, C.A.; Hosking, F.M.; Curlee, R.M.

    1995-01-01

    This report describes a novel means of closing and sealing small type B radioactive material transport packages for surface or air transport as governed by 10CFR71 or NUREG-0360 has been developed at Sandia National Laboratories (SNL). This method is a controlled brazing process that may be used to attach and seal a closure lid to a containment vessel and then remove it at a later time. The process may be performed multiple times without the need for special preparations of the braze joint. A number of advantages for utilization of this technique have been determined. A brazed seal has integrity at high temperatures for better protection in accident or abnormal environments. A properly designed joint has essentially the same strength as the parent metal. A closure that is brazed, therefore, will no longer be the anticipated point of failure for a broad range of accident environments. This technique will allow the containment vessel design to be optimized with a lighter, more uniform wall thickness throughout. Finally, with a well defined process for sealing, mechanical inspection, leak testing, and then reopening at a later time, automation of the process is relatively straightforward and the overall system should be as easy to use as one that utilizes elastomeric seals for containment

  11. Investigation of Active Interrogation Techniques to Detect Special Nuclear Material in Maritime Environments

    International Nuclear Information System (INIS)

    Miller, Thomas Martin; Patton, Bruce W.

    2010-01-01

    The detection and interdiction of special nuclear material (SNM) is still a high-priority focus area for many organizations around the world. One method that is commonly considered a leading candidate in the detection of SNM is active interrogation (AI). AI is different from its close relative, passive interrogation, in that an active source is used to enhance or create a detectable signal (usually fission) from SNM, particularly in shielded scenarios or scenarios where the SNM has a low activity. The use of AI thus makes the detection of SNM easier or, in some scenarios, even enables previously impossible detection. In this work the signal from prompt neutrons and photons as well as delayed neutrons and photons will be combined, as is typically done in AI. In previous work AI has been evaluated experimentally and computationally. However, for the purposes of this work, past scenarios are considered lightly shielded and tightly coupled spatially. At most, the previous work interrogated the contents of one standard cargo container (2.44 x 2.60 x 6.10 m) and the source and detector were both within a few meters of the object being interrogated. A few examples of this type of previous work can be found in references 1 and 2. Obviously, more heavily shielded AI scenarios will require larger source intensities, larger detector surface areas (larger detectors or more detectors), greater detector efficiencies, longer count times, or some combination of these.

  12. Development of "material-specific" hemispheric specialization from beginning to end.

    Science.gov (United States)

    Gingras, Benjamin; Braun, Claude M J

    2018-07-01

    Disparity of verbal and performance intelligence (VIQ, PIQ) on the Wechsler scales of intelligence is a conceptually cluttered and empirically weak measure of hemispheric specialization (HS). However, in the context of life span research, it is the only measure that can be exploited meta-analytically with the lesion method from prenatal life to late senescence. We assembled 1917 cases with a unilateral cortical focal brain lesion occurring at all ages and a post-lesion VIQ and PIQ. Lesion locus, volume and side were documented for each case, as well as age at lesion onset, age at first symptoms and age at the IQ test, presence/absence of epilepsy, lesion aetiology, gender, date of publication or of transfer of medical file. With and without covariate adjustment, HS was significant across the life span though its pattern changed. HS increased linearly and highly significantly until late senescence. Only in early adulthood did VIQ appear to vacate the right temporal lobe and occupy the left and PIQ vacate the left parietal lobe and occupy the right until late senescence. Biomaturational factors are more important in the ontogeny of material-specific HS over the whole life span than previously established.

  13. Technique for detecting a small magnitude loss of special nuclear material

    International Nuclear Information System (INIS)

    Pike, D.H.; Chernick, M.R.; Downing, D.J.

    The detection of losses of special nuclear materials has been the subject of much research in recent years. The standard industry practice using ID/LEID will detect large magnitude losses. Time series techniques such as the Kalman Filter or CUSUM methods will detect small magnitude losses if they occur regularly over a sustained period of time. To date no technique has been proposed which adequately addresses the problem of detecting a small magnitude loss occurring in a single period. This paper proposes a method for detecting a small magnitude loss. The approach makes use of the influence function of Hempel. The influence function measures the effect of a single inventory difference on a group of statistics. An inventory difference for a period in which a loss occurs can be expected to produce an abnormality in the calculated statistics. This abnormality is measurable by the influence function. It is shown that a one period loss smaller in magnitude than the LEID can be detected using this approach

  14. Finite element analysis of ion transport in solid state nuclear waste form materials

    Science.gov (United States)

    Rabbi, F.; Brinkman, K.; Amoroso, J.; Reifsnider, K.

    2017-09-01

    Release of nuclear species from spent fuel ceramic waste form storage depends on the individual constituent properties as well as their internal morphology, heterogeneity and boundary conditions. Predicting the release rate is essential for designing a ceramic waste form, which is capable of effectively storing the spent fuel without contaminating the surrounding environment for a longer period of time. To predict the release rate, in the present work a conformal finite element model is developed based on the Nernst Planck Equation. The equation describes charged species transport through different media by convection, diffusion, or migration. And the transport can be driven by chemical/electrical potentials or velocity fields. The model calculates species flux in the waste form with different diffusion coefficient for each species in each constituent phase. In the work reported, a 2D approach is taken to investigate the contributions of different basic parameters in a waste form design, i.e., volume fraction, phase dispersion, phase surface area variation, phase diffusion co-efficient, boundary concentration etc. The analytical approach with preliminary results is discussed. The method is postulated to be a foundation for conformal analysis based design of heterogeneous waste form materials.

  15. Regulatory Aspects of Clearance and Recycling of Metallic Material forming Part of Buildings of Nuclear Facilities in Germany

    International Nuclear Information System (INIS)

    Thierfeldt, Stefan; Woerlen, Stefan; Harding, Philip

    2014-01-01

    Metallic materials as part of buildings of nuclear installations, like reinforcement in concrete, anchor slabs, pipework buried in concrete, but also steel liners of water basins or anchor rails that are welded to the reinforcement steel etc. require special considerations during decommissioning. It is the aim to release as much of this material as possible for recycling (either by melting in conventional foundries or by melting in a controlled recycling plant for reuse in the nuclear field). This poses problems as on the one hand these metallic materials cannot be removed from the buildings prior to their demolition, while on the other hand they would in principle require a specific clearance procedure for which they should be available separately. Besides aspects of radiological characterisation and measurements, this is also a regulatory issue, as the competent authority has to grant clearance of materials that may not be fully characterised by measurements, but for which a significant part of the information required for clearance is inferred from the operational history, from conclusions by analogy and from other sources. This issue has been resolved in different ways in various NPPs in Germany. Examples of materials that pose problems of the kind listed above (including relevant contamination pathways) are given, together with examples for solving these problems by specific considerations in the clearance procedure. The clearance regulations for metal scrap in Germany require adherence to both mass specific and surface related clearance levels in Bq/g and Bq/cm 2 , respectively, which are similar to those as laid down in the EU recommendations RP 89/101. Therefore, approaches had to be developed for inferring sufficiently comprehensive and conservative estimates of the mass and surface related activities for metallic materials forming an integral part of buildings from measurements that do not cover 100% of the material. The ways are outlined in which the

  16. Materials Characterization Center. Second workshop on irradiation effects in nuclear waste forms. Summary report

    International Nuclear Information System (INIS)

    Weber, W.J.; Turcotte, R.P.

    1982-01-01

    The purpose of this second workshop on irradiations effects was to continue the discussions initiated at the first workshop and to obtain guidance for the Materials Characterization Center in developing test methods. The following major conclusions were reached: Ion or neutron irradiations are not substitutes for the actinide-doping technique, as described by the MCC-6 Method for Preparation and Characterization of Actinide-Doped Waste Forms, in the final evaluation of any waste form with respect to the radiation effects from actinide decay. Ion or neutron irradiations may be useful for screening tests or more fundamental studies. The use of these simulation techniques as screening tests for actinide decay requires that a correlation between ion or neutron irradiations and actinide decay be established. Such a correlation has not yet been established and experimental programs in this area are highly recommended. There is a need for more fundamental studies on dose-rate effects, temperature dependence, and the nature and importance of alpha-particle effects relative to the recoil nucleus in actinide decay. There are insufficient data presently available to evaluate the potential for damage from ionizing radiation in nuclear waste forms. No additional test methods were recommended for using ion or neutron irradiations to simulate actinide decay or for testing ionization damage in nuclear waste forms. It was recognized that additional test methods may be required and developed as more data become available. An American Society for Testing and Materials (ASTM) Task Group on the Simulation of Radiation Effects in Nuclear Waste Forms (E 10.08.03) was organized to act as a continuing vehicle for discussions and development of procedures, particularly with regard to ion irradiations

  17. Quantitative model of super-Arrhenian behavior in glass forming materials

    Science.gov (United States)

    Caruthers, J. M.; Medvedev, G. A.

    2018-05-01

    The key feature of glass forming liquids is the super-Arrhenian temperature dependence of the mobility, where the mobility can increase by ten orders of magnitude or more as the temperature is decreased if crystallization does not intervene. A fundamental description of the super-Arrhenian behavior has been developed; specifically, the logarithm of the relaxation time is a linear function of 1 /U¯x , where U¯x is the independently determined excess molar internal energy and B is a material constant. This one-parameter mobility model quantitatively describes data for 21 glass forming materials, which are all the materials where there are sufficient experimental data for analysis. The effect of pressure on the loga mobility is also described using the same U¯x(T ,p ) function determined from the difference between the liquid and crystalline internal energies. It is also shown that B is well correlated with the heat of fusion. The prediction of the B /U¯x model is compared to the Adam and Gibbs 1 /T S¯x model, where the B /U¯x model is significantly better in unifying the full complement of mobility data. The implications of the B /U¯x model for the development of a fundamental description of glass are discussed.

  18. Comparative parametric numerical simulations of materials used as liners in the explosively formed projectiles (EFPs)

    International Nuclear Information System (INIS)

    Hussain, G.; Sanaullah, K.

    2009-01-01

    A conventional shaped charge comprises a conical metal liner projecting a hyper velocity jet of metal that is able to penetrate to great depths into steel armour. However, misalignment problems exist in tandem with jet break up and spewing particles that greatly diminish its penetration power. An EFP, on the other hand, has a liner in the shape of a geometrical recess. The force of the blast molds the liner into a number of configurations, depending on the geometry and the explosive detonation characteristics. This paper presents comparative parametric numerical simulations of materials used as liners in the explosively formed projectiles EFPs. Numerical simulations are carried out using AUTODYN 2D hydrocode to study effects of liner's materials on the shape, velocity, traveled distance, time, pressure, internal energy, temperature, yield stress, divergence or stability, density, compression, and length to diameter (L/D) ratio of EFPs. These parameters are estimated at the instants of maximum as well as at stable velocities. The parametric study reveals that aluminum has maximum velocity in shortest time among the liner materials. From this reason, it was concluded effective standoff was greater for aluminum than more denser metals. Maximum velocity and traveled distance of Tantalum EFP is found to be minimum which may be due to low thermal softening exponent and larger hardening exponent. The simulated yield stress and pressure developed in the Fe EFP reaches at maximum. The L/D ratio for Copper is found to be maximum which supports maximum penetration. From the stability point of view, 1006 MS is found to be the most reliable liner material due to minimum divergence. Generally all liner materials have similar effects of all parameters like pressure, internal energy, temperature, yield stress, divergence or stability, density, compression at the instants of maximum as well as at stable velocities except L/D ratio of EFPs. At the instant of maximum velocity, L

  19. Conditions for forming composite carbon nanotube-diamond like carbon material that retain the good properties of both materials

    Energy Technology Data Exchange (ETDEWEB)

    Ren, Wei, E-mail: wei.ren@helsinki.fi; Avchaciov, Konstantin; Nordlund, Kai [Department of Physics, University of Helsinki, P.O. Box 43, FIN-00014 Helsinki (Finland); Iyer, Ajai; Koskinen, Jari [Department of Materials Science and Engineering, School of Chemical Technology, Aalto University, P.O. Box 16200, 00076 Espoo (Finland); Kaskela, Antti; Kauppinen, Esko I. [NanoMaterials Group, Department of Applied Physics, Aalto University School of Science, P.O. Box 15100, 00076 Aalto (Finland)

    2015-11-21

    Carbon nanotubes are of wide interest due to their excellent properties such as tensile strength and electrical and thermal conductivity, but are not, when placed alone on a substrate, well resistant to mechanical wear. Diamond-like carbon (DLC), on the other hand, is widely used in applications due to its very good wear resistance. Combining the two materials could provide a very durable pure carbon nanomaterial enabling to benefit from the best properties of both carbon allotropes. However, the synthesis of high-quality diamond-like carbon uses energetic plasmas, which can damage the nanotubes. From previous works it is neither clear whether the quality of the tubes remains good after DLC deposition, nor whether the DLC above the tubes retains the high sp{sup 3} bonding fraction. In this work, we use experiments and classical molecular dynamics simulations to study the mechanisms of DLC formation on various carbon nanotube compositions. The results show that high-sp{sup 3}-content DLC can be formed provided the deposition conditions allow for sidewards pressure to form from a substrate close beneath the tubes. Under optimal DLC formation energies of around 40–70 eV, the top two nanotube atom layers are fully destroyed by the plasma deposition, but layers below this can retain their structural integrity.

  20. Plans of reorganization of USA nuclear military complex and provision of military program by special nuclear materials

    International Nuclear Information System (INIS)

    Semenovskaya, I.V.

    1996-01-01

    Consideration is given to plans and implementation of the program of reorganization of USA nuclear military complex, related with conducted reduction of nuclear arsenal after concluding the Strategic Nuclear Armament Reduction Treaty. Particular attention is paid to problems of satisfying short-term and long-term requirements in special nuclear materials and in tritium in particular

  1. Single Point Incremental Forming to increase material knowledge and production flexibility

    International Nuclear Information System (INIS)

    Habraken, A.M.

    2016-01-01

    Nowadays, manufactured pieces can be divided into two groups: mass production and production of low volume number of parts. Within the second group (prototyping or small batch production), an emerging solution relies on Incremental Sheet Forming or ISF. ISF refers to processes where the plastic deformation occurs by repeated contact with a relatively small tool. More specifically, many publications over the past decade investigate Single Point Incremental Forming (SPIF) where the final shape is determined only by the tool movement. This manufacturing process is characterized by the forming of sheets by means of a CNC controlled generic tool stylus, with the sheets clamped by means of a non-workpiece-specific clamping system and in absence of a partial or a full die. The advantage is no tooling requirements and often enhanced formability, however it poses a challenge in term of process control and accuracy assurance. Note that the most commonly used materials in incremental forming are aluminum and steel alloys however other alloys are also used especially for medical industry applications, such as cobalt and chromium alloys, stainless steel and titanium alloys. Some scientists have applied incremental forming on PVC plates and other on sandwich panels composed of propylene with mild steel and aluminum metallic foams with aluminum sheet metal. Micro incremental forming of thin foils has also been developed. Starting from the scattering of the results of Finite Element (FE) simulations, when one tries to predict the tool force (see SPIF benchmark of 2014 Numisheet conference), we will see how SPIF and even micro SPIF (process applied on thin metallic sheet with a few grains within the thickness) allow investigating the material behavior. This lecture will focus on the identification of constitutive laws, on the SPIF forming mechanisms and formability as well as the failure mechanism. Different hypotheses have been proposed to explain SPIF formability, they will be

  2. Single Point Incremental Forming to increase material knowledge and production flexibility

    Science.gov (United States)

    Habraken, A. M.

    2016-08-01

    Nowadays, manufactured pieces can be divided into two groups: mass production and production of low volume number of parts. Within the second group (prototyping or small batch production), an emerging solution relies on Incremental Sheet Forming or ISF. ISF refers to processes where the plastic deformation occurs by repeated contact with a relatively small tool. More specifically, many publications over the past decade investigate Single Point Incremental Forming (SPIF) where the final shape is determined only by the tool movement. This manufacturing process is characterized by the forming of sheets by means of a CNC controlled generic tool stylus, with the sheets clamped by means of a non-workpiece-specific clamping system and in absence of a partial or a full die. The advantage is no tooling requirements and often enhanced formability, however it poses a challenge in term of process control and accuracy assurance. Note that the most commonly used materials in incremental forming are aluminum and steel alloys however other alloys are also used especially for medical industry applications, such as cobalt and chromium alloys, stainless steel and titanium alloys. Some scientists have applied incremental forming on PVC plates and other on sandwich panels composed of propylene with mild steel and aluminum metallic foams with aluminum sheet metal. Micro incremental forming of thin foils has also been developed. Starting from the scattering of the results of Finite Element (FE) simulations, when one tries to predict the tool force (see SPIF benchmark of 2014 Numisheet conference), we will see how SPIF and even micro SPIF (process applied on thin metallic sheet with a few grains within the thickness) allow investigating the material behavior. This lecture will focus on the identification of constitutive laws, on the SPIF forming mechanisms and formability as well as the failure mechanism. Different hypotheses have been proposed to explain SPIF formability, they will be

  3. Cesium release from ceramic waste form materials in simulated canister corrosion product containing solutions

    Energy Technology Data Exchange (ETDEWEB)

    Vittorio, Luca; Drabarek, Elizabeth; Chronis, Harriet; Griffith, Christopher S

    2004-07-01

    It has previously been demonstrated that immobilization of Cs{sup +} and/or Sr{sup 2+} sorbed on hexagonal tungsten oxide bronze (HTB) adsorbent materials can be achieved by heating the materials in air at temperatures in the range 500 - 1300 deg C. Highly crystalline powdered HTB materials formed by heating at 800 deg C show leach characteristics comparable to Cs-containing hot-pressed hollandites in the pH range from 0 to 12. As a very harsh leaching test, and also to model in a basic manner, leaching in the presence of canister corrosion products in oxidising environments, leaching of the bronzoid phases has been undertaken in Fe(NO{sub 3}){sub 3} solutions of increasing concentration. This is done in comparison with Cs -hollandite materials in order to compare the leaching characteristics of these two materials under such conditions. Both the Cs-loaded bronze and hollandite materials leach severely in Fe(NO{sub 3}){sub 3} losing virtually all of the immobilized Cs in a period of four days at 150 deg C. Total release of Cs and conversion of hollandite to titanium and iron titanium oxides begins to be observed at relatively low concentrations and is virtually complete after four days reaction in 0.5 mol/L Fe(NO{sub 3}){sub 3}. In the case of the bronze, all of the Cs is also extracted but the HTB structure is preserved. The reaction presumably involves an ion-exchange mechanism and iron oxide with a spinel structure is also observed at high Fe concentrations. (authors)

  4. Cesium release from ceramic waste form materials in simulated canister corrosion product containing solutions

    International Nuclear Information System (INIS)

    Vittorio, Luca; Drabarek, Elizabeth; Chronis, Harriet; Griffith, Christopher S.

    2004-01-01

    It has previously been demonstrated that immobilization of Cs + and/or Sr 2+ sorbed on hexagonal tungsten oxide bronze (HTB) adsorbent materials can be achieved by heating the materials in air at temperatures in the range 500 - 1300 deg C. Highly crystalline powdered HTB materials formed by heating at 800 deg C show leach characteristics comparable to Cs-containing hot-pressed hollandites in the pH range from 0 to 12. As a very harsh leaching test, and also to model in a basic manner, leaching in the presence of canister corrosion products in oxidising environments, leaching of the bronzoid phases has been undertaken in Fe(NO 3 ) 3 solutions of increasing concentration. This is done in comparison with Cs -hollandite materials in order to compare the leaching characteristics of these two materials under such conditions. Both the Cs-loaded bronze and hollandite materials leach severely in Fe(NO 3 ) 3 losing virtually all of the immobilized Cs in a period of four days at 150 deg C. Total release of Cs and conversion of hollandite to titanium and iron titanium oxides begins to be observed at relatively low concentrations and is virtually complete after four days reaction in 0.5 mol/L Fe(NO 3 ) 3 . In the case of the bronze, all of the Cs is also extracted but the HTB structure is preserved. The reaction presumably involves an ion-exchange mechanism and iron oxide with a spinel structure is also observed at high Fe concentrations. (authors)

  5. Influence of inductive heating on microstructure and material properties in roll forming processes

    Science.gov (United States)

    Guk, Anna; Kunke, Andreas; Kräusel, Verena; Landgrebe, Dirk

    2017-10-01

    The increasing demand for sheet metal parts and profiles with enhanced mechanical properties by using high and ultra-high-strength (UHS) steels for the automotive industry must be covered by increasing flexibility of tools and machines. This can be achieved by applying innovative technologies such as roll forming with integrated inductive heating. This process is similar to indirect press hardening and can be used for the production of hardened profiles and profiles with graded properties in longitudinal and traverse direction. The advantage is that the production of hardened components takes place in a continuous process and the integration of heating and quenching units in the profiling system increases flexibility, accompanied by shortening of the entire process chain and minimizing the springback risk. The features of the mentioned process consists of the combination of inhomogeneous strain distribution over the stripe width by roll forming and inhomogeneity of microstructure by accelerated inductive heating to austenitizing temperature. Therefore, these two features have a direct influence on the mechanical properties of the material during forming and hardening. The aim of this work is the investigation of the influence of heating rates on microstructure evolution and mechanical properties to determine the process window. The results showed that heating rate should be set at 110 K/s for economic integration of inductive heating into the roll forming process.

  6. New ceramic material specially designed to optimise the output of the heating systems; Nuevo material ceramico disenado especificamente para optimizar el rendimiento de los sistemas de calefaccion

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This article sets out the main features of Dual Kherr, its development and uses. Dual Kherr(reg.) is a ceramic composite based on porcelain clay. It has been specially designed to work as a storage heater and a radiant heating system. Jointly developed by the R and D departments of both companies, PAMESA and CLIMASTAR, this new material optimises the output of any heating system and it has been specially conceived to save energy. It is a great revolution, mainly due to the following: On the one hand, Dual Kherr incorporates ceramic to the heating business, opening a new and important market. On the other hand, this new material adds the aesthetics proper of the ceramic material to the design of the heating systems. It even allows the development of artistic collections. (Author)

  7. 77 FR 9298 - Office of Hazardous Materials Safety; Actions on Special Permit Applications

    Science.gov (United States)

    2012-02-16

    ... Lake 173.302(f). special permit Charles, LA. issued on an emergency basis to a permanent special permit... and Space authorize the Administration transportation in (NASA) commerce of certain Washington, DC... Aeronautics & transportation in Space commerce of certain Administration hydrazine fuels on (NASA) the same...

  8. 41 CFR 101-42.404 - Special requirements for the sale of hazardous materials.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Special requirements for... Management Federal Property Management Regulations System FEDERAL PROPERTY MANAGEMENT REGULATIONS UTILIZATION... special storage and handling. It is the responsibility of the holding agency to properly store hazardous...

  9. 77 FR 23803 - Office of Hazardous Materials Safety; Actions on Special Permit Applications

    Science.gov (United States)

    2012-04-20

    ...-M......... Conference of 49 CFR To modify the Radiation 172.203(d); special permit add Control Part............ Conference of 49 CFR Part To modify the Radiation 172, Subparts, special permit add Control C, D, E, F, G, 49...; additional mode of Berlin 173.345; transportation Packaging 173.346; (cargo vessel). (Former 173.359; Grantee...

  10. 75 FR 43898 - Hazardous Materials Transportation: Revisions of Special Permits Procedures

    Science.gov (United States)

    2010-07-27

    .... The HMR generally are performance-oriented regulations that provide the regulated community with a... aircraft except under a special permit (see Columns 9A and 9B in the table in 49 CFR 172.101), an applicant... forbidden for transportation by aircraft except under a special permit (see Columns 9A and 9B in the table...

  11. STUDY ON THE USAGE OF SPECIAL MATERIALS FOR HIGH-STRENGTH PARTS USED IN THE MACHINES MANUFACTURING INDUSTRY

    Directory of Open Access Journals (Sweden)

    BIBU Marius

    2016-09-01

    Full Text Available Whereas formerly metallic materials were used extensively and for various purposes in the machines manufacturing industry, nowadays new materials are sought that can replace the "conventional" machines manufacturing materials with new ones. This is especially challenging in areas where parts need to be able to withstand very tough conditions, such as high temperatures or large forces applied to them. The current paper intends to analyze some of the most widely used materials for high-strength applications. A special focus in this regard is on the one hand in fiber-reinforced composite materials with the polymer matrix and on the other hand on basalt. The most important properties, processing technologies and applications of these materials are analyzed and discussed and conclusions are drawn regarding their compatibility with the intended purpose.

  12. [Care and specialized clinical follow-up of nursing professionals who have been victims of accidents with biological material].

    Science.gov (United States)

    Pimenta, Flaviana Regina; Ferreira, Milene Dias; Gir, Elucir; Hayashida, Miyeko; Canini, Silvia Rita Marin da Silva

    2013-02-01

    This cross-sectional study aimed to evaluate the conduct of nursing professionals who had been victims of accidents with biological material in a teaching hospital in the interior of the state of São Paulo, Brazil, regarding their care and specialized clinical follow-up. The study population consisted of 1,215 nursing professionals, who were interviewed individually between 2010 and 2011. Of the 1,215 nursing professionals interviewed, 636 (52.3%) reported having experienced accidents with biological material; of this population, 182 (28.6%) didn't sought specialized care. The most frequent reason reported for not seeking care was believing that it was a low-risk accident. The reasons professionals do not seek care and do not complete treatment and the clinical follow-up can contribute to strategies to increase professionals' adherence to prophylaxis measures after occupational exposure to biological material.

  13. Relationship of soil potassium forms with maize potassium contents in soils derived from different parent materials

    Directory of Open Access Journals (Sweden)

    Rashid Mehmood Butt

    2017-06-01

    Full Text Available Understanding of soil potassium (K dynamics is essential for sustainable crop production. Bioavailability of K depends on forms and distribution within the soil profile. The objectives of this research were to determine which soil K forms control the maize (Zea mays K contents and compare the extracting capability of sodium tetraphenylborate (NaTPB with ammonium acetate (NH4OAc method. Nine soils representing three different parent materials, i.e. loess, sandstone and shale were sampled at three surface genetic horizons. Within each parent material, three soils at varying level of development were selected. Besides basic soil parameters, K was fractioned into water soluble K, exchangeable K, non-exchangeable K, and NaTPB-extracted K. The maize was sown in pots having 2 kg soil from each genetic horizon. Crop was harvested at seven weeks and plant was analysed for K contents. Results show that NaTPB-extracted K gave best correlation as compared to NH4OAc method. This conveys that a non-exchangeable K portion that becomes available to plants can be better estimated by NaTPB method than NH4OAc extraction.

  14. Recent progresses and achievements in photovoltaic-phase change material technology: A review with special treatment on photovoltaic thermal-phase change material systems

    International Nuclear Information System (INIS)

    Islam, M.M.; Pandey, A.K.; Hasanuzzaman, M.; Rahim, N.A.

    2016-01-01

    Highlights: • Broad summary of phase change materials based cooling for photovoltaic modules. • Compendium on phase change materials that are mostly used in photovoltaic systems. • Extension of heat availability period by 75–100% with phase change material. • Heat storage potential improves by 33–50% more with phase change material. • Future trend and move in photovoltaic thermal research. - Abstract: This communication lays out an appraisal on the recent works of phase change materials based thermal management techniques for photovoltaic systems with special focus on the so called photovoltaic thermal-phase change material system. Attempt has also been made to draw wide-ranging classification of both photovoltaic and photovoltaic thermal systems and their conventional cooling or heat harvesting methods developed so far so that feasible phase change materials application area in these systems can be pointed out. In addition, a brief literature on phase change materials with particular focus on their solar application has also been presented. Overview of the researches and studies establish that using phase change materials for photovoltaic thermal control is technically viable if some issues like thermal conductivity or phase stability are properly addressed. The photovoltaic thermal-phase change material systems are found to offer 33% (maximum 50%) more heat storage potential than the conventional photovoltaic-thermal water system and that with 75–100% extended heat availability period and around 9% escalation in output. Reduction in temperature attained with photovoltaic thermal-phase change material system is better than that with regular photovoltaic-thermal water system, too. Studies also show the potential of another emerging technology of photovoltaic thermal-microencapsulated phase change material system that makes use of microencapsulated phase change materials in thermal regulation. Future focus areas on photovoltaic thermal-phase change

  15. The Study on the analysis of the revised regulation on the special nuclear materials

    International Nuclear Information System (INIS)

    Ahn, Seung Ho; Koh, Byung Marn; Kim, Ki Hyun

    2015-01-01

    In accordance with successful implementation of the IS in the ROK, the IAEA request the enhanced partnership between the ROK and the IAEA to increase the role of the SSAC(State System of Accounting for and Control of nuclear material) in the ROK. For this reason, the ROK and the IAEA signed the EC(Enhanced Cooperation) arrangement to expand the cooperation area beyond existing LWR enhanced cooperation. The IAEA set up it the one of the EC's objectives to increase the practical use and enhancement of the SSAC. In 2013, the NSSC(Nuclear Safety and Security Committee) formed task force team which included the TSO(Technical Support Organization) staffs and operators to establish scope, object and role of the SSAC for improving it. The improvement of the state safeguards system envisioned in the amendment to the notification is intended to ensure the integrity of the state safeguards with the agreement reached with the IAEA to enhance cooperation, enable facility operators to ensure compliance with their obligatory requirements without assuming unnecessarily duplicate administrative workload, and eliminate unreasonableness of the state accounting and control inspection

  16. The Study on the analysis of the revised regulation on the special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Seung Ho; Koh, Byung Marn; Kim, Ki Hyun [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    In accordance with successful implementation of the IS in the ROK, the IAEA request the enhanced partnership between the ROK and the IAEA to increase the role of the SSAC(State System of Accounting for and Control of nuclear material) in the ROK. For this reason, the ROK and the IAEA signed the EC(Enhanced Cooperation) arrangement to expand the cooperation area beyond existing LWR enhanced cooperation. The IAEA set up it the one of the EC's objectives to increase the practical use and enhancement of the SSAC. In 2013, the NSSC(Nuclear Safety and Security Committee) formed task force team which included the TSO(Technical Support Organization) staffs and operators to establish scope, object and role of the SSAC for improving it. The improvement of the state safeguards system envisioned in the amendment to the notification is intended to ensure the integrity of the state safeguards with the agreement reached with the IAEA to enhance cooperation, enable facility operators to ensure compliance with their obligatory requirements without assuming unnecessarily duplicate administrative workload, and eliminate unreasonableness of the state accounting and control inspection.

  17. Microstructural Characterization of Reaction-Formed Silicon Carbide Ceramics. Materials Characterization

    Science.gov (United States)

    Singh, M.; Leonhardt, T. A.

    1995-01-01

    Microstructural characterization of two reaction-formed silicon carbide ceramics has been carried out by interference layering, plasma etching, and microscopy. These specimens contained free silicon and niobium disilicide as minor phases with silicon carbide as the major phase. In conventionally prepared samples, the niobium disilicide cannot be distinguished from silicon in optical micrographs. After interference layering, all phases are clearly distinguishable. Back scattered electron (BSE) imaging and energy dispersive spectrometry (EDS) confirmed the results obtained by interference layering. Plasma etching with CF4 plus 4% O2 selectively attacks silicon in these specimens. It is demonstrated that interference layering and plasma etching are very useful techniques in the phase identification and microstructural characterization of multiphase ceramic materials.

  18. Radiation Field Forming for Industrial Electron Accelerators Using Rare-Earth Magnetic Materials

    Science.gov (United States)

    Ermakov, A. N.; Khankin, V. V.; Shvedunov, N. V.; Shvedunov, V. I.; Yurov, D. S.

    2016-09-01

    The article describes the radiation field forming system for industrial electron accelerators, which would have uniform distribution of linear charge density at the surface of an item being irradiated perpendicular to the direction of its motion. Its main element is non-linear quadrupole lens made with the use of rare-earth magnetic materials. The proposed system has a number of advantages over traditional beam scanning systems that use electromagnets, including easier product irradiation planning, lower instantaneous local dose rate, smaller size, lower cost. Provided are the calculation results for a 10 MeV industrial electron accelerator, as well as measurement results for current distribution in the prototype build based on calculations.

  19. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP Facility

    International Nuclear Information System (INIS)

    Goldberg, H.J.

    1998-01-01

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility. To internally check the accuracy and sensitivity of the NDA instruments, a further set of sources and standards will also be used by the facility. Each sealed source or standard will be referred to herein as a unit. Various combinations of these units will be placed in test drums and/or boxes which will be subject to their own limits until unloaded. There will be two sealed test drums with five grams of weapons grade plutonium loaded in them. These drums will be appropriately marked and will be subject to the unit limits rather than the drum limits. This analysis shows that the storage and use of special nuclear material sources and standards within the limited control facility of WRAP (Rooms 101 and 104) is safe from a criticality standpoint. With the form, geometry, and masses involved with this evaluation, a criticality is not possible. The limits given in Section 2 should be imposed on facility operations

  20. Study on metal material corrosion behavior of packaging of cement solidified form

    International Nuclear Information System (INIS)

    He Zhouguo; Lin Meiqiong; Fan Xianhua

    1997-01-01

    The corrosion behavior of A3 carbon steel is studied by the specimens that are exposed to atmosphere, embedded in cement solidified form or immersed in corrosion liquid. The corrosion rate is determined by mass change of the specimens. In order to compare the corrosion resistant performance of various coatings, the specimens painted with various material such as epoxide resin, propionic acid resin, propane ether resin and Ti-white paint are tested. The results of the tests show that corrosion rate of A3 carbon steel is less than 10 -3 mm·a -1 in the atmosphere and the cement solidified from, less than 0.1 mm·a -1 in the corrosion liquids, and pH value in the corrosion liquids also affect the corrosion rate of A3 carbon steel. The corrosion resistant performance of Ti-white paint is better than that of other paints. So, A3 carbon steel as packaging material can meet the requirements during storage

  1. Performance evaluation of a commercially available heat flow calorimeter and applicability assessment for safeguarding special nuclear materials

    International Nuclear Information System (INIS)

    Bracken, D.S.; Biddle, R.; Rudy, C.

    1998-01-01

    The performance characteristics of a commercially available heat-flow calorimeter will be presented. The heat-flow sensors within the calorimeter are based on thermopile technology with a vendor-quoted sensitivity of 150 microV/mW. The calorimeter is a full-twin design to compensate for ambient temperature fluctuations. The efficacy of temperature fluctuation compensations will also be detailed. Finally, an assessment of design applicability to special nuclear materials control and accountability and safeguarding will be presented

  2. Environmental-impact appraisal related to special nuclear materials. License No. SNM-696; Docket No. 70-734

    International Nuclear Information System (INIS)

    1983-06-01

    This Environmental Impact Appraisal is issued by the US Nuclear Regulatory Commission in response to an application by GA Technologies, Inc., (GA) for renewal of Special Nuclear Material (SNM) License No. SNM-696 covering plant operations at San Diego, California. The proposed action provides for continuing research, development, and production activities involving SNM, uranium enriched in the U-235 and U-233 isotopes, and plutonium

  3. Materials Characterization Center workshop on leaching of radioactive waste forms. Summary report

    International Nuclear Information System (INIS)

    Ross, W.A.; Strachan, D.M.; Turcotte, R.P.; Westsik, J.H. Jr.

    1980-04-01

    At the first Materials Characterization Center (MCC) workshop, on the leaching of radioactive waste forms, there was general agreement that, after certain revisions, the proposed leach test plan set forth by the MCC can be expected to meet most of the nuclear waste community's waste form durability data requirements. The revisions give a clearer definition of the purposes of each test and the end uses of the data. As a result of the workshop, the format of the test program has been recast to clarify the purposes, limitations, and interrelationships of the individual tests. There was also a recognition that the leach test program must be based on an understanding of the mechanistic principles of leaching, and that further study is needed to ensure that the approved data from the MCC leach tests will be compatible with mechanistic research needs. It was agreed that another meeting of the participants in Working Groups 3 and 4, and perhaps some other experts, should be held as soon as possible to focus just on the definition of leach test requirements for mechanistic research. The MCC plans to hold this meeting in April 1980. Many of the tests that will lead to increased understanding of mechanisms will of necessity be long-term tests, sometimes lasting for several years. But the MCC also faces pressing needs to produce approved data that can be used for the comparison of waste forms in the relative near-term, i.e., in the next 1 to 3 yr. Therefore, it was decided to initiate a round-robin test of the MCC short-term static leach procedure as soon as practicable. The MCC has tentative plans for organization of the round robin in May 1980

  4. Material characterization and finite element simulations of aluminum alloy sheets during non-isothermal forming process

    Science.gov (United States)

    Zhang, Nan

    The utilization of more non-ferrous materials is one of the key factors to succeed out of the constantly increasing demand for lightweight vehicles in automotive sector. Aluminum-magnesium alloys have been identified as the most promising substitutions to the conventional steel without significant compromise in structural stiffness and strength. However, the conventional forming methods to deform the aluminum alloy sheets are either costly or insufficient in formability which limit the wide applications of aluminum alloy sheets. A recently proposed non-isothermal hot stamping approach, which is also referred as Hot Blank - Cold Die (HB-CD) stamping, aims at fitting the commercial grade aluminum alloy sheets, such as AA5XXX and AA7XXX, into high-volume and cost-effective production for automotive sector. In essence, HB-CD is a mutation of the conventional hot stamping approach for boron steel (22MnB5) which deforms the hot blank within the cold tool set. By elevating the operation temperature, the formability of aluminum alloy sheets can be significantly improved. Meanwhile, heating the blank only and deforming within the cold tool sets allow to reduce the energy and time consumed. This research work aims at conducting a comprehensive investigation of HB-CD with particular focuses on material characterization, constitutive modeling and coupled thermo-mechanical finite element simulations with validation. The material properties of AA5182-O, a popular commercial grade of aluminum alloy sheet in automotive sector, are obtained through isothermal tensile testing at temperatures from 25° to 300°, covering a quasi-static strain-rate range (0.001--0.1s-1). As the state-of-the-art non-contact strain measurement technique, digital image correlation (DIC) system is utilized to evaluate the stress-strain curves as well as to reveal the details of material deformation with full-field and multi-axis strain measurement. Material anisotropy is characterized by extracting the

  5. In-Drift Accumulation of Fissile Material From Waste Packages Containing Plutonium Disposition Waste Forms

    International Nuclear Information System (INIS)

    H.W. Stockman; S. LeStrange

    2000-01-01

    The objective of this calculation is to provide estimates of the amount of fissile material flowing out of the waste package (source term) and the accumulation of fissile elements (U and Pu) in a crushed-tuff invert. These calculations provide input for the analysis of repository impacts of the Pu-ceramic waste forms. In particular, the source term results are used as input to the far-field accumulation calculation reported in Ref. 51, and the in-drift accumulation results are used as inputs for the criticality calculations reported in Ref. 2. The results are also summarized and interpreted in Ref. 52. The scope of this calculation is the waste package (WP) Viability Assessment (VA) design, which consists of an outer corrosion-allowance material (CAM) and an inner corrosion-resistant material (CRM). This design is used in this calculation in order to be consistent with earlier Pu-ceramic degradation calculations (Ref. 15). The impact of the new Enhanced Design Alternative-I1 (EDA-11) design on the results will be addressed in a subsequent report. The design of the invert (a leveling foundation, which creates a level surface of the drift floor and supports the WP mounting structure) is consistent with the EDA-I1 design. The invert will be composed of crushed stone and a steel support structure (Ref. 17). The scope of this calculation is also defined by the nominal degradation scenario, which involves the breach of the WP (Section 10.5.1.2, Ref. 48), followed by the influx of water. Water in the WP may, in time, gradually leach the fissile components and neutron absorbers out of the ceramic waste forms. Thus, the water in the WP may become laden with dissolved actinides (e.g., Pu and U), and may eventually overflow or leak from the WP. Once the water leaves the WP, it may encounter the invert, in which the actinides may reprecipitate. Several factors could induce reprecipitation; these factors include: the high surface area of the crushed stone, and the presence of

  6. In-Drift Accumulation of Fissile Material From Waste Packages Containing Plutonium Disposition Waste Form

    Energy Technology Data Exchange (ETDEWEB)

    H.W> Stockman; S. LeStrange

    2000-09-28

    The objective of this calculation is to provide estimates of the amount of fissile material flowing out of the waste package (source term) and the accumulation of fissile elements (U and Pu) in a crushed-tuff invert. These calculations provide input for the analysis of repository impacts of the Pu-ceramic waste forms. In particular, the source term results are used as input to the far-field accumulation calculation reported in Ref. 51, and the in-drift accumulation results are used as inputs for the criticality calculations reported in Ref. 2. The results are also summarized and interpreted in Ref. 52. The scope of this calculation is the waste package (WP) Viability Assessment (VA) design, which consists of an outer corrosion-allowance material (CAM) and an inner corrosion-resistant material (CRM). This design is used in this calculation in order to be consistent with earlier Pu-ceramic degradation calculations (Ref. 15). The impact of the new Enhanced Design Alternative-I1 (EDA-11) design on the results will be addressed in a subsequent report. The design of the invert (a leveling foundation, which creates a level surface of the drift floor and supports the WP mounting structure) is consistent with the EDA-I1 design. The invert will be composed of crushed stone and a steel support structure (Ref. 17). The scope of this calculation is also defined by the nominal degradation scenario, which involves the breach of the WP (Section 10.5.1.2, Ref. 48), followed by the influx of water. Water in the WP may, in time, gradually leach the fissile components and neutron absorbers out of the ceramic waste forms. Thus, the water in the WP may become laden with dissolved actinides (e.g., Pu and U), and may eventually overflow or leak from the WP. Once the water leaves the WP, it may encounter the invert, in which the actinides may reprecipitate. Several factors could induce reprecipitation; these factors include: the high surface area of the crushed stone, and the presence of

  7. A real-time material control concept for safeguarding special nuclear material in United States licensed processing facilities

    International Nuclear Information System (INIS)

    Shea, T.E.

    1976-01-01

    This paper describes general safeguards research being undertaken by the United States Nuclear Regulatory Commission. Efforts to improve the ability of United States licensed plants to contend with the perceived threat of covert material theft are emphasized. The framework for this improvement is to break down the internal control and accounting system into subsystems to achieve material isolation, inventory control, inventory characterization, and inventory containment analysis. A general programme is outlined to develop and evaluate appropriate mechanisms, integrate selected mechanisms into subsystems, and evaluate the subsystems in the context of policy requirements. (author)

  8. 77 FR 64450 - Hazardous Materials: Incorporation of Certain Special Permits and Competent Authorities Into...

    Science.gov (United States)

    2012-10-22

    ... posted without change to the Federal Docket Management System (FDMS), including any personal information.... Transportation of solid coal tar pitch compounds. Transportation of certain ammonia solutions in UN1H1 and UN6HA1... production and the transportation stream. Thus, special permits provide a mechanism for testing new...

  9. 41 CFR 101-42.304 - Special requirements for donation of certain hazardous materials.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Special requirements for... Management Federal Property Management Regulations System FEDERAL PROPERTY MANAGEMENT REGULATIONS UTILIZATION... is the responsibility of the Federal holding agency or State agency to properly store hazardous...

  10. Physical protection of special nuclear material in the commercial fuel cycle. Volume I. Executive summary

    International Nuclear Information System (INIS)

    1976-04-01

    This is the summary of the work and recommendations resulting from Sandia's participation in the Special Safeguards Study, which covered three areas: protection of SNM at fixed facilities, protection of SNM while in transit, and relocation and recovery of lost SNM. The results are published in full in five other volumes. 6 tables, 4 fig

  11. 77 FR 71031 - Office of Hazardous Materials Safety; Actions on Special Permit Applications

    Science.gov (United States)

    2012-11-28

    ...-Mart Stores, Inc. 49 CFR part 172, part To authorize the one-time, Bentonville, AR. 173 and part 177...- impaired retail stores impacted by Hurricane Sandy to a temporary warehousing facility for approximately 10... Request by EQ Industrial Services, Inc. Ypsilanti, MI October 4, 2012. To modify the special permit to...

  12. Annotated bibliography of methods for determining sulfur and forms of sulfur in coal and coal-related materials

    Energy Technology Data Exchange (ETDEWEB)

    Chriswell, C.D.; Norton, G.A.; Akhtar, S.S.; Straszheim, W.E.; Markuszewski, R.

    1993-01-01

    Over 400 published papers, presentations at scientific meetings, and reports relating to the determination of sulfur and sulfur forms in coal-related materials have been accumulated, classified, and an evaluation made of their content.

  13. Instructional Modules for Training Special Education Teachers: A Final Report on the Development and Field Testing of the CUNY-CBTEP Special Education Modules. Case 30-76. Toward Competence Instructional Materials for Teacher Education.

    Science.gov (United States)

    City Univ. of New York, NY. Center for Advanced Study in Education.

    The City University of New York Competency Based Teacher Education Project (CUNY-CBTEP) in Special Education studied Modularization, focusing on the variables in the instructional setting that facilitate learning from modular materials for a wide range of students. Four of the five modules for the training of special education teachers developed…

  14. Differentiating pedogenesis from diagenesis in early terrestrial paleoweathering surfaces formed on granitic composition parent materials

    Science.gov (United States)

    Driese, S.G.; Medaris, L.G.; Ren, M.; Runkel, Anthony C.; Langford, R.P.

    2007-01-01

    Unconformable surfaces separating Precambrian crystalline basement and overlying Proterozoic to Cambrian sedimentary rocks provide an exceptional opportunity to examine the role of primitive soil ecosystems in weathering and resultant formation of saprolite (weathered rock retaining rock structure) and regolith (weathered rock without rock structure), but many appear to have been affected by burial diagenesis and hydrothermal fluid flow, leading some researchers to discount their suitability for such studies. We examine one modern weathering profile (Cecil series), four Cambrian paleoweathering profiles from the North American craton (Squaw Creek, Franklin Mountains, Core SQ-8, and Core 4), one Neoproterozoic profile (Sheigra), and one late Paleoproterozoic profile (Baraboo), to test the hypothesis that these paleoweathering profiles do provide evidence of primitive terrestrial weathering despite their diagenetic and hydrothermal overprinting, especially additions of potassium. We employ an integrated approach using (1) detailed thin-section investigations to identify characteristic pedogenic features associated with saprolitization and formation of well-drained regoliths, (2) electron microprobe analysis to identify specific weathered and new mineral phases, and (3) geochemical mass balance techniques to characterize volume changes during weathering and elemental gains and losses of major and minor elements relative to the inferred parent materials. There is strong pedogenic evidence of paleoweathering, such as clay illuviation, sepic-plasmic fabrics, redoximorphic features, and dissolution and alteration of feldspars and mafic minerals to kaolinite, gibbsite, and Fe oxides, as well as geochemical evidence, such as whole-rock losses of Na, Ca, Mg, Si, Sr, Fe, and Mn greater than in modern profiles. Evidence of diagenesis includes net additions of K, Ba, and Rb determined through geochemical mass balance, K-feldspar overgrowths in overlying sandstone sections, and

  15. Analysis of alternative transportation methods for radioactive materials shipments including the use of special trains for spent fuel and wastes

    International Nuclear Information System (INIS)

    Smith, D.R.; Luna, R.E.; Taylor, J.M.

    1978-01-01

    Two studies were completed which evaluate the environmental impact of radioactive material transport. The first was a generic study which evaluated all radioactive materials and all transportation modes; the second addressed spent fuel and fuel-cycle wastes shipped by truck, rail and barge. A portion of each of those studies dealing with the change in impact resulting from alternative shipping methods is presented in this paper. Alternatives evaluated in each study were mode shifts, operational constraints, and, in generic case, changes in material properties and package capabilities. Data for the analyses were obtained from a shipper survey and from projections of shipments that would occur in an equilibrium fuel cycle supporting one hundred 1000-MW(e) reactors. Population exposures were deduced from point source radiation formulae using separation distances derived for scenarios appropriate to each shipping mode and to each exposed population group. Fourteen alternatives were investigated for the generic impact case. All showed relatively minor changes in the overall radiological impact. Since the radioactive material transport is estimated to be fewer than 3 latent cancer fatalities (LCF) for each shipment year (compared to some 300,000 yearly cancer fatalities or 5000 LCF's calculated for background radiation using the same radiological effects model), a 15% decrease caused by shifting from passenger air to cargo air is a relatively small effect. Eleven alternatives were considered for the fuel cycle/special train study, but only one produced a reduction in total special train baseline LCF's (.047) that was larger than 5%

  16. K-α emission form medium and high-Z materials irradiated by femtosecond laser pulses

    International Nuclear Information System (INIS)

    Limpouch, J.; Klimo, O.; Zhavoronkov, N.; Andreev, A.A.

    2006-01-01

    Complete test of publication follows. Fast electrons are created at the target surface during the interaction of high intensity ultra short laser pulses with solids. Fast electrons penetrate deep into the target where they generate K-α and Bremsstrahlung radiation. Generated high brightness K-α pulses offer the prospect of creating a cheap and compact X-ray source, posing a promising alternative to synchrotron radiation, e.g. in medical application and in material science. With an increase in laser intensity, efficient X-ray emission in the multi-keV range with pulse duration shorter than few picoseconds is expected. This short incoherent but monochromatic X-ray emission synchronized with laser pulses may be used for time-resolved measurements. Acceleration of fast electrons, their transport and K-α photon generation and emission from the target surface in both forward and backward directions are studied here numerically. The results are compared to recent experiments studying K-α emission from the front and rear surface of copper foil targets of various thicknesses and for various parameters of the laser plasma interaction. One-dimensional PIC simulations coupled with 3D time-resolved Monte Carlo simulations show that account of ionization processes and of density profile formed by laser ASE emission is essential for reliable explanation of experimental data. While sub-relativistic intensities are optimum for laser energy transformation into K-α emission for medium-Z targets, relativistic laser intensities have to be used for hard X-ray generation in high-Z materials. The cross-section for K-α shell ionization of high-Z elements by electrons increases or remains approximately constant within a factor of two at relativistic electron energies up to electron energies in the 100-MeV range. Moreover, the splitting ratio of K-α photon emission to Auger electron emission is favorable for high-Z materials, and thus efficient K-α emission is possible. In our

  17. Statues of the study on the irradiated materials by a special capsule in HANARO

    International Nuclear Information System (INIS)

    Kang, Y.-H.; Kim, B.-G.; Cho, M.-S.; Choi, Y.

    2005-01-01

    A special capsule installed with multi-specimens for HANARO has been designed and its parts were fabricated based on the design criteria of sustaining it at the working conditions of 20 n/cm 2 of a fast neutron fluence with energies above 1 MeV and a maximum load of 200 MPa. The special capsule consists of four modules which work independently. Two of them are located in the upper part of the machine and the others are located in the lower part with a 90 degree rotation. Each module has three separate chambers, each of which contains a loading system, various measuring and controlling units. Each module was evaluated by determining the load-displacement curve of four zirconium specimens. Reliable load-displacement curves of the four specimens were obtained by a simultaneous loading at a controlled temperature. (authors)

  18. A Characterization of the Ship-Effect in a Maritime Environment and Special Nuclear Material Detection

    Science.gov (United States)

    2015-05-18

    physics where cosmic radiation interacts preferentially with high atomic number materials to produce additional background radiation. This research...physics where cosmic radiation interacts preferentially with high atomic number materials to produce additional background radiation. A classic...LTC Michael Shannon, Director, J9-NSERC, Defense Threat Reduction Agency IV Table of Contents Abstract

  19. A survey of infrared technology for special nuclear materials control and accounting

    International Nuclear Information System (INIS)

    Stanbro, W.D.; Leonard, R.S.; Steverson, C.A.; Angerman, M.I.

    1992-03-01

    This report reviews some aspects of current infrared measurement technology and suggests two applications in which it may be used in nuclear safeguards. These applications include both materials control and materials accounting. In each case, the measurements rely on passive detection of infrared radiation generated from the heat produced by the radioactive decay of plutonium. Both imaging and non-imaging techniques are discussed

  20. Technical appendix for the special safeguards study on material control and accounting systems. Final report

    International Nuclear Information System (INIS)

    1975-01-01

    The appendixes contain information on alarm levels for detection of theft, computer simulation of theft detection capabilities, benefits and liabilities related to real-time material control, cost analysis, and impact of collocated facilities on the real-time material control concept

  1. Project Plan For Remove Special Nuclear Material (SNM) from Plutonium Finishing Plant (PFP) Project

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SNM Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617. This project plan is the top-level definitive project management document for the PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baseline to manage the execution of the Remove SNM Materials project. Any deviation to the document must be authorized through the appropriate change control process. The Remove SNM Materials project provides the necessary support and controls required for DOE-HQ, DOE-RL, BWHC, and other DOE Complex Contractors the path forward to negotiate shipped/receiver agreements, schedule shipments, and transfer material out of PFP to enable final deactivation

  2. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network

    Energy Technology Data Exchange (ETDEWEB)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-01-01

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  3. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network

    Energy Technology Data Exchange (ETDEWEB)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-10-28

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  4. Locating sensors for detecting source-to-target patterns of special nuclear material smuggling: a spatial information theoretic approach.

    Science.gov (United States)

    Przybyla, Jay; Taylor, Jeffrey; Zhou, Xuesong

    2010-01-01

    In this paper, a spatial information-theoretic model is proposed to locate sensors for detecting source-to-target patterns of special nuclear material (SNM) smuggling. In order to ship the nuclear materials from a source location with SNM production to a target city, the smugglers must employ global and domestic logistics systems. This paper focuses on locating a limited set of fixed and mobile radiation sensors in a transportation network, with the intent to maximize the expected information gain and minimize the estimation error for the subsequent nuclear material detection stage. A Kalman filtering-based framework is adapted to assist the decision-maker in quantifying the network-wide information gain and SNM flow estimation accuracy.

  5. Standard guide for application of radiation monitors to the control and physical security of special nuclear material

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms

  6. Standard guide for application of radiation monitors to the control and physical security of special nuclear material

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

  7. Locating Sensors for Detecting Source-to-Target Patterns of Special Nuclear Material Smuggling: A Spatial Information Theoretic Approach

    Directory of Open Access Journals (Sweden)

    Xuesong Zhou

    2010-08-01

    Full Text Available In this paper, a spatial information-theoretic model is proposed to locate sensors for detecting source-to-target patterns of special nuclear material (SNM smuggling. In order to ship the nuclear materials from a source location with SNM production to a target city, the smugglers must employ global and domestic logistics systems. This paper focuses on locating a limited set of fixed and mobile radiation sensors in a transportation network, with the intent to maximize the expected information gain and minimize the estimation error for the subsequent nuclear material detection stage. A Kalman filtering-based framework is adapted to assist the decision-maker in quantifying the network-wide information gain and SNM flow estimation accuracy.

  8. Spanish experiences with marginal and special materials on the construction of road embankments

    International Nuclear Information System (INIS)

    Cano Linares, H.; Perucho Martinez, A.

    2015-01-01

    The use of existing materials along the alignment of a road is an essential problem within the Sustainable Development policies, which is being promoting worldwide since a long time. In the Word road Association (PIARC-AIPCR) this subject has being investigated by different Technical Committees during last decades. Additionally, the review of the article 330 Embankment of PG-3 (FOM 1382/2002) has opened the door to new non-conventional materials, as wastes and artificial materials, to be used on embankments. This could come to adequate solutions, technically, and environmentally, contributing with national legislation on valorisation policies. In this sense, the use of marginal materials and wastes con represent and important save on natural resources and dumping sites. In Spain, some experiences with marginal materials and wastes have being carried out. The work presented has consisted in compiling and analysing the experiences executed with marginal materials and wastes on Spanish road embankments. Although there are many other cases, 24 cases published with adequate information have being analysed, summarising aspects as: materials problems arrangement solutions or treatments employed. Analysing these experiences and making them public can be a way to transmit confidence, help to improve knowledge, and progress on the preparation of recommendations. This work has being carried out on the frame of the Project Geotechnical Engineering, Materials and Structures and Impact of Infrastructure in Civil engineering (TTIGEM), within the frame Program Border Cooperation Spain-External Borders (POCTEFEX); particularly in the Activity 2 related to Technology Transfer of Construction Materials, including marginal materials and wastes. (Author)

  9. Method for making a low density polyethylene waste form for safe disposal of low level radioactive material

    Science.gov (United States)

    Colombo, P.; Kalb, P.D.

    1984-06-05

    In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.

  10. Frontiers of ferroelectricity a special issue of the journal of materials science

    CERN Document Server

    Lang, Sidney B

    2007-01-01

    The book presents theory, fundamentals and some applications of ferroelectricy. The 24 chapters comprise reviews and research reports covering the spectrum of ferroelectricity. It is intended to describe the current levels of understanding of various aspects of ferroelectricity as presented by authorities in the field. Topics include relaxors, piezoelectrics, microscale and nanoscale studies, polymers and composites, unusual properties, and techniques and devices. The information in this book is intended for physicists, engineers and materials scientists working with ferroelectric materials including ceramics, single crystals, polymers, composites and even some biological materials.

  11. Savannah River Site's H-Canyon Facility: Impacts of Foreign Obligations on Special Nuclear Material Disposition

    International Nuclear Information System (INIS)

    Magoulas, Virginia

    2013-01-01

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These ''123 agreements'' are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  12. Elemental analysis of biological materials. Current problems and techniques with special reference to trace elements

    International Nuclear Information System (INIS)

    1980-01-01

    Selected techniques were reviewed for the assay of trace and minor elements in biological materials. Other relevant information is also presented on the need for such analyses, sampling, sample preparation and analytical quality control. In order to evaluate and compare the applicability of the various analytical techniques on a meaningful and objective basis, the materials chosen for consideration were intended to be typical of a wide range of biological matrics of different elemental compositions, namely Bowen's kale, representing a plant material, and NBS bovine liver, IAEA animal muscle, and blood serum, representing animal tissues. The subject is reviewed under the following headings: on the need for trace element analyses in the life sciences (4 papers); sampling and sample preparation for trace element analysis (2 papers); analytical techniques for trace and minor elements in biological materials (7 papers); analytical quality control (2 papers)

  13. Special quasirandom structures for gadolinia-doped ceria and related materials

    KAUST Repository

    Wang, Hao; Chroneos, Alexander I.; Jiang, Chao; Schwingenschlö gl, Udo

    2012-01-01

    cells describing 9% and 12% gadolinia doped ceria. These SQS cells are transferable and can be used to model related materials such as yttria stabilized zirconia. To demonstrate the applicability of the method we use density functional theory

  14. 76 FR 34273 - Environmental Assessment and Finding of No Significant Impact for Special Nuclear Material...

    Science.gov (United States)

    2011-06-13

    ... Nuclear Material, TVA applied for an SNM license by application dated November 12, 2009 (ML100120487). The..., including site geography, demographics, meteorology, hydrology, and geology. The proposed activity is...

  15. Assessing Worker Exposures during Composite Material and Fiberglass Repair: A Special

    Science.gov (United States)

    2015-01-01

    OEEL, without regard to the use of respirators, shall have shower facilities or other suitable decontamination available [32]. 6.4.2 Dust Removal...use mechanically fastened aluminum or stainless steel patches to repair composite material damage, or repair the composite material damage using...world CBRN environment. If the vacuum mechanism of ventilated tools becomes contaminated with radioactive particulates or chemical/biological agents

  16. Radiolysis in cement-based materials ; application to radioactive waste-forms

    International Nuclear Information System (INIS)

    Bouniol, P.

    2014-01-01

    Cement-based materials appear to be an original environment with respect to radiolysis, due to their intrinsic complexity (porous, multiphasic and evolutional medium) or their very specific physico-chemical conditions (hyper-alkaline medium with pH ≥ 13, high content in calcium) or by the fact of numerous couplings existing between different phenomenologies. At the level of a radioactive cemented wasteform, a high degree of complexity is reached, in particular if the system communicates with the atmosphere (open system allowing regulation of the pressures but also the admission of O 2 , strong reactive with regards to radiolysis). Then, the radiolysis description exceeds widely the only one aspect of the decomposition of alkaline water under irradiation and makes necessary a global phenomenological approach. In this context, some 'outlying' phenomena, highly coupled with radiation chemistry, have to be taken into account because they contribute to deeply modify the net result of the radiolysis: radioactive decay of multiple αβγ emitters with filiation, phase changes (for example H 2 aq → H 2 gas) within the pores, gas transport by convection (Darcy law) and by diffusion (Fick law), precipitation/dissolution of solid phases, effect of the ionic strength and the temperature, disturbances connected to the presence of some solutes with redox potentialities (iron, sulphur). The integration work carried out on the previous points leads to an operational model (DOREMI) allowing the estimate of H 2 amounts produced by radiolysis in different cemented radioactive waste-forms. As the final expression of the model, numerical simulations constitute a relevant tool of expertise and prospecting, contributing to accompany the thought on radiolysis in cement matrices in general and in cemented waste-forms in particular. Starting from different examples, simulations can be so used in order to test some hypotheses or illustrate the greatest influence of gas transport, dose

  17. Cataloguing outside the box a practical guide to cataloguing special collections materials

    CERN Document Server

    Falk, Patricia

    2010-01-01

    A practical guide to cataloguing and processing the unique special collections formats in the Browne Popular Culture Library (BPCL) and the Music Library and Sound Recordings Archives (MLSRA) at Bowling Green State University (BGSU) (e.g. fanzines, popular sound recordings, comic books, motion picture scripts and press kits, popular fiction). Cataloguing Outside the Box provides guidance to professionals in library and information science facing the same cataloguing challenges. Additionally, name authority work for these collections is addressed.provides practical guidelines and solutions for

  18. Data quality objectives for moisture measurement in stabilized special nuclear material

    International Nuclear Information System (INIS)

    Weier, D.R.; Pulsipher, B.A.; Silvers, K.L.

    2000-01-01

    Data Quality Objectives methodology is applied to Loss-on-Ignition (LOI) moisture content testing for stabilized nuclear materials. This work was performed by Pacific Northwest National Laboratory in support of the Plutonium Finishing Plant (PFP)/Fluor Hanford, Inc. Historical results on LOI test results for two material types, oxide and sludge, are used to estimate within container variability. This variability estimate is then used in formulating the two recommended acceptance criteria for containers of material. The criteria which follow are proposed to replace the current criterion, which requires recycle if either of two container LOI measurements exceed 0.5 wt%, the DOE Standard 3013-99 threshold value. (1) The 95% upper confidence limit (UCL) for the true mean underlying moisture content in the container material should be less than 0.5 wt%. (2) The difference between the two LOI measurements per container should not exceed their expected 95th percentile relative to the estimated variability. Containers not meeting the first criterion, or those that generate in any negative LOI result, require material recycle. Containers not meeting the second criteria require review of the measurement results, potentially leading to resampling and retesting. Data from Los Alamos National Laboratory studies on moisture testing are obtained and analyzed. The performance of Supercritical Fluid Extraction (SFE), which will soon be implemented at the PFP, is described for several material types. This information will be used to establish initial acceptance criteria when SFE comes on line

  19. Catalog of NBS standard reference materials, 1975--76 edition. Special pub

    International Nuclear Information System (INIS)

    Seward, R.W.

    1975-06-01

    This Catalog lists and describes the Standard Reference Materials (SRM's), Research Materials (RM's), and General Materials (GM's) currently distributed by the National Bureau of Standards, as well as many of the materials currently in preparation. SRM's are used to calibrate measurement systems and to provide a central basis for uniformity and accuracy of measurement. The unit and quantity, the type, and the certified characterization are listed for each SRM, as well as directions for ordering. The RM's are not certified, but are issued to meet the needs of scientists engaged in materials research. RM's are issued with a 'Report of Investigation', the sole authority of which is the author of the report. The GM's are standardized by some agency other than NBS. NBS acts only as a distribution point and does not participate in the standardization of these materials. Announcements of new and renewal SRM's, RM's and GM's are made in the semi-annual supplements of this Catalog, SRM Price List, and in scientific and trade journals

  20. Recent advances on glass-forming systems driven far from equilibrium. Special issue marking the completion of the Research Unit FOR 1394 `Nonlinear response to probe vitrification'

    Science.gov (United States)

    Fuchs, Matthias

    2017-08-01

    The nature of the glass transition is one of the frontier questions in Statistical Physics and Materials Science. Highly cooperative structural processes develop in glass-forming melts exhibiting relaxational dynamics which is spread out over many decades in time. While considerable progress has been made in recent decades towards understanding dynamical slowing-down in quiescent systems, the interplay of glassy dynamics with external fields reveals a wealth of novel phenomena yet to be explored. This special issue focuses on recent results obtained by the Research Unit FOR 1394 `Nonlinear response to probe vitrification' which was funded by the German Science Foundation (DFG). In the projects of the research unit, strong external fields were used in order to gain insights into the complex structural and transport phenomena at the glass transition under far-from-equilibrium conditions. This aimed inter alia to test theories of the glass transition developed for quiescent systems by pushing them beyond their original regime. Combining experimental, simulational, and theoretical efforts, the eight projects within the FOR 1394 measured and determined aspects of the nonlinear response of supercooled metallic, polymeric, and silica melts, of colloidal dispersions, and of ionic liquids. Applied fields included electric and mechanic fields, and forced active probing (`micro-rheology'), where a single probe is forced through the glass-forming host. Nonlinear stress-strain and force-velocity relations as well as nonlinear dielectric susceptibilities and conductivities were observed. While the physical manipulation of melts and glasses is interesting in its own right, especially technologically, the investigations performed by the FOR 1394 suggest to use the response to strong homogeneous and inhomogeneous fields as technique to explore on the microscopic level the cooperative mechanisms in dense melts of strongly interacting constituents. Questions considered concern the

  1. Far-Field Accumulation of Fissile Material From Waste Packages Containing Plutonium Disposition Waste Form

    International Nuclear Information System (INIS)

    J.P. Nicot

    2000-01-01

    The objective of this calculation is to estimate the quantity of fissile material that could accumulate in fractures in the rock beneath plutonium-ceramic (Pu-ceramic) and Mixed-Oxide (MOX) waste packages (WPs) as they degrade in the potential monitored geologic repository at Yucca Mountain. This calculation is to feed another calculation (Ref. 31) computing the probability of criticality in the systems described in Section 6 and then ultimately to a more general report on the impact of plutonium on the performance of the proposed repository (Ref. 32), both developed concurrently to this work. This calculation is done in accordance with the development plan TDP-DDC-MD-000001 (Ref. 9), item 5. The original document described in item 5 has been split into two documents: this calculation and Ref. 4. The scope of the calculation is limited to only very low flow rates because they lead to the most conservative cases for Pu accumulation and more generally are consistent with the way the effluent from the WP (called source term in this calculation) was calculated (Ref. 4). Ref. 4 (''In-Drift Accumulation of Fissile Material from WPs Containing Plutonium Disposition Waste Forms'') details the evolution through time (breach time is initial time) of the chemical composition of the solution inside the WP as degradation of the fuel and other materials proceed. It is the chemical solution used as a source term in this calculation. Ref. 4 takes that same source term and reacts it with the invert; this calculation reacts it with the rock. In addition to reactions with the rock minerals (that release Si and Ca), the basic mechanisms for actinide precipitation are dilution and mixing with resident water as explained in Section 2.1.4. No other potential mechanism such as flow through a reducing zone is investigated in this calculation. No attempt was made to use the effluent water from the bottom of the invert instead of using directly the effluent water from the WP. This

  2. Far-Field Accumulation of Fissile Material From Waste Packages Containing Plutonium Disposition Waste Form

    Energy Technology Data Exchange (ETDEWEB)

    J.P. Nicot

    2000-09-29

    The objective of this calculation is to estimate the quantity of fissile material that could accumulate in fractures in the rock beneath plutonium-ceramic (Pu-ceramic) and Mixed-Oxide (MOX) waste packages (WPs) as they degrade in the potential monitored geologic repository at Yucca Mountain. This calculation is to feed another calculation (Ref. 31) computing the probability of criticality in the systems described in Section 6 and then ultimately to a more general report on the impact of plutonium on the performance of the proposed repository (Ref. 32), both developed concurrently to this work. This calculation is done in accordance with the development plan TDP-DDC-MD-000001 (Ref. 9), item 5. The original document described in item 5 has been split into two documents: this calculation and Ref. 4. The scope of the calculation is limited to only very low flow rates because they lead to the most conservative cases for Pu accumulation and more generally are consistent with the way the effluent from the WP (called source term in this calculation) was calculated (Ref. 4). Ref. 4 (''In-Drift Accumulation of Fissile Material from WPs Containing Plutonium Disposition Waste Forms'') details the evolution through time (breach time is initial time) of the chemical composition of the solution inside the WP as degradation of the fuel and other materials proceed. It is the chemical solution used as a source term in this calculation. Ref. 4 takes that same source term and reacts it with the invert; this calculation reacts it with the rock. In addition to reactions with the rock minerals (that release Si and Ca), the basic mechanisms for actinide precipitation are dilution and mixing with resident water as explained in Section 2.1.4. No other potential mechanism such as flow through a reducing zone is investigated in this calculation. No attempt was made to use the effluent water from the bottom of the invert instead of using directly the effluent water from the

  3. The effect of using different sources of dry materials on waste-form grout properties

    International Nuclear Information System (INIS)

    Spence, R.D.; Gilliam, T.M.; McDaniel, E.W.

    1992-01-01

    A reference grout formulation had been developed for a liquid low-level radioactive waste using the following dry materials: ground limestone, ground granulated blast furnace slag, fly ash, and cement. The effect of varying the sources of these dry materials are tested. Two limestones, two fly ashes, two cements, and eight slags were tested. Varying the source of dry materials significantly affected the grout properties, but only the 28-d free-standing liquid varied outside of the preferred range. A statistical technique, Tukey's paired comparison, can be used to ascertain whether a given combination of dry materials resulted in grout properties significantly different from those of other combinations of dry materials

  4. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  5. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

  6. Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

    International Nuclear Information System (INIS)

    Smith, H.A. Jr.; Schillebeeckx, P.

    1997-01-01

    A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

  7. Special Features of Using Secondary Materials in the Interior Design of Public Dining Establishments

    Science.gov (United States)

    Kuznetsova, Irina; Hapchuk, Olena; Lukinov, Vitaly

    2017-10-01

    This article analyses the latest publications studying the use and practical application of secondary resources as raw materials in design. This analysis is based on the list of secondary resources and their applications in interior decoration. In particular, the interiors of public catering enterprises were analysed. Restaurants with different functional purposes that were classified into several categories with specific peculiarities of interior design were identified. This article presents and describes different types of public catering enterprises based on those categories. The interior design of a public catering enterprise is regarded as a considerably complex system. Different types of secondary materials were reviewed to identify the most frequently used materials for interior space design. This article describes the main peculiarities of the use of secondary materials and presents examples of their practical application. The function of secondary materials in the interior design of public catering enterprises were detected and reviewed. On the basis of the analysis, several directions for the practical application of our results in the field of public catering enterprise design were suggested.

  8. Use of 15N in nitrification inhibitor studies with special reference to indigenous materials

    International Nuclear Information System (INIS)

    Sahrawat, K.L.

    1988-01-01

    Non-edible oil seed cakes and their constituents have been advantageously used for increasing the efficiency of fertilizer nitrogen (N) for crop production. The beneficial effects of these materials have been attributed to retardation of nitrification, which lessen the loss of N associated with nitrification by leaching and denitrification in situations where these losses are high. However, it is possible that some of the effects of these materials could be due to immobilization-remineralization of N particularly when the carbonaceous materials are added with fertilizers at high rates. A methodology involving the use of 15 N-labelled fertilizers is advanced to sort out whether the beneficial effects of non-edible oil seed cakes and other materials are due to retardation of nitrification and or immobilization-remineralization of fertilizer N. Using the proposed technique it would be possible to make realistic evaluation of the wealth of indigenous products as nitrification inhibitors. Following the proposed approach it would also be possible to widen the scope and depth of research in this area for ultimately better exploitation of indigenous materials as nitrification inhibitors. (author). 18 refs

  9. The transport of radioactive materials, paying special attention to nuclear fuels

    International Nuclear Information System (INIS)

    Blechschmidt, M.

    1977-06-01

    The transport of radioactive materials, particularly within the nuclear fuel cycle, is of increasing importance, and is more than ever a matter of public debate. This report provides information concerning the necessary physical, technical and administrative precautions which must be taken to ensure protection of the environment. The international standard of requirements for the packing of the materials is emphasized, as in many cases, transports cross national borders. The relatively comprehensive list of references can be used for the study of details. (orig.) [de

  10. Selfwelding, friction and wear behaviour of special materials in sodium under corroding conditions

    International Nuclear Information System (INIS)

    Borgstedt, H.U.; Mattes, K.; Wild, E.

    1975-11-01

    Control rod guides and fuel element duct load pads have to be fabricated from materials exhibiting optimum slide behaviour. Galling or self-welding under static conditions should not be tolerated. Given bearing clearances have to be maintained constant and loop contamination, caused by wear particles, have to be prevented. Since high friction between contacting pads may impose severe limitations on core compaction, for the duct load pads a maximum friction coefficient of 0.5 is acceptable. The effect of sodium corrosion should not impair the friction and wear behaviour of the materials applied. This report covers the work performed to optain appropriate mechanical design data. (orig.) [de

  11. Single access laparoscopic cholecystectomy: technique without the need for special materials and with better ergonomics

    Directory of Open Access Journals (Sweden)

    Marco Aurélio Lameirão Pinto

    Full Text Available The authors describe a surgical technique which allows, without increasing costs, to perform laparoscopic cholecystectomy with a single incision, without using specific materials and with better surgical ergonomics. The technique consists of a longitudinal umbilical incision, navel detachment, use of a permanent 10mm trocar and two clamps directly and bilaterally through the aponeurosis without the use of 5mm trocars, transcutaneous gallbladder repair with straight needle cotton suture, ligation with unabsorbable suture and umbilical incision for the specimen extraction. The presented technique enables the procedure with conventional and permanent materials, improving surgical ergonomics, with safety and aesthetic advantages.

  12. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1981-01-01

    This report provides and explains the differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1979, through March 31, 1980, and includes accounting corrections for data from earlier periods. It is the seventh such semiannual report. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic spcial nuclear material has occurred

  13. Executive summary of the special safeguards study on material control and accounting systems. Final report

    International Nuclear Information System (INIS)

    1975-01-01

    This report assesses the feasibility of real-time systems applied to mixed-oxide fuel rod fabrication. Their interaction with other material control and accounting measures are considered. Economics, effectiveness, and acceptance factors are discussed. A cost-benefit evaluation is made and recommendations given for safeguards improvements

  14. 75 FR 45195 - Office of Hazardous Materials Safety; Notice of Applications for Modification of Special Permit

    Science.gov (United States)

    2010-08-02

    ... permits (e.g. to provide for additional hazardous materials, packaging design changes, additional mode of... compressed oxygen without rigid outer packaging when no other means of transportation exist. 14860-M Alaska... authorizing the transportation in commerce of compressed oxygen without rigid outer packaging when no other...

  15. 75 FR 42364 - Hazardous Materials: Incorporation of Certain Cargo Tank Special Permits Into Regulations

    Science.gov (United States)

    2010-07-21

    .... Moveable fuel storage tenders are used to supply LPG fuel to farmers for crop drying, crop irrigation... vegetables, fruits, and ornamentals. Control of soil- borne pests increases plant aesthetics, plant quality... liquid lacquer base. Paint related material including paint 3 UN1263 II thinning drying, removing, or...

  16. On the source material of magmas - with special reference to Nd isotopic ratios of igneous rocks

    International Nuclear Information System (INIS)

    Shuto, Kenji

    1980-01-01

    In 1973, the Sm-Nd method was first used for the measurement of the absolute age of igneous rocks and meteorites. Subsequently in the following years, the research works by means of the Nd isotopic ratio in igneous rocks have been made strenuously in order to reveal the chemistry of the source materials of magma giving rise to the igneous rocks and further the evolution process of mantle and earth's crust. The fundamental items for the Sm-Nd method are explained. Then, the research results more important in the above connection are given. Finally, the ideas by the author concerning the source materials of magma are presented from the data available on the Nd isotopes in meteorites and igneous rocks. The following matters are described: the fundamentals of Sm-Nd method, the Nd content in seawater, the negative correlation between Nd and Sr isotopic ratios in igneous rocks, magma source materials and Nd isotopes, and considerations on magma source materials. (J.P.N.)

  17. 77 FR 22362 - Exemption Requests for Special Nuclear Material License SNM-362, Department of Commerce...

    Science.gov (United States)

    2012-04-13

    ... Nuclear Material License SNM-362, Department of Commerce, Gaithersburg, MD AGENCY: Nuclear Regulatory... Commerce, National Institutes of Standards and Technology (NIST) in Gaithersburg, Maryland. NIST requested... within the Department of Commerce. The SNM license was renewed in 1979, 1985, 1991, and 1997. The current...

  18. Study of a chromia-forming alloy behavior as interconnect material for High Temperature Vapor Electrolysis

    International Nuclear Information System (INIS)

    Guillou, S.

    2011-01-01

    In High Temperature Vapor Electrolysis (HTVE) system, the materials chosen for the inter-connectors should have a good corrosion behaviour in air and in H 2 -H 2 O mixtures at 800 C, and keep a high electronic conductivity over long durations as well. In this context, the first goal of this study was to evaluate a commercial ferritic alloy (the K41X alloy) as interconnect for HTVE application. Oxidation tests in furnace and in microbalance have therefore been carried out in order to determine oxidation kinetics. Meanwhile, the Area Specific Resistance (ASR) was evaluated by Contact Resistance measurements performed at 800 C. The second objective was to improve our comprehension of chromia-forming alloys oxidation mechanism, in particular in H 2 /H 2 O mixtures. For that purpose, some specific tests have been conducted: tracer experiments, coupled with the characterization of the oxide scale by PEC (Photo-Electro-Chemistry). This approach has also been applied to the study of a LaCrO 3 perovskite oxide coating on the K41X alloy. This phase is indeed of high interest for HTVE applications due to its high conductivity properties. This latter study leads to further understanding on the role of lanthanum as reactive element, which effect is still under discussion in literature.In both media at 800 C, the scale is composed of a Cr 2 O 3 /(Mn,Cr) 3 O 4 duplex scale, covered in the case of H 2 -H 2 O mixture by a thin scale made of Mn 2 TiO 4 spinel. In air, the growth mechanism is found to be cationic, in agreement with literature. The LaCrO 3 coating does not modify the direction of scale growth but lowers the growth kinetics during the first hundreds hours. Moreover, with the coating, the scale adherence is favored and the conductivity appears to be slightly higher. In the H 2 -H 2 O mixture, the growth mechanism is found to be anionic. The LaCrO 3 coating diminishes the oxidation kinetics. Although the scale thickness is about the same in both media, the ASR parameter

  19. Department of Energy (DOE) system for the transportation of strategic quantities of special nuclear material (SQ SNM)

    International Nuclear Information System (INIS)

    Dickason, D.P.

    1978-01-01

    Since 1947 DOE and its predecessor agencies, AEC and ERDA, have moved nuclear materials by a variety of commercial and government transportation modes. In the late 1960's world-wide terrorism and other dissident activities prompted the then-AEC to review its procedures for safeguarding SNM. These reviews resulted in immediate and long-range programs for improvement of overall safeguards. Domestic transportation of completed nuclear weapons and SNM used in the weapons program was selected for special consideration. In the early 1970's AEC started the development of a Safe Secure Trailer (SST) to transport nuclear weapons and nuclear components and the development and installation of a high frequency (HF) communications system to assure continuous radio contact between selected highway and rail shipments and Headquarters, Albuquerque Operations (ALO). Late 1974 AEC directed ALO to develop a transportation system to extend weapons-level protection to all AEC SQ SNM shipments and to consolidate, manage, and operate this system. As of September 1976 all SQ SNM was being transported in the Safe Secure DOE (then ERDA) transportation safeguards system, composed of the following principal elements: (1) Transport equipment consisting of Safe Secure Trailers and specially modified towing tractors; Safe Secure Railcars and specially modified escort coaches; and specially designed highway escort vehicles. (2) An automated high-frequency digital radio system that enables continuous communications between the transporting equipment and central control. (3) A courier force that operates all transport equipment (except aircraft and rail power units) and mobile communications equipment; provides armed protection for shipments; and assures proper safety en route. (4) A central Headquarters staff that plans, executes, and controls shipments and directs, manages, and operates the system

  20. Special Issue: Adaptive/Smart Structures and Multifunctional Materials with Application to Morphing Aircraft

    Directory of Open Access Journals (Sweden)

    Rafic Ajaj

    2014-12-01

    Full Text Available Recent advances in smart structures and multifunctional materials have facilitated many novel aerospace technologies such as morphing aircraft. A morphing aircraft, bio-inspired by natural fliers, has gained a lot of interest as a potential technology to meet the ambitious goals of the Advisory Council for Aeronautics Research in Europe (ACARE Vision 2020 and the FlightPath 2050 documents. A morphing aircraft continuously adjusts its wing geometry to enhance flight performance, control authority, and multi-mission capability.[...

  1. New cranial material of the earliest filter feeding flamingo Harrisonavis croizeti (Aves, Phoenicopteridae) informs the evolution of the highly specialized filter feeding apparatus

    NARCIS (Netherlands)

    Torres, Chris R.; De Pietri, Vanesa L.; Louchart, Antoine; van Tuinen, Marcel

    The Oligo-Miocene flamingo Harrisonavis croizeti represents an intermediate form between the highly specialized extant flamingo cranial morphology and the more generalized ancestral phoenicopteriform one, characterized by the extinct taxon Palaelodus. However, the original description of H. croizeti

  2. The effect of using different sources of dry materials on waste-form grout properties

    International Nuclear Information System (INIS)

    Spence, R.D.; Gilliam, T.M.; McDaniel, E.W.

    1992-01-01

    A reference grout formulation had been developed for a liquid low-level radioactive waste using the following dry materials: ground limestone, ground granulated blast furnace slag, fly ash, and cement. The effect of varying the sources of these dry materials was tested. Two limestones, two fly ashes, two cements, and eight slags were tested. Varying the source of dry materials significantly affected the grout properties, but only the 28-d free-standing liquid varied outside of the preferred range. A statistical technique, Tukey's paired comparison, can be used to ascertain whether a given combination of dry materials resulted in grout properties significantly different from those of other combinations of dry materials. (author)

  3. 77 FR 32711 - 30-Day Notice of Proposed Information Collection: DS-234, Special Immigrant Visa Biodata Form...

    Science.gov (United States)

    2012-06-01

    ..., Refugees, and Migration, Office of Admissions (PRM/A). Form Number: DS-234. Respondents: Iraqi and Afghan... Population, Refugees and Migration. Dated: May 14, 2012. Kelly A. Gauger, Deputy Director, Office of Admissions, Bureau of Population, Refugees, and Migration, Department of State. [FR Doc. 2012-13343 Filed 5...

  4. Opportunities of influence of plasma streams formed in IKA with continuos nor king gas filling en the surface of materials

    International Nuclear Information System (INIS)

    Useinov, B.M.; Useinova, A.M.; Amrenova, A.U.; Pusankov, S.A.; Sartin, S.A.; Virko, P.G.

    2001-01-01

    The results of the investigation of influence of plasma stream formed in IKA with continuous working gas filling on the surface of stainless steel 12X18H10T and aluminum are given in this article. It is shown here that the effect of influence of plasma stream on the surface of materials depends on the way of working gas filling. There is the comparison of influence of plasma stream formed in plasma accelerator with impulse and continuous working gas filling

  5. Effect of material scatter on the plastic behavior and stretchability in sheet metal forming

    NARCIS (Netherlands)

    Wiebenga, J.H.; Atzema, E.H.; Atzema, E.H.; An, Y.G.; Vegter, H.; van den Boogaard, Antonius H.

    2014-01-01

    Robust design of forming processes is gaining attention throughout the industry. To analyze the robustness of a sheet metal forming process using Finite Element (FE) simulations, an accurate input in terms of parameter scatter is required. This paper presents a pragmatic, accurate and economic

  6. Astrophysical implications of extraterrestrial materials: A special issue for Ernst K. Zinner

    Science.gov (United States)

    Nittler, Larry R.

    2018-01-01

    This special issue is dedicated to the memory of Dr. Ernst K. Zinner (Fig. 1). Dr. Zinner (1937-2015) was a pioneer in the use of Secondary Ion Mass Spectrometry (SIMS) in geo- and cosmochemistry. His contributions to science were vast, but in addition to his foundational SIMS development work, he is best known for the discovery and detailed characterization of presolar stardust grains in meteorites. This discovery opened up important new connections between astrophysics and meteoritical research and this is the overarching theme of this issue. Throughout his career, Ernst was a teacher, mentor, friend, and generous collaborator to legions of scientists. This issue presents research by many who were taught by, inspired by, and/or collaborated with this innovative cosmochemist and astrophysicist. In addition to the author, Ernst's former students and collaborators Drs. Christine Floss (Washington University) Peter Hoppe (MPI for chemistry, Mainz, Germany), and Kevin McKeegan (University of California, Los Angeles) served as Guest Editors for this issue.

  7. ONE YEAR'S EXPERIENCE IN REGULATING BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIAL IN THE COMMONWEALTH OF KENTUCKY

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, C L

    1963-06-15

    On March 26, 1962, Kentucky assumed regulatory control for the licensing of subcritical nuclear materials within its boundaries. The administration of the state radiological health program is described, and the manpower, fiscal, and equipment requirements are outlined. The licensing activity of the state is also described. Results are reported of preliminary studies of state-owned land for low-level radioactive waste disposal. The procedures for inspection of licensees are described. Proposed changes in the Radiological Health regulations of Kentucky in order to bring about compatibility with AEC's code of Federal Regulations are outlined. (D.L.C.)

  8. Uranium isotopic composition and uranium concentration in special reference material SRM A (uranium in KCl/LiCl salt matrix)

    International Nuclear Information System (INIS)

    Graczyk, D.G.; Essling, A.M.; Sabau, C.S.; Smith, F.P.; Bowers, D.L.; Ackerman, J.P.

    1997-07-01

    To help assure that analysis data of known quality will be produced in support of demonstration programs at the Fuel Conditioning Facility at Argonne National Laboratory-West (Idaho Falls, ID), a special reference material has been prepared and characterized. Designated SRM A, the material consists of individual units of LiCl/KCl eutectic salt containing a nominal concentration of 2.5 wt. % enriched uranium. Analyses were performed at Argonne National Laboratory-East (Argonne, IL) to determine the uniformity of the material and to establish reference values for the uranium concentration and uranium isotopic composition. Ten units from a batch of approximately 190 units were analyzed by the mass spectrometric isotope dilution technique to determine their uranium concentration. These measurements provided a mean value of 2.5058 ± 0.0052 wt. % U, where the uncertainty includes estimated limits to both random and systematic errors that might have affected the measurements. Evidence was found of a small, apparently random, non-uniformity in uranium content of the individual SRM A units, which exhibits a standard deviation of 0.078% of the mean uranium concentration. Isotopic analysis of the uranium from three units, by means of thermal ionization mass spectrometry with a special, internal-standard procedure, indicated that the uranium isotopy is uniform among the pellets with a composition corresponding to 0.1115 ± 0.0006 wt. % 234 U, 19.8336 ± 0.0059 wt. % 235 U, 0.1337 ± 0.0006 wt. % 236 U, and 79.9171 ± 0.0057 wt. % 238 U

  9. Standard practice for sampling special nuclear materials in multi-container lots

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of several containers. The problem addressed is the selection of the number of containers to be sampled, the number of samples to be taken from each sampled container, and the number of aliquot analyses to be performed on each sample. 1.2 This practice provides examples for application as well as the necessary development for understanding the statistics involved. The uniqueness of most situations does not allow presentation of step-by-step procedures for designing sampling plans. It is recommended that a statistician experienced in materials sampling be consulted when developing such plans. 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standar...

  10. Sustainable fibre materials for replacing plastics in 3D-forming applications

    OpenAIRE

    Jacobsen, Eirik Ulsaker

    2017-01-01

    Plastic is a very broad family of materials that may provide a wide array of mechanical properties depending on the plastic or production method in question. This is why many industries have chosen plastic as their material of choice for the production of anything from plastic bags to underground piping. There is, however, a prominent issue concerning the heavy environmental impact of plastic. This is both due to the processing of crude oil and lack of biodegradability which in turn impact na...

  11. Characterization of material parameters for high speed forming and cutting via experiment and inverse simulation

    Science.gov (United States)

    Scheffler, Christian; Psyk, Verena; Linnemann, Maik; Tulke, Marc; Brosius, Alexander; Landgrebe, Dirk

    2018-05-01

    High speed velocity effects in production technology provide a broad range of technological and economic advantages [1, 2]. However, exploiting them necessitates the knowledge of strain rate dependent material behavior in process modelling. In general, high speed material data characterization features several difficulties and requires sophisticated approaches in order to provide reliable material data. This paper proposes two innovative concepts with electromagnetic and pneumatic drive and an approach for material characterization in terms of strain rate dependent flow curves and parameters of failure or damage models. The test setups have been designed for investigations of strain rates up to 105 s-1. In principle, knowledge about the temporary courses and local distributions of stress and strain in the specimen is essential for identifying material characteristics, but short process times, fast changes of the measurement values, small specimen size and frequently limited accessibility of the specimen during the test hinder directly measuring these parameters at high-velocity testing. Therefore, auxiliary test parameters, which are easier to measure, are recorded and used as input data for an inverse numerical simulation that provides the desired material characteristics, e.g. the Johnson-Cook parameters, as a result. These parameters are a force equivalent strain signal on a measurement body and the displacement of the upper specimen edge.

  12. Restructuring of microparticles in nuclear ceramic materials. Part III. Form distribution

    International Nuclear Information System (INIS)

    Lameiras, F.S.

    1991-01-01

    According to the present model, the modification of the microparticle form, tending to an equiaxial one, is a way to decrease the interface energy of a microparticle set. If the microparticles are dispersed, these ones tend to the spherical form. If they form aggregates (grains), the interface energy is stored in the grain boundaries, triple lines and quadruple points. A mean topological structure combining two kinds of nearly equiaxed polyhedra is proposed for aggregates of microparticles in order to minimize the surface of the grain boundaries, the length of the triple lines and the number of the quadruple points. As the restructuring evolutes, the average grain form tends to take the one of this polyhedra structure. (author)

  13. Equipping a glovebox for waste form testing and characterization of plutonium bearing materials

    International Nuclear Information System (INIS)

    Noy, M.; Johnson, S.G.; Moschetti, T.L.

    1997-01-01

    The recent decision by the Department of Energy to pursue a hybrid option for the disposition of weapons plutonium has created the need for additional facilities that can examine and characterize waste forms that contain Pu. This hybrid option consists of the placement of plutonium into stable waste forms and also into mixed oxide fuel for commercial reactors. Glass and glass-ceramic waste forms have a long history of being effective hosts for containing radionuclides, including plutonium. The types of tests necessary to characterize the performance of candidate waste forms include: static leaching experiments on both monolithic and crushed waste forms, microscopic examination, and density determination. Frequently, the respective candidate waste forms must first be produced using elevated temperatures and/or high pressures. The desired operations in the glovebox include, but are not limited to the following: (1) production of vitrified/sintered samples, (2) sampling of glass from crucibles or other vessels, (3) preparing samples for microscopic inspection and monolithic and crushed static leach tests, and (4) performing and analyzing leach tests in situ. This paper will describe the essential equipment and modifications that are necessary to successfully accomplish the goal of outfitting a glovebox for these functions

  14. LOGICAL-ORIENTED TASKS AS A FORM OF ORGANIZATION OF THE EDUCATIONAL MATERIAL CONTENT IN TEACHING MATHEMATICS TO STUDENTS

    Directory of Open Access Journals (Sweden)

    Oksana Smirnova

    2015-09-01

    Full Text Available The article substantiates the need to improve the logical preparation of students. The authors regard the logical-oriented tasks as a form of organization of the content of educational material in teaching Mathematics and discriminate the types of tasks aimed at the formation of logical methods and operations.

  15. A Special Material or a New State of Matter: A Review and Reconsideration of the Aerogel

    Directory of Open Access Journals (Sweden)

    Jun Shen

    2013-03-01

    Full Text Available The ultrahighly nanoporous aerogel is recognized as a state of matter rather than as a functional material, because of its qualitative differences in bulk properties, transitional density and enthalpy between liquid and gas, and diverse chemical compositions. In this review, the characteristics, classification, history and preparation of the aerogel were introduced. More attention was paid to the sol-gel method for preparing different kinds of aerogels, given its important role on bridging the synthetic parameters with the properties. At last, preparation of a novel single-component aerogel, design of a composite aerogel and industrial application of the aerogel were regarded as the research tendency of the aerogel state in the near future.

  16. The ''nuclear car wash'': a scanner to detect illicit special nuclear material in cargo containers

    International Nuclear Information System (INIS)

    Slaughter, D. R.; Accatino, M. R.; Bernstein, A.; Dougan, A. D.; Hall, J. M.; Loshak, A.; Manatt, D. R.; Pohl, B. A.; Prussin, S. G.; Walling, R. S.; Weirup, D. L.

    2004-01-01

    There is an urgent need to improve the reliability of screening cargo containers for illicit nuclear material that may be hidden there for terrorist purposes. A screening system is described for detection of fissionable material hidden in maritime cargo containers. The system makes use of a low intensity neutron beam for producing fission; and the detection of the abundant high-energy γ rays emitted in the β-decay of short-lived fission products and β-delayed neutrons. The abundance of the delayed γ rays is almost an order of magnitude larger than that of the delayed neutrons normally used to detect fission and they are emitted on about the same time scale as the delayed neutrons, i.e., ∼1 min. The energy and temporal distributions of the delayed γ rays provide a unique signature of fission. Because of their high energy, these delayed γ rays penetrate loW--Z cargoes much more readily than the delayed neutrons. Coupled with their higher abundance, the signal from the delayed γ rays escaping from the container is predicted to be as much as six decades more intense than the delayed neutron signal, depending upon the type and thickness of the intervening cargo. The γ rays are detected in a large array of scintillators located along the sides of the container as it is moved through them. Measurements have confirmed the signal strength in somewhat idealized experiments and have also identified one interference when 14.5 MeV neutrons from the D, T reaction are used for the interrogation. The interference can be removed easily by the appropriate choice of the neutron source

  17. Printing, folding and assembly methods for forming 3D mesostructures in advanced materials

    Science.gov (United States)

    Zhang, Yihui; Zhang, Fan; Yan, Zheng; Ma, Qiang; Li, Xiuling; Huang, Yonggang; Rogers, John A.

    2017-03-01

    A rapidly expanding area of research in materials science involves the development of routes to complex 3D structures with feature sizes in the mesoscopic range (that is, between tens of nanometres and hundreds of micrometres). A goal is to establish methods for controlling the properties of materials systems and the function of devices constructed with them, not only through chemistry and morphology, but also through 3D architectures. The resulting systems, sometimes referred to as metamaterials, offer engineered behaviours with optical, thermal, acoustic, mechanical and electronic properties that do not occur in the natural world. Impressive advances in 3D printing techniques represent some of the most broadly recognized developments in this field, but recent successes with strategies based on concepts in origami, kirigami and deterministic assembly provide additional, unique options in 3D design and high-performance materials. In this Review, we highlight the latest progress and trends in methods for fabricating 3D mesostructures, beginning with the development of advanced material inks for nozzle-based approaches to 3D printing and new schemes for 3D optical patterning. In subsequent sections, we summarize more recent methods based on folding, rolling and mechanical assembly, including their application with materials such as designer hydrogels, monocrystalline inorganic semiconductors and graphene.

  18. Special aspects of responsibility of the principal offender for commission of the crimes with two forms of guilt

    Directory of Open Access Journals (Sweden)

    Ірина Анатоліївна Зінов'єва

    2016-06-01

    Full Text Available In the article the author analyzed the views of scientists on the issue of existence of complicity in the crimes with two forms of guilt. The author drew a conclusion that the confines of complicity as joint intentional participation in commission of intentional crime include nothing else than an act or an act and causation of basic consequence. An aggravated consequence caused by the principal offender through negligence is outside complicity because the joint intent to its commission is absent. The author substantiated the necessity for inculpation an aggravated consequence caused by the principal offender through negligence others accomplices if they had a duty and possibility to envisage it. Determining of the confines of knowing nature of an act of the principal offender of others accomplices as the joint result of their interrelated acts is recognized as prerequisite for inculpation them this consequence. Causation an aggravated consequence through negligence of intentional crime jointly by several persons that had a duty and possibility to envisage it is recognized as jointly causation through negligence. The author suggested examine the subjects of causation this consequence that had a duty and possibility to envisage it not as accomplices but as co-causers, each of them individually liable for its causation. The author distinguished the groups of crimes that have an aggravated consequence which is outside complicity. The author suggested the ways of qualification the crime with two forms of guilt subject to existence of the elements of complicity.

  19. Method of extruding and packaging a thin sample of reactive material including forming the extrusion die

    International Nuclear Information System (INIS)

    Lewandowski, E.F.; Peterson, L.L.

    1985-01-01

    This invention teaches a method of cutting a narrow slot in an extrusion die with an electrical discharge machine by first drilling spaced holes at the ends of where the slot will be, whereby the oil can flow through the holes and slot to flush the material eroded away as the slot is being cut. The invention further teaches a method of extruding a very thin ribbon of solid highly reactive material such as lithium or sodium through the die in an inert atmosphere of nitrogen, argon or the like as in a glovebox. The invention further teaches a method of stamping out sample discs from the ribbon and of packaging each disc by sandwiching it between two aluminum sheets and cold welding the sheets together along an annular seam beyond the outer periphery of the disc. This provides a sample of high purity reactive material that can have a long shelf life

  20. The particulate material formed during the combusion of polonium and plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, K.

    1963-11-15

    Over the last decade the production and use of uranium, plutonium and other radioactive materials has developed steadily. The work described in this paper is part of a reasonably comprehensive study of the extent and seriousness of the radiological hazards which could occur as the result of selected types of accidents. Additionally, these studies demonstrate the types of material and operations which are the more likely to produce a serious situation should a mishap occur. The emphasis in the paper, therefore, is on the differences between an element, polonium, of high specific activity which is volatile, and a reactive material, plutonium, of lower specific activity which is non-volatile but of somewhat greater radiotoxicity. The modes of formation of oxide aerosols from these two elements are, to a very considerable degree, representative of two important and contrasting processes.

  1. Standard test method for nondestructive assay of special nuclear material holdup using Gamma-Ray spectroscopic methods

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2007-01-01

    1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U, or 239Pu remaining as holdup in nuclear facilities. Holdup occurs in all facilities where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors. 1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources (1, 2, 3, 4). 1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements; as well as the laws of physics. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material...

  2. Dependence of cell adhesion on extracellular matrix materials formed on pore bridge boundaries by nanopore opening and closing geometry.

    Science.gov (United States)

    Kim, Sueon; Han, Dong Yeol; Chen, Zhenzhong; Lee, Won Gu

    2018-04-30

    In this study, we report experimental results for characterization of the growth and formation of pore bridge materials that modified the adhesion structures of cells cultured on nanomembranes with opening and closing geometry. To perform the proof-of-concept experiments, we fabricated two types of anodized alumina oxide substrates with single-sided opening (i.e., one side open, but closed at the other side) and double-sided opening (i.e., both sides open). In our experiment, we compared the densities of pores formed and of bridge materials which differently act as connective proteins depending on the size of pores. The results show that the pore opening geometry can be used to promote the net contact force between pores, resulting in the growth and formation of pore bridge materials before and after cell culture. The results also imply that the bridge materials can be used to attract the structural protrusion of filopodia that can promote the adhesion of cell-to-cell and cell-to-pore bridge. It is observed that the shape and size of cellular structures of filopodia depend on the presence of pore bridge materials. Overall, this observation brought us a significant clue that cells cultured on nanopore substrates would change the adhesion property depending on not only the formation of nanopores formed on the surface of topological substrates, but also that of pore bridge materials by its morphological growth.

  3. [Heel pressure ulcers. Comparative study between heel protective bandage and hydrocellular dressing with special form for the heel].

    Science.gov (United States)

    Torra i Bou, Joan-Enric; Rueda López, Justo; Camañes, Gemma; Herrero Narváez, Elias; Blanco Blanco, Joan; Martínez-Esparza, Elvira Hernández; Aneas Alcántara, Jesús; Verdú Soriano, José

    2002-05-01

    The heels, together with the sacra area, are one of the most frequent spots where pressure sores appear here in Spain. Any preventive measure against pressure sores on heels needs be oriented towards two main objectives: effective relief of pressure and its compatibility with localized care and skin inspection in order to detect lesions early on at least once a day. The authors planned a comparative, multi-centered, open, labeled and controlled study in which patients were assigned to two groups receiving these treatments: one received traditional preventive pressure sore treatment and a protective bandage on their heels while the other used a special Allevyn Heel hydrocellular dressing to protect their heels. The patients took part in this study over an eight week period. The response variable used to determine the effectiveness of the preventive measure in this study was the appearance of pressure sores. At the beginning, 130 patients were included in this study, 65 in each one of the treatment groups. In the bandage group, 50 patients finished this study while 61 in the dressing group finished this study. The appearance of pressure sores in the protective bandage group occurred in 44% of the patients, 22 out of 50, while in the dressing group, the occurrence rate was 3.3%, 2 out of 61 patients with a value of "ji" squared p pressure sore brought us a value of relative risk of 13.42 (IC 95%: 3.31-54.3) in the group wearing the protective bandage compared to the group wearing the dressing. The results of this study allow us to accept as valid the alternate hypothesis that there exist significant statistical differences between both treatment methods in favor of the Allevyn Heel dressing instead of the protective heel bandage. The use of this dressing, even though it is more expensive a priori than the protective bandage, in terms of unit cost for the product, has proven to be more effective in preventing pressure sores, and cheaper than the protective bandage if

  4. Using natural local materials for developing special radiation shielding concretes, and deduction of its shielding characteristics

    International Nuclear Information System (INIS)

    Kharita, M. H.; Takeyeddin, M.; Al-Nassar, M.; Yousef, S.

    2006-06-01

    Concrete is considered as the most important material to be used for radiation shielding in facilities contain radioactive sources and radiation generating machines. The concrete shielding properties may vary depending on the construction of the concrete, which is highly relative to the composing aggregates i.e. aggregates consist about 70 - 80% of the total weight of normal concrete. In this project tow types of concrete used in Syria (in Damascus and Aleppo) had been studied and their shielding properties were defined for gamma ray from Cs-137 and Co-60 sources, and for neutrons from Am-Be source. About 10% reduction in HVL was found in the comparison between the tow concrete types for both neutrons and gammas. Some other types of concrete were studied using aggregates from different regions in Syria, to improve the shielding properties of concrete, and another 10% of reduction was achieved in comparison with Damascene concrete (20% in comparison with the concrete from Aleppo) for both neutrons and gamma rays. (author)

  5. Availability of special local rock materials for using in radiation shielding concrete

    International Nuclear Information System (INIS)

    Rammah, S.; Al-Hent, R.; Aissa, M.; Yousef, S.

    2003-11-01

    Concrete is an excellent and versatile material for using in radiation shielding of nuclear power plants, hot cells and medical facilities that deal with ionizing radiations, Because it is easy controlled with composition and density by using aggregates with high specific gravity such as Barite, Hematite, Magnetite, or minerals with high hydrogen content such as Serpentine. This research offered the essential information about local resources rocks and minerals can be used in this inclination, as aggregates for heavy/high hydrion concrete. The present work indicates that iron ores, which located in RAJO-EFREEN is better than other locations like ANTI-LEBANON or AL-KADMOUS. While the heavy beach sands in AL-BASSIT are the best compared with other locations on the Syrian seaside, because it has acceptable percentage of heavy mineral. Barite concretions were found in KALAMON, HOMS and other sites, which its percentages approach 50%, but however in small quantities. Finally, high hydrion concrete can be used by Serpentinite were found with high Serpentine percentage in BAYER and BASSIT blocks. (author)

  6. Technological physics and special materials: wood-plastic composites obtained by radiation polymerization

    International Nuclear Information System (INIS)

    Peteu, Gh.; Iliescu, V.

    1995-01-01

    General estimates and references are made in connection with the role of technological physics in obtaining materials with specific features. The first part of the paper presents the modification of weak wood essences as well as technological processes at bench-scale and semi industrial scale of wood-plastic composites, under various irradiation conditions. Two technological installations for the fabrication of wood-plastic composites on both scales with technical and practical specifications of their performances are presented. Experimental data for different wood-plastic composite systems using some local wood essences in combination with several polymer and copolymer systems are given. Impregnation and polymerization levels are mentioned for every specific system. The radiation dose rate and integrated dose are given for every experimental polymerization system. The features of the wood-plastic composites are compared with the initial wood essences. Finally, a few technical and economic assessments of wood-plastic composites and their implications in the domestic economy are presented. (author)

  7. Superconductors, analysis and applications, with special reference to the utilisation of bulk (Re)BCO materials

    Energy Technology Data Exchange (ETDEWEB)

    Coombs, T.A., E-mail: tac1000@cam.ac.u [University of Cambridge, Department of Engineering, Trumpington Street, Cambridge CB2 1PZ (United Kingdom)

    2010-11-01

    The Electrical Power and Energy Conversion (EPEC) superconductivity group at Cambridge University has been working on the application of superconductivity to large scale devices. This work is taking place over a range of areas which cover FCLs, motors and generators, SMES, accelerator magnets and MRI. The research is underpinned by advanced modelling techniques using both pure Critical State models and E-J models to analyse the behaviour of the superconductors. As part of the device design we are concentrating on the analysis of AC losses in complicated geometries such as are found in motor windings and the magnetisation of bulk superconductors to enable their full potential to be realised. We are interested in the full range of high-temperature superconductors and have measured and predicted the performance of YBCO, MgB{sub 2} and BSCCO at a range of temperatures and in wire, tape and bulk forms. This paper concentrates on recent work which includes: modelling of coils using formulations based on H and A. A critical state model for the analysis of coils in SMES; crossed field effects in bulk superconductors; a magnetic model together with experimental results which explain and describe the method of flux pumping whereby a bulk superconductor can be magnetised to a high flux density using a repeatedly applied field of low flux density and finally a new configuration for MRI magnets

  8. Standard format and content of a licensee physical protection plan for strategic special nuclear material in transit - April 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A predetermined plan to respond to safeguards contingency events is required to be prepared, based on personnel and other physical protection resources described in the Physical Protection Plan for strategic special nuclear material (SSNM) in transit. Specific requirements for the contingency plan are provided in Appendix C. Licensee Safeguards Contingency Plans, to 10 CFR Part 73. Regulatory Guide 5.56, Standard Format and Content of Safeguards Contingency Plans for Transportation, provides guidance for the preparation of transportation contingency plans. Licensee is reminded that all three submissions - the Physical Protection Plan, the Physical Protection Arrangements for Specific Shipments, and the Safeguards Contingency Plan - together describe the system for physical protection of each particular shipment. They should be developed and maintained to be completely consistent with each other for each shipment

  9. Investigations and characterization of the microstructure of special ceramic materials using the high-resolution electron microscope

    International Nuclear Information System (INIS)

    Kirn, M.

    1979-01-01

    The possibilities to characterize phases and microstructures by direct lattice imaging are indicated in the following work. Ceramic materials are particularly suitable for this as these exhibit a high mechanical stability in the investigation in the transmission electron microscope. First of all the fundamentals of the high-resolution electron microscopy are introduced and the various resulting possibilities to characterize microstructures are presented. A report then follows on experimental observations on undisturbed crystals of special ceramics on a Si 3 N 4 basis. Furthermore, it is shown that the high-resolution electron microscope provides valuable contributions to the determination of structure, in particular of twin variants. Finally, revealing information on the structure of the interfaces was obtained with the help of high-resolution electron microscopy. (orig./IHOE) [de

  10. Proton-conductive materials formed by coumarin photocrosslinked ionic liquid crystal dendrimers

    NARCIS (Netherlands)

    Concellon, A.; Liang, T.; Schenning, A.P.H.J.; Luis Serrano, J.; Romero, P.; Marcos, M.

    2018-01-01

    In this work, we have successfully examined for the first time the use of ionic dendrimers as building blocks for the preparation of 1D and 2D proton conductive materials. For this purpose, a new family of liquid crystalline dendrimers has been synthesized by ionic self-assembly of poly(amidoamine)

  11. YIELD FORMING EFFECT OF APPLICATION OF COMPOSTS CONTAINING POLYMER MATERIALS ENRICHED IN BIOCOMPONENTS

    Directory of Open Access Journals (Sweden)

    Florian Gambuś

    2014-01-01

    Full Text Available In a pot experiment the impact of composts containing polymeric materials modified with biocomponents on the diversity of crops of oats and mustard was examined. The composts used in the study were produced in the laboratory from wheat and rape straw, and pea seed cleaning waste with 8-percent addition of chopped biopolymer materials (films which were prepared in the Central Mining Institute (GIG in Katowice. Three polymers differing in content of starch and density were selected for the composting. The pot experiment was conducted on three substrates: light and medium soil and on the sediment obtained after flotation of zinc and lead ores, coming from the landfill ZGH “Boleslaw” S.A. in Bukowno. The need for using such materials and substrates results from the conditions of processing some morphological fractions of municipal waste and from improving methods of reclamation. Yield enhancing effect of composts depends on the substrate on which the compost was used, cultivated plants and crop succession. Application of composts prepared with 8% of polymeric materials based on polyethylene, modified with starch as biocomponent, resulted in significantly lower yields in sandy (light soil in case of oats and, in some cases, in medium soil. Subsequent plant yield did not differ significantly between the objects fertilized with compost.

  12. Research of Acoustic Properties of Materials with the Purpose of Their Use at Design of Special Noise Protective Clothes for Oil and Gas Industry

    Science.gov (United States)

    Drofa, E. A.; Lipilina, E. Yu

    2018-01-01

    The article is devoted to the substantiation of the choice of a rational package of materials, which has the greatest noise-protective properties when designing special clothes with reference to the oil and gas industry. Studies were conducted to assess the factors that have the most significant effect on the noise-protective properties of clothing. Conclusions are made about the possibility of using the developed technique for studying the noise-protective properties of materials in selecting rational packages of materials for the production of special clothes with high noise-protective properties.

  13. A Novel Manufacturing Processing Route for Forming High-Density Ceramic Armor Materials: Phase I - SBIR

    National Research Council Canada - National Science Library

    Raman, Ramas

    1999-01-01

    .... The effects of applied pressure and pressure-transmitting media (PTM) temperature in controlling density, as well as thermal management issues to prevent cracking in applying the CS/Ceracon process to form TiC and TiB2, have been identified...

  14. Chemical form of tritium released from solid breeder materials and the influences of it on a bred tritium recovery systems

    International Nuclear Information System (INIS)

    Furukubo, Y.; Nishikawa, M.; Nishida, Y.; Kinjyo, T.; Tanifuji, Takaaki; Kawamura, Yoshinori; Enoeda, Mikio

    2004-01-01

    The ratio of HTO in total tritium was measured at release of the bred tritium to the purge gas with hydrogen using the thermal release after irradiation method, where neutron irradiation was performed at JRR-3 reactor in JAERI or KUR reactor in Kyoto University. It is experimentally confirmed in this study that not a small portion of bred tritium is released to the purge gas in the form of HTO form ceramic breeder materials even when hydrogen is added to the purge gas. The chemical composition is to be decided by the competitive reaction at the grain surface of a ceramic breeder material where desorption reaction, isotope exchange reaction 1, isotope exchange reaction 2 and water formation reaction are considered to take part. Observation in this study implies that it is necessary to have a bred tritium recovery system applicable for both HT and HTO form to recover whole bred tritium. The chemical composition also decides the amount of tritium transferable to the cooling water of the electricity generation system through the structural material in the blanket system. Permeation behavior of tritium through some structural materials at various conditions are also discussed. (author)

  15. Special aspects for forming the interiors of thai shopping malls through the use of the biological approach

    Science.gov (United States)

    Kuznetsova, Iryna O.; Rosliakova, Ljubov V.; Zakharchuk, Viktorija L.; Samosudova, Natalia

    2017-10-01

    This study reviews the biological approach to Thai shopping mall’s interior design planning. The authors defined the principles of the mall’s design optimization in Thailand on the basis of the imitation of biological samples at constructive, art-compositional, organizational and ecological levels. The analysis of forming the shopping malls interiors and space-planning solutions is based on the imitation of eight basic levels of organization of living things: molecules, cells, tissues, organs, organisms, populations, ecosystem and biosphere. The examples of the direct and implicit application of biological analogues were demonstrated in the architecture and design of Thai shopping malls. In the study, the shopping mall is regarded as an open self-sufficient system with a high level of autonomy and a fortified structural organization that includes various functional components. On the basis of the analysis of existing Thai shopping malls, a list of the basic requirements for the design of the malls was compiled. This corresponds to the needs and desires of the modern customer and ensures the competitiveness of the establishment. The phenomenon of multisensory design approach that enhances the psychophysical comfort of the shopping mall visitors is described. Socio-cultural and geographical factors were identified which determine the development of biodesign in Thailand. The article reveals the potential for a combination of biology and design to enhance the aesthetics, ergonomics and efficiency of the shopping malls. The prospects within the development of this field and the possibility of applying the solutions in practice were explored.

  16. Cystography in infants and children: a critical appraisal of the many forms with special regard to voiding cystourethrography

    Energy Technology Data Exchange (ETDEWEB)

    Riccabona, Michael [Department of Radiology, Division of Pediatric Radiology, University Hospital Graz, LKH Graz, Auebruggenplatz, 8036 Graz (Austria)

    2002-12-01

    The aim of this study was to describe and discuss the various forms of cystography and their clinical value. Conventional fluoroscopic voiding cystourethrography (VCU), radionuclide cystography and the various sonographic cystographic approaches, including echo-enhanced cystosonography (EECS), are described. Their indications, potential, benefit and setbacks/restrictions are discussed with regard to the literature and the constantly changing clinical demand. With the introduction of EECS a new and reliable tool has been established to be useful for follow-up and screening for vesico-ureteral reflux (VUR); however, with the growing importance of functional disturbances a reliable method to evaluate both function and anatomy/VUR as offered by modified VCU is mandatory, and thus VCU remains to play a major part in evaluating children with urinary tract infection, suspected VUR, hydronephrosis or functional bladder disturbances. While EECS offers a new method for certain indications, such as follow-up examinations in VUR or screening, VCU remains an irreplaceable tool for evaluating anatomy (particularly the male urethra) and bladder function (if performed using the modified technique). (orig.)

  17. Cystography in infants and children: a critical appraisal of the many forms with special regard to voiding cystourethrography

    International Nuclear Information System (INIS)

    Riccabona, Michael

    2002-01-01

    The aim of this study was to describe and discuss the various forms of cystography and their clinical value. Conventional fluoroscopic voiding cystourethrography (VCU), radionuclide cystography and the various sonographic cystographic approaches, including echo-enhanced cystosonography (EECS), are described. Their indications, potential, benefit and setbacks/restrictions are discussed with regard to the literature and the constantly changing clinical demand. With the introduction of EECS a new and reliable tool has been established to be useful for follow-up and screening for vesico-ureteral reflux (VUR); however, with the growing importance of functional disturbances a reliable method to evaluate both function and anatomy/VUR as offered by modified VCU is mandatory, and thus VCU remains to play a major part in evaluating children with urinary tract infection, suspected VUR, hydronephrosis or functional bladder disturbances. While EECS offers a new method for certain indications, such as follow-up examinations in VUR or screening, VCU remains an irreplaceable tool for evaluating anatomy (particularly the male urethra) and bladder function (if performed using the modified technique). (orig.)

  18. THE MODEL CONSTRUCTIONS OF PRICE FORMING OF BUILDING MATERIALS MANUFACTURE IN BASHKORTOSTAN

    Directory of Open Access Journals (Sweden)

    H.N. Gizatullin

    2007-06-01

    Full Text Available In this work attempt has been done analyze the influence of the environmental factors, as outward, as inside to choice of the strategy and the pricing of the industry of the building materials of Bashkortostan. This article examines the competitive surroundings of enterprises and branches in a aspect of the regional market of the building industry’s production. The evaluation of the compatibility is given of the price and competitive strategy. As a result of the research and pricing majority of industry’s enterprises had no official document stating their per pose in a pricing area. In reason of analysis the general situation of the industry building materials the enterprises of Bashkortostan, the conception of pricing is determined on functional level.

  19. Application of titanates, niobates, and tantalates to neutralized defense waste decontamination: materials properties, physical forms, and regeneration techniques. Final report

    International Nuclear Information System (INIS)

    Dosch, R.G.

    1981-01-01

    A study of the application of sodium titanate (ST) to the decontamination of neutralized defense waste has been completed. The work was directed at Sr removal from dissolved salt cake, simulated in this work with a 6.0 N NaNO 3 - 0.6 N NaOH solution. Three physical forms of the titanates were developed including powder, pellets, and titanate-loaded resin beads and all were found to be superior to conventional organic ion exchange in this application. When spent, the titanate materials can be calcined to an oxide from which is a stable waste form in itself or can be added directly to a glass melter to become part of a vitrified waste form. Radiation stability of titanate powder and resin forms was assessed in tests in which these materials were exposed to 60 Co radiation. The strontium exchange capacity of the powder remained constant through a dose of 3 x 10 7 rads and retained 50% capacity after a dose of 2 x 10 9 rads. The primary mechanism involved in loss of capacity was believed to be heating associated with the irradiation. The resin forms were unchanged through a dose of 5 x 10 8 rads and retained 30% capacity after a dose of 2 x 10 9 rads. The latter dose resulted in visible degradation of the resin matrix. Anion exchange resins loaded with sodium niobate and sodium tantalate were also prepared by similar methods and evaluated for this application. These materials had Sr sorption properties comparable to the titanate material; however, they would have to provide a significant improvement to justify their higher cost

  20. Ionizing radiation thickness meters for materials in the form of sheets, coatings or laminates

    International Nuclear Information System (INIS)

    1979-04-01

    The draft standard deals with definitions and test methods for all measuring instruments used in connection with ionizing radiation, either for continuous operation or for discontinuous control measurements of plane materials or coating. It applies to systems where the signal relates directly to the measured value as well as to systems where the signal refers to the deviation from a given rated value. (orig./RW) [de

  1. Preparation of glass-forming materials from granulated blast furnace slag

    Science.gov (United States)

    Alonso, M.; Sáinz, E.; Lopez, F. A.

    1996-10-01

    Glass precursor materials, to be used for the vitrification of hazardous wastes, have been prepared from blast furnace slag powder through a sol-gel route. The slag is initially reacted with a mixture of alcohol (ethanol or methanol) and mineral acid (HNO3 or H2SO4) to give a sol principally consisting of Si, Ca, Al, and Mg alkoxides. Gelation is carried out with variable amounts of either ammonia or water. The gelation rate can be made as fast as desired by adding excess hydrolizing agent or else by distilling the excess alcohol out of the alkoxide solution. The resulting gel is first dried at low temperature and ground. The powder thus obtained is then heat treated at several temperatures. The intermediate and final materials are characterized by thermal analysis, infrared (IR) spectroscopy, X-ray diffraction, scanning electron microscopy (SEM), and chemical analysis. From the results, the operating conditions yielding a variety of glass precursors differing in their composition are established. The method, in comparison with direct vitrification of slag, presents a number of advantages: (1) the glass precursor obtained devitrifies at higher temperatures; (2) it enables the adjustment, to a certain extent, of the chemical composition of the glass precursor; and (3) it permits recovering marketable materials at different stages of the process.

  2. Preparation and flammability of high density polyethylene/paraffin/organophilic montmorillonite hybrids as a form stable phase change material

    International Nuclear Information System (INIS)

    Cai, Yibing; Hu, Yuan; Song, Lei; Kong, Qinghong; Yang, Rui; Zhang, Yinping; Chen, Zuyao; Fan, Weicheng

    2007-01-01

    A kind of form stable phase change material (PCM) based on high density polyethylene (HDPE), paraffin, organophilic montmorillonite (OMT) and intumescent flame retardant (IFR) hybrids is prepared by using a twin screw extruder technique. This kind of form stable PCM is made of paraffin as a dispersed phase change material and HDPE as a supporting material. The structure of the montmorillonite (MMT) and OMT is characterized by X-ray diffraction (XRD) and high resolution electron microscopy (HREM). The analysis indicates that the MMT is a kind of lamellar structure, and the structure does not change after organic modification. However, the structure of the hybrid is evidenced by the XRD and scanning electronic microscope (SEM). Its thermal stability, latent heat and flame retardant properties are given by the Thermogravimetry analysis (TGA), differential scanning calorimeter (DSC) method and cone calorimeter, respectively. Synergy is observed between the OMT and IFR. The XRD result indicates that the paraffin intercalates into the silicate layers of the OMT, thus forming a typically intercalated hybrid. The SEM investigation and DSC result show that the additives of OMT and IFR have hardly any effect on the HDPE/paraffin three dimensional netted structure and the latent heat. In TGA curves, although the onset of weight loss of flame-retardant form stable PCMs occur at a lower temperature than that of form stable PCM, flame-retardant form stable PCMs produce a large amount of char residue at 700 o C. The synergy between OMT and IFR leads to the decrease of the heat release rate (HRR), contributing to improvement of the flammability performance

  3. Reversible and Irreversible Behavior of Glass-forming Materials from the Standpoint of Hierarchical Dynamical Facilitation

    Science.gov (United States)

    Keys, Aaron

    2013-03-01

    Using molecular simulation and coarse-grained lattice models, we study the dynamics of glass-forming liquids above and below the glass transition temperature. In the supercooled regime, we study the structure, statistics, and dynamics of excitations responsible for structural relaxation for several atomistic models of glass-formers. Excitations (or soft spots) are detected in terms of persistent particle displacements. At supercooled conditions, we find that excitations are associated with correlated particle motions that are sparse and localized, and the statistics and dynamics of these excitations are facilitated and hierarchical. Excitations at one point in space facilitate the birth and death of excitations at neighboring locations, and space-time excitation structures are microcosms of heterogeneous dynamics at larger scales. Excitation-energy scales grow logarithmically with the characteristic size of the excitation, giving structural-relaxation times that can be predicted quantitatively from dynamics at short time scales. We demonstrate that these same physical principles govern the dynamics of glass-forming systems driven out-of-equilibrium by time-dependent protocols. For a system cooled and re-heated through the glass transition, non-equilibrium response functions, such as heat capacities, are notably asymmetric in time, and the response to melting a glass depends markedly on the cooling protocol by which the glass was formed. We introduce a quantitative description of this behavior based on the East model, with parameters determined from reversible transport data, that agrees well with irreversible differential scanning calorimetry. We find that the observed hysteresis and asymmetric response is a signature of an underlying dynamical transition between equilibrium melts with no trivial spatial correlations and non-equilibrium glasses with correlation lengths that are both large and dependent upon the rate at which the glass is prepared. The correlation

  4. Detection of special nuclear material from delayed neutron emission induced by a dual-particle monoenergetic source

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, M. [Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, Pennsylvania 16802 (United States); Nattress, J.; Jovanovic, I., E-mail: ijov@umich.edu [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, Michigan 48109 (United States)

    2016-06-27

    Detection of unique signatures of special nuclear materials is critical for their interdiction in a variety of nuclear security and nonproliferation scenarios. We report on the observation of delayed neutrons from fission of uranium induced in dual-particle active interrogation based on the {sup 11}B(d,n γ){sup 12}C nuclear reaction. Majority of the fissions are attributed to fast fission induced by the incident quasi-monoenergetic neutrons. A Li-doped glass–polymer composite scintillation neutron detector, which displays excellent neutron/γ discrimination at low energies, was used in the measurements, along with a recoil-based liquid scintillation detector. Time-dependent buildup and decay of delayed neutron emission from {sup 238}U were measured between the interrogating beam pulses and after the interrogating beam was turned off, respectively. Characteristic buildup and decay time profiles were compared to the common parametrization into six delayed neutron groups, finding a good agreement between the measurement and nuclear data. This method is promising for detecting fissile and fissionable materials in cargo scanning applications and can be readily integrated with transmission radiography using low-energy nuclear reaction sources.

  5. Development and application of special instrumentation for materials accountancy and process control in spent fuel recycle plants

    International Nuclear Information System (INIS)

    Clark, P.A.; Gardner, N.; Merrill, N.H.; Whitehouse, K.R.

    1996-01-01

    Safe and optimum operations of spent fuel recycle plants rely on the availability of real time measurement systems at key points in the process. More than thirty types of special instrument systems have been developed and commissioned on the THORP reprocessing plant at Sellafield. These systems are compiled together with the associated information on measurement purpose, measurement technique and plant performance. A number of these measurement systems are of interest to support Safeguards arrangements on the plant. A more detailed overview of two such instrument systems respectively within the Head End and Product Finishing Stages of THORP is provided. The first of these is the Hulls Monitor, based on high resolution gamma spectrometry, as well as active and passive neutron measurements, of the basket of leached fuel cladding. This provides vital data for criticality assurance, nuclear material accountancy and inventory determination for ultimate disposal of the cladding waste. The second system is the Plutonium Inventory Monitoring System (PIMS) which employs passive neutron counting from a distributed array of neutron detectors within the Pu Finishing Line. This provides a near real time estimate of Pu inventories both during operations and at clean out of the Finishing Line. Both the Hulls Monitor and PIMS technologies are applicable to MOX Fuel recycle. Both systems enhance the control of fissile material in key areas of the recycle process which are of interest to the Safeguards authorities. (author)

  6. Synthesis and Self-Assembly of Chiral Cylindrical Molecular Complexes: Functional Heterogeneous Liquid-Solid Materials Formed by Helicene Oligomers

    Directory of Open Access Journals (Sweden)

    Nozomi Saito

    2018-01-01

    Full Text Available Chiral cylindrical molecular complexes of homo- and hetero-double-helices derived from helicene oligomers self-assemble in solution, providing functional heterogeneous liquid-solid materials. Gels and liotropic liquid crystals are formed by fibril self-assembly in solution; molecular monolayers and fibril films are formed by self-assembly on solid surfaces; gels containing gold nanoparticles emit light; silica nanoparticles aggregate and adsorb double-helices. Notable dynamics appears during self-assembly, including multistep self-assembly, solid surface catalyzed double-helix formation, sigmoidal and stairwise kinetics, molecular recognition of nanoparticles, discontinuous self-assembly, materials clocking, chiral symmetry breaking and homogeneous-heterogeneous transitions. These phenomena are derived from strong intercomplex interactions of chiral cylindrical molecular complexes.

  7. Hydroceramics, a ''new'' cementitious waste form material for U.S. defense-type reprocessing waste

    International Nuclear Information System (INIS)

    Siemer, Darryl D.

    2002-01-01

    A ''hydroceramic'' (HC) is a concrete which possesses mineralogy similar to the zeolitized rock indigenous to the USA's current ''basis'' high level radioactive waste (HLW) repository site, Yucca Mountain (YM). It is made by curing a mixture of inorganic waste, calcined clay, vermiculite, Na 2 S, NaOH, plus water under hydrothermal conditions. The product differs from conventional Portland cement and/or slag-based concretes (''grouts'') in that it is primarily comprised of alkali aluminosilicate ''cage minerals'' (cancrinites, sodalites, and zeolites)rather than hydrated calcium silicates (C-S-H in cement-chemistry shorthand). Consequently it microencapsulates individual salt molecules thereby rendering them less leachable than they are from conventional grouts. A fundamental difference between the formulations of HCs and radwaste-type glasses is that the latter contain insufficient aluminum to form insoluble minerals with all of the alkali metals in them. This means that the imposition of worst-case ''repository failure'' (hydrothermal) conditions would cause a substantial fraction of such glasses to alter to water-soluble forms. Since the same conditions tend to reduce the solubility of HC concretes, they constitute a more rugged immobilization sub-system. This paper compares leach characteristics of HCs with those of radwaste-type glasses and points out why hydroceramic solidification makes more sense than vitrification for US defense-type reprocessing waste. (orig.)

  8. Mechanism of forming interfacial intermetallic compounds at interface for solid state diffusion bonding of dissimilar materials

    International Nuclear Information System (INIS)

    He, P.; Liu, D.

    2006-01-01

    The formation of brittle intermetallic compounds at the interfaces of diffusion bonds is the main cause which leads to poor bond strength. Therefore, it is very important to study and establish the formation and growth model of intermetallic compounds at the interfaces for the control process of diffusion bonding. In this paper, according to the diffusion kinetics and the thermodynamics, the principle of formation of intermetallic compounds at interfaces in the multi-component diffusion couple, the flux-energy principle, is put forward. In the light of diffusion theory, the formation capacity of the phase at the interfaces is determined by specific properties of the composition in the diffusion couple and the composition ratio of the formed phase is in agreement with the diffusion flux. In accordance with the flux-energy principle, the microstructure of the Ni/TC4 interface is Ni/TiNi 3 /TiNi/Ti 2 Ni/TC4, the microstructure of the TC4/00Cr18Ni9Ti interface is 00Cr18Ni9Ti/TiFe 2 /TiFe/Ti 2 Fe/TC4, and the microstructure of the TiAl/40Cr interface is 40Cr/TiC/Ti 3 Al + FeAl + FeAl 2 /TiAl. Multi-intermetallic compounds with the equivalent flux-energy can be formed at the interfaces at the same time

  9. Biofilm forming ability of Sphingomonas paucimobilis isolated from community drinking water systems on plumbing materials used in water distribution.

    Science.gov (United States)

    Gulati, Parul; Ghosh, Moushumi

    2017-10-01

    Sphingomonas paucimobilis, an oligotroph, is well recognized for its potential for biofilm formation. The present study explored the biofilm forming ability of a strain isolated from municipal drinking water on plumbing materials. The intensity of biofilm formation of this strain on different plumbing materials was examined by using 1 × 1 cm 2 pieces of six different pipe materials, i.e. polyvinyl chloride (PVC), polypropylene (PP), polyethylene (PE), aluminium (Al), copper (Cu) and rubber (R) and observing by staining with the chemical chromophore, Calcofluor. To understand whether biofilm formation occurs under flow through conditions, a laboratory-scale simulated distribution system, comprised of the above materials was fabricated. Biofilm samples were collected from the designed system at different biofilm ages (10, 40 and 90 hours old) and enumerated. The results indicated that the biofilm formation occurred on all plumbing materials with Cu and R as exceptions. The intensity of biofilm formation was found to be maximum on PVC followed by PP and PE. We also demonstrated the chemical chromophore (Calcofluor) successfully for rapid and easy visual detection of biofilms, validated by scanning electron microscope (SEM) analysis of the plumbing materials. Chlorination has little effect in preventing biofilm development.

  10. Graphene/phase change material nanocomposites: light-driven, reversible electrical resistivity regulation via form-stable phase transitions.

    Science.gov (United States)

    Wang, Yunming; Mi, Hongyi; Zheng, Qifeng; Ma, Zhenqiang; Gong, Shaoqin

    2015-02-04

    Innovative photoresponsive materials are needed to address the complexity of optical control systems. Here, we report a new type of photoresponsive nanomaterial composed of graphene and a form-stable phase change material (PCM) that exhibited a 3 orders of magnitude change in electrical resistivity upon light illumination while retaining its overall original solid form at the macroscopic level. This dramatic change in electrical resistivity also occurred reversibly through the on/off control of light illumination. This was attributed to the reversible phase transition (i.e., melting/recrystallization) behavior of the microscopic crystalline domains present in the form-stable PCM. The reversible phase transition observed in the graphene/PCM nanocomposite was induced by a reversible temperature change through the on/off control of light illumination because graphene can effectively absorb light energy and convert it to thermal energy. In addition, this graphene/PCM nanocomposite also possessed excellent mechanical properties. Such photoresponsive materials have many potential applications, including flexible electronics.

  11. Influence of corn flour as pore forming agent on porous ceramic material based mullite: Morphology and mechanical properties

    Directory of Open Access Journals (Sweden)

    Ayala-Landeros J.G.

    2016-01-01

    Full Text Available Porous material was processed by the mixing, molding and pressing the ceramic material, afterward burnout and sintering; through the forming porous, using corn flour at different concentration (10, 15 and 20 wt.% as a pore forming agent; in order to determinate the influence of porous on the mechanical, morphological and structural properties. The effect of the volume fraction of corn flour in the mullite matrix, at various sintering temperature from 1100, 1200, 1300 and 1500°C were tested by Diffraction X ray, showing changes in crystalline phases of mullite (3Al2O3-2SiO2, as result of sintered temperatures. Presence of talcum powder in formula, also cause the formation of the cordierite and cristobalite crystalline phases, giving stability and adhesion to the structure of ceramic material. When sintering at temperatures between 1300 to 1500°C, and it was used the concentration of corn flour 15-20 wt.% as forming agent porous, it was found the better mechanical properties. The scanning electron microscopy analysis shows the presence of open porosity and anisotropy.

  12. The effects of topology on the structural, dynamic and mechanical properties of network-forming materials

    International Nuclear Information System (INIS)

    Wilson, Mark

    2012-01-01

    The effects of network topology on the static structural, mechanical and dynamic properties of MX 2 network-forming liquids (with tetrahedral short-range order) are discussed. The network topology is controlled via a single model parameter (the anion polarizability) which effectively constrains the inter-tetrahedral linkages in a physically transparent manner. Critically, it is found to control the balance between the stability of corner- and edge-sharing tetrahedra. A potential rigidity transformation is investigated. The vibrational density of states is investigated, using an instantaneous normal model analysis, as a function of both anion polarizability and temperature. A low frequency peak is seen to appear and is shown to be correlated with the fraction of cations which are linked through solely edge-sharing structural motifs. A modified effective mean atom coordination number is proposed which allows the appearance of the low frequency feature to be understood in terms of a mean field rigidity percolation threshold. (paper)

  13. Targets and special materials

    International Nuclear Information System (INIS)

    Blanc, R.; Bouriant, M.; Richaud, J.P.

    1997-01-01

    The target preparation group supplied a large number of samples to nuclear physicists for experiments using SARA and also other accelerators throughout the world. Particular preparation and projects include: 208 Pb, 116 Cd, 6 LiF, 123 Sb, In and Ta targets, strippers for SARA and GANIL, optical silicone disks for POLDER and GRAAL experiments, active participations for the AMS project and finally filament preparation for the GENEPI project. (authors)

  14. High-functionalization of fiber-forming materials. Polymer membrane as separation media

    Energy Technology Data Exchange (ETDEWEB)

    Kamide, Kenji; Iijima, Hideki (Asahi Chemical Industry Co. Ltd., Osaka, (Japan))

    1989-07-05

    For obtaining higher functions by donating specific functions to the fiber, it is effective to change its structure. Various separating films which is known as an example of the high-functionalization of the fiber materials is an example of the fiber structure conversion from the view-point of substance-permeating function. This report firstly describes the features and types of the film separation method and the production of films, and then on the correlation between the structure and functions of the fibers, the correlation of the structure and the separating characteristics of the films, and the mechanism of the emergence of the film structure. Finally, applied examples of the film separating method in the medical field are described. In the medical liquid film separation, blood or plasma are the object of the separation. Blood has various components whose concentration and particle size are multiplicated, and yet requires a tremendous separating accuracy when compared with the industrial separation. Examples are a blood dialyzer film and an ultrafiltration film (film for plasma separation and virus separation), etc.. 28 refs., 6 figs., 2 tabs.

  15. Transmission FTIR derivative spectroscopy for estimation of furosemide in raw material and tablet dosage form

    Directory of Open Access Journals (Sweden)

    Máximo Gallignani

    2014-10-01

    Full Text Available A Fourier transform infrared derivative spectroscopy (FTIR-DS method has been developed for determining furosemide (FUR in pharmaceutical solid dosage form. The method involves the extraction of FUR from tablets with N,N-dimethylformamide by sonication and direct measurement in liquid phase mode using a reduced path length cell. In general, the spectra were measured in transmission mode and the equipment was configured to collect a spectrum at 4 cm−1 resolution and a 13 s collection time (10 scans co-added. The spectra were collected between 1400 cm−1 and 450 cm−1. Derivative spectroscopy was used for data processing and quantitative measurement using the peak area of the second order spectrum of the major spectral band found at 1165 cm−1 (SO2 stretching of FUR with baseline correction. The method fulfilled most validation requirements in the 2 mg/mL and 20 mg/mL range, with a 0.9998 coefficient of determination obtained by simple calibration model, and a general coefficient of variation <2%. The mean recovery for the proposed assay method resulted within the (100±3% over the 80%–120% range of the target concentration. The results agree with a pharmacopoeial method and, therefore, could be considered interchangeable.

  16. Fundamental properties of monolithic bentonite buffer material formed by cold isostatic pressing for high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Kawakami, S.; Yamanaka, Y.; Kato, K.; Asano, H.; Ueda, H.

    1999-01-01

    The methods of fabrication, handling, and emplacement of engineered barriers used in a deep geological repository for high level radioactive waste should be planned as simply as possible from the engineering and economic viewpoints. Therefore, a new concept of a monolithic buffer material around a waste package have been proposed instead of the conventional concept with the use of small blocks, which would decrease the cost for buffer material. The monolithic buffer material is composed of two parts of highly compacted bentonite, a cup type body and a cover. As the forming method of the monolithic buffer material, compaction by the cold isostatic pressing process (CIP) has been employed. In this study, monolithic bentonite bodies with the diameter of about 333 mm and the height of about 455 mm (corresponding to the approx. 1/5 scale for the Japanese reference concept) were made by the CIP of bentonite powder. The dry densities: ρd of the bodies as a whole were measured and the small samples were cut from several locations to investigate the density distribution. The swelling pressure and hydraulic conductivity as function of the monolithic body density for CIP-formed specimens were also measured. High density (ρd: 1.4--2.0 Mg/m 3 ) and homogeneous monolithic bodies were formed by the CIP. The measured results of the swelling pressure (3--15 MPa) and hydraulic conductivity (0.5--1.4 x 10 -13 m/s) of the specimens were almost the same as those for the uniaxial compacted bentonite in the literature. It is shown that the vacuum hoist system is an applicable handling method for emplacement of the monolithic bentonite

  17. Conditional release of materials from decommissioning process into the environment in the form of steel railway tracks

    International Nuclear Information System (INIS)

    Tatransky, Peter; Necas, Vladimir

    2009-01-01

    This work points to the possibilities of conditional release of materials from the process of decommissioning the nuclear unit from the operation. According to the valid legislation, materials which do not meet the condition of direct-unconditional release into the environment, should be modified and processed into the matrix designed for the final disposal in the storing place. However there exists a group of materials which activity is on the borderline of the limit of releasing into the environment and it is possible to release them conditionally. The matter of conditional release is that notable amount of materials, mainly metals, is usually contaminated only by radionuclids with relatively short time of half decay. These materials are suitable to use for a specific industrial purpose where the longtime fixation of shortly living radionuclids is expected in one place. This work deals with the conditional release of metals into the form of steel railway tracks. It describes the (working) groups of workers working with the steel railway tracks and defines in the numbers the critical group and its critical individual. For critical individual it dimensions the amounts of materials, which are possible to be released conditionally from one double-unit of the plant of the type VVER 440 V-230 which operation was ended on the regular basis. According to the calculations in the software VISIPLAN and OMEGA there is defined a number of released steel in such way that the internationally recommended rate of maximal effective dose for critical individual-10 μSv/year [IAEA, 2008. Managing low radioactivity material from the decommissioning of nuclear facility. Technical reports series no. 462] is not extended. In the final part there are compared the estimates of the costs of the decommissioning process with the application of conditional release and without it, which is directly reflected in the amount of saved costs and number of containers for surface disposal.

  18. THE EFFECT OF PREPARATION CONDITIONS OF RAPIDLY SOLIDIFIED IRON BASED GRANULES ON PROPERTIES OF COMPOSITE MATERIAL FORMED BY CASTING TECHNOLOGY

    Directory of Open Access Journals (Sweden)

    A. S. Kalinichenko

    2017-01-01

    Full Text Available The variety of requirements for friction pairs requires the development of different technologies for the production of tribological materials with reference to the operation modes. Composite materials obtained by the casting technology have been successfully applied for the normalization of the thermomechanical state of the steam turbines. These composites consist of the matrix based on copper alloys reinforced with cast iron granules. Because the structure and properties of cast iron are determined by the conditions of their production studies have been conducted on determination of preparation conditions on grain structure and properties of the synthesized composite material. Using an upgraded unit for production of granules technological regimes were determined providing narrow fractional composition. It has been found that granules formed are characterized with typical microstructure of white cast iron containing perlite and ledeburite. Microhardness of pilot cast iron granules is characterized by high values (from 7450 up to 9450 MPa and depends on the size of the fraction. Composite materials obtained using experimental granules had a microhardness of the reinforcing cast iron granules about 3500 MPa, and a bronze matrix – 1220 MPa, which is higher than the hardness of the composite material obtained by using the annealed DCL-1granules (2250 MPa. Metal base of experimental granules in the composite material has the structure of perlitic ductile iron with inclusions of ferrite not exceeding 10–15% and set around a flocculent graphite. As a result, the increase of physical-mechanical properties of finished products made of composite material is observed. 

  19. Physicochemical characterization of in situ drug-polymer nanocomplex formed between zwitterionic drug and ionomeric material in aqueous solution

    Energy Technology Data Exchange (ETDEWEB)

    Salamanca, Constain H., E-mail: chsalamanca@icesi.edu.co [Pharmaceutical physical chemistry laboratory, Department of Pharmacy, Faculty of Natural Sciences, ICESI University, Cali (Colombia); Castillo, Duvan F.; Villada, Juan D. [Pharmaceutical physical chemistry laboratory, Department of Pharmacy, Faculty of Natural Sciences, ICESI University, Cali (Colombia); Rivera, Gustavo R. [SIT Biotech GmbH, BMZ 2 Otto-Hahn-Str. 15, 44227 Dortmund (Germany)

    2017-03-01

    Biocompatible polymeric materials with the potential to form functional structures, in association with different therapeutic molecules, in physiological media, represent a great potential for biological and pharmaceutical applications. Therefore, here the formation of a nano-complex between a synthetic cationic polymer and model drug (ampicillin trihydrate) was studied. The formed complex was characterized by size and zeta potential measurements, using dynamic light scattering and capillary electrophoresis. Moreover, the chemical and thermodynamically stability of these complexes were studied. The ionomeric material, here referred as EuCl, was obtained by equimolar reaction between Eudragit E and HCl. The structural characterization was carried out by potentiometric titration, FTIR spectroscopy, and DSC. The effect of pH, time, polymer concentration and ampicillin/polymer molar ratio over the hydrodynamic diameter and zeta potential were established. The results show that EuCl ionomer in aqueous media presents two different populations of nanoparticles; one of this tends to form flocculated aggregates in high pH and concentrations, by acquiring different conformations in solution by changing from a compact to an extended conformation. Moreover, the formation of an in situ interfacial polymer-drug complex was demonstrated, this could slightly reduce the hydrolytic degradation of the drug while affecting its solubility, mainly under acidic conditions. - Highlights: • The EuCl ionomer in aqueous media presents two different populations of nanoparticle, corresponding to proximally 15 nm and 150 nm. • The EuCl ionomer in aqueous media may form different structure depending on the pH and polymer concentration, which tends to form flocculated aggregates in high pH and concentrations. • The formation of an in situ interfacial polymer-drug complex was demonstrated, which could slightly reduce the hydrolytic degradation of the drug and affecting its solubility in

  20. Nondestructive Inspection System for Special Nuclear Material Using Inertial Electrostatic Confinement Fusion Neutrons and Laser Compton Scattering Gamma-Rays

    Science.gov (United States)

    Ohgaki, H.; Daito, I.; Zen, H.; Kii, T.; Masuda, K.; Misawa, T.; Hajima, R.; Hayakawa, T.; Shizuma, T.; Kando, M.; Fujimoto, S.

    2017-07-01

    A Neutron/Gamma-ray combined inspection system for hidden special nuclear materials (SNMs) in cargo containers has been developed under a program of Japan Science and Technology Agency in Japan. This inspection system consists of an active neutron-detection system for fast screening and a laser Compton backscattering gamma-ray source in coupling with nuclear resonance fluorescence (NRF) method for precise inspection. The inertial electrostatic confinement fusion device has been adopted as a neutron source and two neutron-detection methods, delayed neutron noise analysis method and high-energy neutron-detection method, have been developed to realize the fast screening system. The prototype system has been constructed and tested in the Reactor Research Institute, Kyoto University. For the generation of the laser Compton backscattering gamma-ray beam, a race track microtron accelerator has been used to reduce the size of the system. For the NRF measurement, an array of LaBr3(Ce) scintillation detectors has been adopted to realize a low-cost detection system. The prototype of the gamma-ray system has been demonstrated in the Kansai Photon Science Institute, National Institutes for Quantum and Radiological Science and Technology. By using numerical simulations based on the data taken from these prototype systems and the inspection-flow, the system designed by this program can detect 1 kg of highly enriched 235U (HEU) hidden in an empty 20-ft container within several minutes.

  1. Study of the prompt gamma ray signal from fissions in special nuclear materials induced using an associated particle neutron generator

    International Nuclear Information System (INIS)

    Koltick, D. S.; Kane, S. Z.

    2009-01-01

    More than 42 million cargo containers entered the United States in 2005. To search for a few kilograms of special nuclear material (SNM) within this vast stream of cargo, an inspection system based on neutron-induced fission followed by the coincident detection of multiple prompt fission gamma rays is investigated using MCNP-Polimi code. The system utilizes two deuterium-tritium (DT) associated particle neutron generators, each capable of 10 9 neutrons/s at 14.1 MeV, with sub-nanosecond timing resolution ZnO:Ga alpha detectors internal to the generator. Because prompt fission signals are approximately 100 times stronger than the delayed signals, the neutron flux is greatly reduced compared to 10 11-12 neutrons/s required for systems based on delayed signals such as the 'nuclear car wash' [4]. In addition the system utilizes 30 cm deep liquid krypton (LKr) noble gas detectors having 94% detection efficiency for 1 MeV gamma rays, high solid angle coverage (∼ 50% of the total solid angle), and sub-nanosecond timing resolution (∼ 600 ps). An algorithm for distinguishing U-235 from U-238 is presented. (authors)

  2. Simultaneous sound velocity and thickness measurement by the ultrasonic pitch-catch method for corrosion-layer-forming polymeric materials.

    Science.gov (United States)

    Kusano, Masahiro; Takizawa, Shota; Sakai, Tetsuya; Arao, Yoshihiko; Kubouchi, Masatoshi

    2018-01-01

    Since thermosetting resins have excellent resistance to chemicals, fiber reinforced plastics composed of such resins and reinforcement fibers are widely used as construction materials for equipment in chemical plants. Such equipment is usually used for several decades under severe corrosive conditions so that failure due to degradation may result. One of the degradation behaviors in thermosetting resins under chemical solutions is "corrosion-layer-forming" degradation. In this type of degradation, surface resins in contact with a solution corrode, and some of them remain asa corrosion layer on the pristine part. It is difficult to precisely measure the thickness of the pristine part of such degradation type materials by conventional pulse-echo ultrasonic testing, because the sound velocity depends on the degree of corrosion of the polymeric material. In addition, the ultrasonic reflection interface between the pristine part and the corrosion layer is obscure. Thus, we propose a pitch-catch method using a pair of normal and angle probes to measure four parameters: the thicknesses of the pristine part and the corrosion layer, and their respective sound velocities. The validity of the proposed method was confirmed by measuring a two-layer sample and a sample including corroded parts. The results demonstrate that the pitch-catch method can successfully measure the four parameters and evaluate the residual thickness of the pristine part in the corrosion-layer-forming sample. Copyright © 2017 Elsevier B.V. All rights reserved.

  3. Development of a data acquisition system in form of an apparatus which is specially designed for the study of the cerebral metabolism employing radioactive tracers

    International Nuclear Information System (INIS)

    Ponchon, J.

    1988-03-01

    The subject of this thesis is the development of a data acquisition system in form of an apparatus which is specially designed for the study of cerebral metabolism employing radioactive tracers. Currently, the test is based on the continuous inhalation of gas identified with oxygen 15. After an inhalation period of 6 to 8 minutes the local brain radioactivity attains an equilibrium which corresponds to the parameters of brain metabolism. The constant measurement of the radioactivity facilitates the monitoring of the evolution of these parameters. The apparatus consists of an assemby of lead collimators in which are lodged 26 gamma ray detectors (INa probes), each one of which scans a particular brain region. For ease of use and the provision of numerous possibilities, each detector has been assigned a multichannel pulse height analyser which has been developed by ourselves in order to correspond to and to comply with the demands of our tests. They are equipped with a device which automatically corrects for dead time thereby permitting the analysis of random impulses of a rate greater than 50.000 per second with a loss of less than 1%. The multichannel analysers are connected to a central computer which by means of suitably adapted software allows the calibration of different channel of measurement, controls, the choice of the zone of interest to be integrated and the presentation of integrated results in form of graphs [fr

  4. Development of form stable Poly(methyl methacrylate) (PMMA) coated thermal phase change material for solar water heater applications

    Science.gov (United States)

    Munusamy, Y.; Shanmugam, S.; Shi-Ying, Kee

    2018-04-01

    Phase change material (PCM) is one of the most popular and widely used thermal energy storage material in solar water heater because it able to absorb and release a large amount of latent heat during a phase change process over a narrow temperature range. However the practical application of PCM is limited by two major issues; 1) leakage which leads to material loss and corrosion of tank and 2) large volume change during phase change process which cause pressure build up in the tank. In this work, form-stable PCM was prepared by coating myristic acid with Poly(methyl methacrylate) (PMMA) to prevent leakage of PCM. PMMA was mixed with different weight percentage (0.1, 0.2, 0.3, 0.4 and 0.5 wt%) of dicumyl peroxide (DCP). The purpose of adding DCP to PMMA is to crosslink the polymer and to increase the mechanical strength of PMMA to hold the myristic acid content inside the coating during the phase change process. Leakage test results showed that PMMA mixed with 0.1% DCP exhibit 0% leakage. This result is further supported by Field Emission Scanning Electron Microscopy (FESEM) images and Fourier transform infrared spectroscopy (FTIR) analysis results, where a compact and uniform coating without cracks were formed for PCM coated with PMMA with 0.1% DCP. Differential scanning calorimetry (DSC) results shows that the melting point of form-stable PCM is 55°C, freezing point is 50°C, the latent heat of melting and freezing is 67.59 J/g.

  5. Pressing device for producing compacts from source material in powder form in particular pulverized nuclear reactor fuel

    International Nuclear Information System (INIS)

    Heller, G.; Adelmann, M.; Konigs, W.; Wendorf, W.

    1984-01-01

    Pressing device for producing compacts from source material in powder form, in particular pulverized nuclear reactor fuel having a die-plate contained in platen and a bore associated with a ram, for receiving source material powder, a filling shoe, and a reservoir for powder connected by a hose to the filling shoe. The device is characterized by a passing wheel in the filling shoe as filling aid means; a tube containing a feedscrew disposed between the reservoir and hose as metering means; the reservoir having a bottom part with a can type place-on part with an opening eccentric to the axis; a coupling part and a cover part are placed on the open part of the can, these parts are also provided with a passageway to the feedscrew eccentric to the longitudinal axis

  6. Equilibrium leach tests with cobalt in the system cemented waste form/container material/aqueous solution

    International Nuclear Information System (INIS)

    Vejmelka, P.; Koester, R.; Lee, M. J.; Han, K. W.

    1991-01-01

    The equilibrium concentrations of Co in the system of cemented waste form/aqueous solutions were determined including the effect of the container material and its corrosion products under the respective conditions. The chemical conditions in the near field of the waste form were characterized by measurement of the pH and E h value. As disposal relevant solutions, saturated sodium chloride, Q-brine (main constituent MgCl 2 ) and a granitic type groundwater were used. For comparison, also experiments using deionized water were performed. In all systems investigated the cemented waste form itself has a strong influence on the chemical conditions in the near field. The pH and E h values are affected in all cases by the addition of the cemented waste form. There is no or only a slight difference between the E h values if iron powder or iron hydroxide is added to the cemented waste form/solution systems, but the E h is markedly decreased when iron powder is added to the solution free of cement. The Co concentration is decreased in all solutions by the addition of the cemented waste form, the largest effect is observed in Q-brine and this can be attributed either to the sorption of the Co-ions on the corrosion products of the cement or to the coprecipitation of Co-hydroxide and Mg-hydroxide. In the other solutions the Co concentration is decreased by precipitation of Co-hydroxide due to the high pH value of 12.5, and the concentrations are comparable for the different solutions

  7. The Text of Tile Master Agreement between the Agency and the United States of America Governing Sales of Source, By- Product and Special Nuclear Materials for research Purposes

    International Nuclear Information System (INIS)

    1974-01-01

    The text of the Master Agreement Governing Sales of Source, Bye Product and Special Nuclear Materials for Research Purposes, which has been concluded between the Agency and the Government of the United States of America, is reproduced herein for the information of all Members,

  8. Epoxy-Based Organogels for Thermally Reversible Light Scattering Films and Form-Stable Phase Change Materials.

    Science.gov (United States)

    Puig, Julieta; Dell' Erba, Ignacio E; Schroeder, Walter F; Hoppe, Cristina E; Williams, Roberto J J

    2017-03-29

    Alkyl chains of β-hydroxyesters synthesized by the capping of terminal epoxy groups of diglycidylether of bisphenol A (DGEBA) with palmitic (C16), stearic (C18), or behenic (C22) fatty acids self-assemble forming a crystalline phase. Above a particular concentration solutions of these esters in a variety of solvents led to supramolecular (physical) gels below the crystallization temperature of alkyl chains. A form-stable phase change material (FS-PCM) was obtained by blending the ester derived from behenic acid with eicosane. A blend containing 20 wt % ester was stable as a gel up to 53 °C and exhibited a heat storage capacity of 161 J/g, absorbed during the melting of eicosane at 37 °C. Thermally reversible light scattering (TRLS) films were obtained by visible-light photopolymerization of poly(ethylene glycol) dimethacrylate-ester blends (50 wt %) in the gel state at room temperature. The reaction was very fast and not inhibited by oxygen. TRLS films consisted of a cross-linked methacrylic network interpenetrated by the supramolecular network formed by the esters. Above the melting temperature of crystallites formed by alkyl chains, the film was transparent due to the matching between refractive indices of the methacrylic network and the amorphous ester. Below the crystallization temperature, the film was opaque because of light dispersion produced by the organic crystallites uniformly dispersed in the material. Of high significance for application was the fact that the contrast ratio did not depend on heating and cooling rates.

  9. Preparation and characterization of form-stable paraffin/polyurethane composites as phase change materials for thermal energy storage

    International Nuclear Information System (INIS)

    Chen, Keping; Yu, Xuejiang; Tian, Chunrong; Wang, Jianhua

    2014-01-01

    Highlights: • Paraffin/polyurethane composite as form-stable phase change material was prepared by bulk polymerization. • Paraffin/polyurethane composite possesses typical character of dual phase transition. • Total latent heat of n-eicosane/PUPCM is as high as 141.2 J/g. • Maximum encapsulation ratio for n-octadecane/PUPCM composites is 25% w/w. - Abstract: Polyurethane phase change material (PUPCM) has been demonstrated to be effective solid–solid phase change material for thermal energy storage. However, the high cost and complex process on preparation of PUPCMs with high enthalpy and broad phase transition temperature range can prohibit industrial-scale applications. In this work, a series of novel form-stable paraffin/PUPCMs composites (n-octadecane/PUPCM, n-eicosane/PUPCM and paraffin wax/PUPCM) with high enthalpy and broad phase transition temperature range (20–65 °C) were directly synthesized via bulk polymerization. The composites were prepared at different mass fractions of n-octadecane (10, 20, 25, 30% w/w). The results indicated that the maximum encapsulation ratio for n-octadecane/PUPCM10000 composites was around 25% w/w. The chemical structure and crystalline properties of these composites were characterized by Fourier transform infrared spectroscopy (FT-IR), polarizing optical microscopy (POM), wide-angle X-ray diffraction (WAXD). Thermal properties and thermal reliability of the composites were determined using differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA). From DSC analysis, the composites showed a typical dual phase change temperature. The enthalpy for the composite with 25% w/w n-eicosane was as high as 141.2 J/g. TGA analysis indicated that the composites degraded at considerably high temperatures. The process of preparation of PUPCMs and their composites was very simple, inexpensive, environmental friendly and easy to process into desired shapes, which could find the promising applications in solar

  10. Bioactivity of freeze-dried platelet-rich plasma in an adsorbed form on a biodegradable polymer material.

    Science.gov (United States)

    Nakajima, Yu; Kawase, Tomoyuki; Kobayashi, Mito; Okuda, Kazuhiro; Wolff, Larry F; Yoshie, Hiromasa

    2012-01-01

    Owing to the necessity for the immediate preparation from patients' blood, autologous platelet-rich plasma (PRP) limits its clinical applicability. To address this concern and respond to emergency care and other unpredictable uses, we have developed a freeze-dried PRP in an adsorbed form on a biodegradable polymer material (Polyglactin 910). On the polymer filaments of PRP mesh, which was prepared by coating the polymer mesh with human fresh PRP and subsequent freeze-drying, platelets were incorporated, and related growth factors were preserved at high levels. This new PRP mesh preparation significantly and reproducibly stimulated the proliferation of human periodontal ligament cells in vitro and neovascularization in a chorioallantoic membrane assay. A full-thickness skin defect model in a diabetic mouse demonstrated the PRP mesh, although prepared from human blood, substantially facilitated angiogenesis, granulation tissue formation, and re-epithelialization without inducing severe inflammation in vivo. These data demonstrate that our new PRP mesh preparation functions as a bioactive material to facilitate tissue repair/regeneration. Therefore, we suggest that this bioactive material, composed of allogeneic PRP, could be clinically used as a promising alternative in emergency care or at times when autologous PRP is not prepared immediately before application.

  11. An alternative host matrix based on iron phosphate glasses for the vitrification of specialized nuclear waste forms. Annual progress report, September 15, 1996 - September 14, 1997

    International Nuclear Information System (INIS)

    Day, D.E.; Marasinghe, K.; Ray, C.S.

    1997-01-01

    'Objectives of this project are to: (1) investigate the glass composition and processing conditions that yield optimum properties for iron phosphate glasses for vitrifying radioactive waste, (2) determine the atomic structure of iron phosphate glasses and the structure-property relationships, (3) determine how the physical and structural properties of iron phosphate glasses are affected by the addition of simulated high level nuclear waste components, and (4) investigate the process and products of devitrification of iron phosphate waste forms. The glass forming ability of about 125 iron phosphate melts has been investigated in different oxidizing to reducing atmospheres using various iron oxide raw materials such as Fe 2 O 3 , FeO, Fe 3 O 4 , and FeC 2 O 4 2H 2 O. The chemical durability, redox equilibria between Fe(II) and Fe(III), crystallization behavior and structural features for these glasses and their crystalline forms have been investigated using a variety of techniques including Mossbauer spectroscopy, X-ray absorption spectroscopy (XAS), X-ray photoelectron spectroscopy (XPS), Extended x-ray absorption fine structure (EXAFS) and X-ray absorption near edge structure (XANES) analysis, differential thermal and thermogravimetric analysis (DTA/TGA), and X-ray and neutron diffraction.'

  12. Preparation and thermal energy storage properties of paraffin/calcined diatomite composites as form-stable phase change materials

    International Nuclear Information System (INIS)

    Sun, Zhiming; Zhang, Yuzhong; Zheng, Shuilin; Park, Yuri; Frost, Ray L.

    2013-01-01

    Highlights: ► Composite phase change material (PCM) was prepared by blending composite paraffin and calcined diatomite. ► The optimum mixed proportion was obtained through differential scanning calorimetry. ► Thermal energy storage properties of the composite PCMs were determined by DSC. ► Thermal cycling test showed that the prepared PCMs are thermally reliable and chemically stable. - Abstract: A composite paraffin-based phase change material (PCM) was prepared by blending composite paraffin and calcined diatomite through the fusion adsorption method. In this study, raw diatomite was purified by thermal treatment in order to improve the adsorption capacity of diatomite, which acted as a carrier material to prepare shape-stabilized PCMs. Two forms of paraffin (paraffin waxes and liquid paraffin) with different melting points were blended together by the fusion method, and the optimum mixed proportion with a suitable phase-transition temperature was obtained through differential scanning calorimetry (DSC) analysis. Then the prepared composite paraffin was adsorbed in calcined diatomite. The prepared paraffin/calcined diatomite composites were characterized by the scanning electron microscope (SEM) and Fourier transformation infrared (FT-IR) analysis techniques. Thermal energy storage properties of the composite PCMs were determined by DSC method. DSC results showed that there was an optimum adsorption ratio between composite paraffin and calcined diatomite and the phase-transition temperature and the latent heat of the composite PCMs were 33.04 °C and 89.54 J/g, respectively. Thermal cycling test of composite PCMs showed that the prepared material is thermally reliable and chemically stable. The obtained paraffin/calcined diatomite composites have proper latent heat and melting temperatures, and show practical significance and good potential application value

  13. Preparation and thermal energy storage properties of paraffin/calcined diatomite composites as form-stable phase change materials

    Energy Technology Data Exchange (ETDEWEB)

    Sun, Zhiming [School of Chemical and Environmental Engineering, China University of Mining and Technology, Beijing 100083 (China); Chemistry Discipline, Faculty of Science and Technology, Queensland University of Technology, 2 George Street, GPO Box 2434, Brisbane, Queensland 4001 (Australia); Zhang, Yuzhong [School of Chemical and Environmental Engineering, China University of Mining and Technology, Beijing 100083 (China); Zheng, Shuilin, E-mail: shuilinzh@yahoo.com.cn [School of Chemical and Environmental Engineering, China University of Mining and Technology, Beijing 100083 (China); Park, Yuri [Chemistry Discipline, Faculty of Science and Technology, Queensland University of Technology, 2 George Street, GPO Box 2434, Brisbane, Queensland 4001 (Australia); Frost, Ray L., E-mail: r.frost@qut.edu.au [Chemistry Discipline, Faculty of Science and Technology, Queensland University of Technology, 2 George Street, GPO Box 2434, Brisbane, Queensland 4001 (Australia)

    2013-04-20

    Highlights: ► Composite phase change material (PCM) was prepared by blending composite paraffin and calcined diatomite. ► The optimum mixed proportion was obtained through differential scanning calorimetry. ► Thermal energy storage properties of the composite PCMs were determined by DSC. ► Thermal cycling test showed that the prepared PCMs are thermally reliable and chemically stable. - Abstract: A composite paraffin-based phase change material (PCM) was prepared by blending composite paraffin and calcined diatomite through the fusion adsorption method. In this study, raw diatomite was purified by thermal treatment in order to improve the adsorption capacity of diatomite, which acted as a carrier material to prepare shape-stabilized PCMs. Two forms of paraffin (paraffin waxes and liquid paraffin) with different melting points were blended together by the fusion method, and the optimum mixed proportion with a suitable phase-transition temperature was obtained through differential scanning calorimetry (DSC) analysis. Then the prepared composite paraffin was adsorbed in calcined diatomite. The prepared paraffin/calcined diatomite composites were characterized by the scanning electron microscope (SEM) and Fourier transformation infrared (FT-IR) analysis techniques. Thermal energy storage properties of the composite PCMs were determined by DSC method. DSC results showed that there was an optimum adsorption ratio between composite paraffin and calcined diatomite and the phase-transition temperature and the latent heat of the composite PCMs were 33.04 °C and 89.54 J/g, respectively. Thermal cycling test of composite PCMs showed that the prepared material is thermally reliable and chemically stable. The obtained paraffin/calcined diatomite composites have proper latent heat and melting temperatures, and show practical significance and good potential application value.

  14. Combining 3D printed forms with textile structures - mechanical and geometrical properties of multi-material systems

    International Nuclear Information System (INIS)

    Sabantina, L; Kinzel, F; Ehrmann, A; Finsterbusch, K

    2015-01-01

    The 3D printing belongs to the rapidly emerging technologies which have the chance to revolutionize the way products are created. In the textile industry, several designers have already presented creations of shoes, dresses or other garments which could not be produced with common techniques. 3D printing, however, is still far away from being a usual process in textile and clothing production. The main challenge results from the insufficient mechanical properties, especially the low tensile strength, of pure 3D printed products, prohibiting them from replacing common technologies such as weaving or knitting. Thus, one way to the application of 3D printed forms in garments is combining them with textile fabrics, the latter ensuring the necessary tensile strength. This article reports about different approaches to combine 3D printed polymers with different textile materials and fabrics, showing chances and limits of this technique. (paper)

  15. Application of ion beams in materials science of radioactive waste forms: focus on the performance of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Garrido, Frederico [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France)]. E-mail: garrido@csnsm.in2p3.fr; Nowicki, Lech [Andrzej Soltan Institute for Nuclear Studies, Hoza 69, 00-681 Warsaw (Poland); Thome, Lionel [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Ba-hat timents 104-108, 91405 Orsay Campus (France)

    2005-10-15

    Ion beam techniques provide unique tools for the qualification of radioactive waste forms. They address three major issues: (i) the simulation by ion irradiation of the stability of a matrix submitted to radiative environment; (ii) the doping of a material with stable or radioactive elements which simulate the species to be confined; (iii) the characterisation of a material via nuclear microanalysis techniques. Among various classes of nuclear matrices the spent nuclear fuel is widely considered as a potential candidate for the stabilisation of radioactive wastes in scenarios of long term interim storage or final geological disposal. Illustrative examples revealing the potentialities of the use of ion beams either as a pure characterisation tool - to investigate the chemical stability of the UO{sub 2} matrix under an oxygen potential - or in a combined way (e.g. irradiation/characterisation, doping/characterisation) - to explore the radiation stability and the behaviour of foreign species - are presented. Transformations (stoichiometry, depth and structure of growing hyperstoichiometric U{sub 4}O{sub 9}/U{sub 3}O{sub 7} oxides) occurring during low-temperature air oxidation of uranium dioxide single crystals are reported. Swift heavy ion irradiation of UO{sub 2} single crystals leads to a peculiar single crystal-polycrystal transformation (i.e. polygonisation of the fluorite-type structure of the material). Irradiation of UO{sub 2} at low energy shows that the damage production is directly linked to the energy deposited in nuclear elastic collisions. The lattice location of helium atoms (generated in large amount during the storage period) in interstitial octahedral positions is discussed.

  16. Simulations and imaging algorithm development for a cosmic ray muon tomography system for the detection of special nuclear material in transport containers

    International Nuclear Information System (INIS)

    Jewett, C.; Anghel, V.N.P.; Armitage, J.; Boudjemline, K.; Botte, J.; Bryman, D.; Bueno, J.; Charles, E.; Cousins, T.; Didsbury, R.; Erhardt, L.; Erlandson, A.; Gallant, G.; Jason, A.; Jonkmans, G.; Liu, Z.; McCall, M.; Noel, S.; Oakham, F.G.; Ong, D.; Stocki, T.; Thompson, M.; Waller, D.

    2011-01-01

    The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify Special Nuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded Special Nuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs. (author)

  17. Simulations and imaging algorithm development for a cosmic ray muon tomography system for the detection of special nuclear material in transport containers

    Energy Technology Data Exchange (ETDEWEB)

    Jewett, C.; Anghel, V.N.P. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Armitage, J.; Boudjemline, K.; Botte, J. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); Bryman, D. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Univ. of British Columbia, Vancouver, British Columbia (Canada); Bueno, J. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Charles, E. [Canada Border Services Agency, Ottawa, Ontario (Canada); Cousins, T. [International Safety Research, Ottawa, Ontario (Canada); Didsbury, R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Erhardt, L. [Defence Research and Development Canada, Ottawa, Ontario (Canada); Erlandson, A. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); Gallant, G. [Canada Border Services Agency, Ottawa, Ontario (Canada); Jason, A. [Los Alamos National Laboratory, Los Alamos (United States); Jonkmans, G. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Liu, Z. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Univ. of British Columbia, Vancouver, British Columbia (Canada); McCall, M.; Noel, S. [International Safety Research, Ottawa, Ontario (Canada); Oakham, F.G. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); TRIUMF, Vancouver, British Columbia, (Canada); Ong, D.; Stocki, T. [Health Canada, Ottawa, Ontario (Canada); Thompson, M. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Waller, D. [Defence Research and Development Canada, Ottawa, Ontario (Canada)

    2011-07-01

    The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify Special Nuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded Special Nuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs. (author)

  18. Proposed real-time data processing system to control source and special nuclear material (SS) at Mound Laboratory

    International Nuclear Information System (INIS)

    DeVer, E.A.; Baston, M.; Bishop, T.C.

    1976-01-01

    The SS Acountability System was designed to provide accountability of all SS materials by unit identification and grams. The existing system is a gram-accountable system. The new system was designed to incorporate unit identification into an ADP (Automated Data Processing) System. It also records all transactions performed against a particular unit of accountable material. The high volume of data is input via CRT terminals. Input data will consist of the following: source of the material (its unit identification), amount of material being moved, isotopic content, type of material, Health Physics number of the person moving the material, account number from which the material is being moved, unit identification of the material being moved (if all material is not moved), Health Physics number of the person receiving the material, account number to which material is being moved, and acceptance of the material by the receiver. A running inventory of all material is kept. At the end of the month the physical inventory will be compared to the data base and all discrepancies reported. Since a complete history of transactions has been kept, the source and cause for any discrepancies should be easily located. Discrepancies are held to a minimum since errors are detected before entrance into the data base. The system will also furnish all reports necessary to control SS Accountability. These reports may be requested at any time via an accountability master terminal

  19. Preparation and properties of lauric acid/silicon dioxide composites as form-stable phase change materials for thermal energy storage

    International Nuclear Information System (INIS)

    Fang Guiyin; Li Hui; Liu Xu

    2010-01-01

    Form-stable lauric acid (LA)/silicon dioxide (SiO 2 ) composite phase change materials were prepared using sol-gel methods. The LA was used as the phase change material for thermal energy storage, with the SiO 2 acting as the supporting material. The structural analysis of these form-stable LA/SiO 2 composite phase change materials was carried out using Fourier transformation infrared spectroscope (FT-IR). The microstructure of the form-stable composite phase change materials was observed by a scanning electronic microscope (SEM). The thermal properties and thermal stability were investigated by a differential scanning calorimeter (DSC) and a thermogravimetric analysis apparatus (TGA), respectively. The SEM results showed that the LA was well dispersed in the porous network of SiO 2 . The DSC results indicated that the melting latent heat of the form-stable composite phase change material is 117.21 kJ kg -1 when the mass percentage of the LA in the SiO 2 is 64.8%. The results of the TGA showed that these materials have good thermal stability. The form-stable composite phase change materials can be used for thermal energy storage in waste heat recovery and solar heating systems.

  20. Word-Preserving Arts: Material Inscription, Ekphrasis, and Spatial Form in the Later Work of William Wordsworth

    DEFF Research Database (Denmark)

    Simonsen, Peter

    William Wordsworth, posterity, reading, material inscription, ekphrasis, description, sonnet, portraiture......William Wordsworth, posterity, reading, material inscription, ekphrasis, description, sonnet, portraiture...

  1. 10 CFR 74.11 - Reports of loss or theft or attempted theft or unauthorized production of special nuclear material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Reports of loss or theft or attempted theft or... Requirements § 74.11 Reports of loss or theft or attempted theft or unauthorized production of special nuclear... plutonium shall notify the NRC Operations Center within 1 hour of discovery of any loss or theft or other...

  2. Densified waste form and method for forming

    Science.gov (United States)

    Garino, Terry J.; Nenoff, Tina M.; Sava Gallis, Dorina Florentina

    2015-08-25

    Materials and methods of making densified waste forms for temperature sensitive waste material, such as nuclear waste, formed with low temperature processing using metallic powder that forms the matrix that encapsulates the temperature sensitive waste material. The densified waste form includes a temperature sensitive waste material in a physically densified matrix, the matrix is a compacted metallic powder. The method for forming the densified waste form includes mixing a metallic powder and a temperature sensitive waste material to form a waste form precursor. The waste form precursor is compacted with sufficient pressure to densify the waste precursor and encapsulate the temperature sensitive waste material in a physically densified matrix.

  3. Lubricant Film Breakdown and Material Pick-Up in Sheet Forming of Advanced High Strength Steels and Stainless Steels when Using Environmental Friendly Lubricants

    DEFF Research Database (Denmark)

    Ceron, Ermanno; Olsson, M.; Bay, Niels

    2014-01-01

    chemically with the tool and workpiece material forming thin films, which adhere strongly to the surfaces and reduce the tendency to metal-metal contact and material pick-up. Production tests of new, environmentally benign tribo-systems are, however, costly and laboratory tests are preferred as a preliminary...... the tribological performance, i.e. tendency to material pick-up and galling, of the evaluated tribo-systems. Moreover the SEM analysis shows that different workpiece materials result in different types of material pick-up....

  4. Evaluation of gum mastic (Pistacia lentiscus as a microencapsulating and matrix forming material for sustained drug release

    Directory of Open Access Journals (Sweden)

    Dinesh M. Morkhade

    2017-09-01

    Full Text Available In this study, a natural gum mastic was evaluated as a microencapsulating and matrix-forming material for sustained drug release. Mastic was characterized for its physicochemical properties. Microparticles were prepared by oil-in-oil solvent evaporation method. Matrix tablets were prepared by wet and melt granulation techniques. Diclofenac sodium (DFS and diltiazem hydrochloride (DLTZ were used as model drugs. Mastic produced discrete and spherical microspheres with DLTZ and microcapsules with DFS. Particle size and drug loading of microparticles was in the range of 22–62 µm and 50–87%, respectively. Increase in mastic: drug ratio increased microparticle size, improved drug loading and decreased the drug release rate. Microparticles with gum: drug ratio of 2:1 could sustain DLTZ release up to 12 h and released 57% DFS in 12 h. Mastic produced tablets with acceptable pharmacotechnical properties. A 30% w/w of mastic in tablet could sustain DLTZ release for 5 h from wet granulation, and DFS release for 8 h and 11 h from wet and melt granulation, respectively. Results revealed that a natural gum mastic can be used successfully to formulate matrix tablets and microparticles for sustained drug release.

  5. Determination of Characteristic Peroids of Suppression of Thermal Decomposition Reaction of Forest Fuel Material by Specialized Software

    Directory of Open Access Journals (Sweden)

    Gumerov Vladislav M.

    2015-01-01

    Full Text Available Experimental studies determining periods of suppression of thermal decomposition reaction of forest combustible materials was carried out by high-speed, cross-correlation cameras and panoramic techniques PIV and IPI under influence of water steam. Conditions and characteristics of reaction termination of thermal decomposition of forest combustible materials under reaction with steam cloud were defined.

  6. Two intelligent materials, both of which are self-forming and self-repairing; one also self-senses and recycles

    Science.gov (United States)

    Dry, Carolyn M.

    1996-04-01

    Two self-forming and repair polymer cementitious composites were developed over a decade apart by the author. Both relied on a nature based paradigm as a model for building, in particular bone formation, repair, and degradation. For the first composite, the proposed material accreted from the ocean, made from a fluids based chemistry, that of seawater. The land based system was not built in-situ but relied on a man made supply of materials which were self-forming, self-repairing and dissolving. But in both cases a fluid based chemistry was necessary for self-building, repair and recycling of a bone-like composite material.

  7. Criteria for Special Nuclear Materials Inventory and Control Procedures; Criteres a Suivre Pour Proceder a l'Inventaire des Matieres Nucleaires Speciales et aux Mesures de Controle; Kriterii dlya inventarizatsii spetsial'nykh yadernykh materialov i metody ucheta; Criterios a Que Deben Ajustarse los Procedimientos de Inventario y Control de los Materiales Nucleares Especiales

    Energy Technology Data Exchange (ETDEWEB)

    Kinderman, E. M.; Tarrice, R. R. [Stanford Research Institute, Menlo Park, CA (United States)

    1966-02-15

    and the total inventory of these special nuclear materials. A matrix of solutions to the management and inventory control of special nuclear materials will be presented. The multiplicity and relative effectiveness of varied techniques at key stages of the materials supply, utilization and recovery are assessed. (author) [French] L'un des plus importants problemes qui, dans le domaine nucleaire et notamment dans l'exploitation commerciale de l'energie d'origine nucleaire, se posera aux societes d'investissement, aux directeursetaux exploitants est celui du controle efficace de l'inventaire des matieres nucleaires dont la valeur depassera, d'ici 1980, 5 milliards de dollars des Etats-Unis. Comparativement a la plupart des matieres utilisees commercialement, les matieres nucleaires speciales sont couteuses; aux Etats-Unis par exemple, l'uranium enrichi a 90%, l'uranium enrichi a 3% sous forme d'hexa- fluorure et l'eau lourde coutent respectivement 10808 dollars, 254 dollars et 61,60 dollars le kilo. En outre, ces matieres sont frequemment soumises, pour des raisons de protection sanitaire et de securite, a des controles gouvernementaux speciaux sans rapport direct avec leur valeur monetaire. En depit de leur prix eleve, ces matieres sont destinees a etre utilisees en grandes quantites; par exemple, on utilisera de 50 a 75 t de combustible enrichi a 3{sup o}{r_brace}o dans un reacteur de 500 MW modere a l'eau ordinaire et 200 a 300 reacteurs de cette puissance fonctionneront vraisemblablement dans le monde en 1980. L'experience acquise a permis la mise au point et l'application de methodes speciales pour le controle commercial de grandes quantites de matieres de faible valeur comme le charbon ou le minerai de fer ou de petites quantites de matieres de grande valeur comme les metaux precieux. Tout en ayant des prix comparables a ces derniers, les matieres nucleaires speciales sont de nature differente et seront utilisees en quantites beaucoup plus importantes que les

  8. The role of sensorimotor learning in the perception of letter-like forms: tracking the causes of neural specialization for letters.

    Science.gov (United States)

    James, Karin H; Atwood, Thea P

    2009-02-01

    Functional specialization in the brain is considered a hallmark of efficient processing. It is therefore not surprising that there are brain areas specialized for processing letters. To better understand the causes of functional specialization for letters, we explore the emergence of this pattern of response in the ventral processing stream through a training paradigm. Previously, we hypothesized that the specialized response pattern seen during letter perception may be due in part to our experience in writing letters. The work presented here investigates whether or not this aspect of letter processing-the integration of sensorimotor systems through writing-leads to functional specialization in the visual system. To test this idea, we investigated whether or not different types of experiences with letter-like stimuli ("pseudoletters") led to functional specialization similar to that which exists for letters. Neural activation patterns were measured using functional magnetic resonance imaging (fMRI) before and after three different types of training sessions. Participants were trained to recognize pseudoletters by writing, typing, or purely visual practice. Results suggested that only after writing practice did neural activation patterns to pseudoletters resemble patterns seen for letters. That is, neural activation in the left fusiform and dorsal precentral gyrus was greater when participants viewed pseudoletters than other, similar stimuli but only after writing experience. Neural activation also increased after typing practice in the right fusiform and left precentral gyrus, suggesting that in some areas, any motor experience may change visual processing. The results of this experiment suggest an intimate interaction among perceptual and motor systems during pseudoletter perception that may be extended to everyday letter perception.

  9. Strategic Materials

    National Research Council Canada - National Science Library

    Buhler, Carl; Burke, Adrian; Davis, Kirk; Gerhard, Michelle; Heil, Valerie; Hulse, Richard; Kwong, Ralph; Mahoney, Michael; Moran, Scott; Peek, Michael

    2006-01-01

    Some materials possess greater value than others. Materials that provide essential support for the nation's economic viability or enable critical military capabilities warrant special attention in security studies...

  10. Application Of A New Semi-Empirical Model For Forming Limit Prediction Of Sheet Material Including Superposed Loads Of Bending And Shearing

    Science.gov (United States)

    Held, Christian; Liewald, Mathias; Schleich, Ralf; Sindel, Manfred

    2010-06-01

    The use of lightweight materials offers substantial strength and weight advantages in car body design. Unfortunately such kinds of sheet material are more susceptible to wrinkling, spring back and fracture during press shop operations. For characterization of capability of sheet material dedicated to deep drawing processes in the automotive industry, mainly Forming Limit Diagrams (FLD) are used. However, new investigations at the Institute for Metal Forming Technology have shown that High Strength Steel Sheet Material and Aluminum Alloys show increased formability in case of bending loads are superposed to stretching loads. Likewise, by superposing shearing on in plane uniaxial or biaxial tension formability changes because of materials crystallographic texture. Such mixed stress and strain conditions including bending and shearing effects can occur in deep-drawing processes of complex car body parts as well as subsequent forming operations like flanging. But changes in formability cannot be described by using the conventional FLC. Hence, for purpose of improvement of failure prediction in numerical simulation codes significant failure criteria for these strain conditions are missing. Considering such aspects in defining suitable failure criteria which is easy to implement into FEA a new semi-empirical model has been developed considering the effect of bending and shearing in sheet metals formability. This failure criterion consists of the combination of the so called cFLC (combined Forming Limit Curve), which considers superposed bending load conditions and the SFLC (Shear Forming Limit Curve), which again includes the effect of shearing on sheet metal's formability.

  11. Application Of A New Semi-Empirical Model For Forming Limit Prediction Of Sheet Material Including Superposed Loads Of Bending And Shearing

    International Nuclear Information System (INIS)

    Held, Christian; Liewald, Mathias; Schleich, Ralf; Sindel, Manfred

    2010-01-01

    The use of lightweight materials offers substantial strength and weight advantages in car body design. Unfortunately such kinds of sheet material are more susceptible to wrinkling, spring back and fracture during press shop operations. For characterization of capability of sheet material dedicated to deep drawing processes in the automotive industry, mainly Forming Limit Diagrams (FLD) are used. However, new investigations at the Institute for Metal Forming Technology have shown that High Strength Steel Sheet Material and Aluminum Alloys show increased formability in case of bending loads are superposed to stretching loads. Likewise, by superposing shearing on in plane uniaxial or biaxial tension formability changes because of materials crystallographic texture. Such mixed stress and strain conditions including bending and shearing effects can occur in deep-drawing processes of complex car body parts as well as subsequent forming operations like flanging. But changes in formability cannot be described by using the conventional FLC. Hence, for purpose of improvement of failure prediction in numerical simulation codes significant failure criteria for these strain conditions are missing. Considering such aspects in defining suitable failure criteria which is easy to implement into FEA a new semi-empirical model has been developed considering the effect of bending and shearing in sheet metals formability. This failure criterion consists of the combination of the so called cFLC (combined Forming Limit Curve), which considers superposed bending load conditions and the SFLC (Shear Forming Limit Curve), which again includes the effect of shearing on sheet metal's formability.

  12. 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.

  13. Longer-term domestic supply problems for nonrenewable materials with special emphasis on energy-related applications

    International Nuclear Information System (INIS)

    Goeller, H.E.

    1980-01-01

    An examination is made on how materials are used in present and future energy production and use. Problem areas which are discussed include by-products production, import limitations, substitution and recycle, accelerated use, synthesis, and the adequacy of the data bases availability

  14. Conceptual design of the special nuclear material nondestructive assay and accountability system for the HTGR fuel refabrication pilot plant

    International Nuclear Information System (INIS)

    Jenkins, J.D.; McNeany, S.R.; Rushton, J.E.

    1975-07-01

    The conceptual design of the fissile material assay and accountability system for the HTGR refabrication pilot plant has been established. The primary feature affecting the design is the high, time varying, gamma activity of the process material due to the unavoidable presence of uranium-232. This imposes stringent requirements for remote operation and remote maintainability of system components. At the same time, the remote operation lends itself to implementation of an automated data collection and processing system for real-time accountability. The high time-varying gamma activity of the material also precludes application of a number of techniques presently employed for light-water reactor fuel assay. The techniques selected for application in the refabrication facility are (1) active thermal neutron interrogation with fast-fission or delayed-neutron counting for fuel-rod and small-sample assay, (2) calorimetry for high-level waste assay, and (3) passive gamma scanning for low-level waste assay, and rapid on-line relative rod-loading measurements. The principal nondestructive assay subsystems are identified as (1) on-line devices for 100 percent product fuel rod assay and quality control, (2) a multipurpose device in the sample inspection laboratory for small- sample assay and secondary standards calibration, and (3) equipment for assay of high- and low-uranium content scrap and waste materials. A data processing system, which coordinates data from these subsystems with information from other process control sensors, is included to provide real-time material balance information. (U.S.)

  15. Study on thermal property of lauric–palmitic–stearic acid/vermiculite composite as form-stable phase change material for energy storage

    Directory of Open Access Journals (Sweden)

    Nan Zhang

    2015-09-01

    Full Text Available The form-stable composite phase change material of lauric–palmitic–stearic acid ternary eutectic mixture/vermiculite was prepared by vacuum impregnation method for thermal energy storage. The maximum mass fraction of lauric–palmitic–stearic acid ternary eutectic mixture retained in vermiculite was determined as 50 wt% without melted phase change material seepage from the composite phase change material. Fourier transformation infrared spectroscope and scanning electron microscope were used to characterize the structure and morphology of the prepared lauric–palmitic–stearic acid ternary eutectic mixture/vermiculite form-stable composite phase change material, and the results indicate that lauric–palmitic–stearic acid ternary eutectic mixture was well confined into the layer porous structure of vermiculite by physical reaction. The melting and freezing temperatures and latent heats were measured by differential scanning calorimeter as 31.4°C and 30.3°C, and 75.8 and 73.2 J/g, respectively. Thermal cycling test showed that there was no significant change in the thermal properties of lauric–palmitic–stearic acid ternary eutectic mixture/vermiculite form-stable composite phase change material after 1000 thermal cycles. Moreover, 2 wt% expanded graphite was added to improve the thermal conductivity of lauric–palmitic–stearic acid ternary eutectic mixture/vermiculite form-stable composite phase change material. All results indicated that the prepared lauric–palmitic–stearic acid ternary eutectic mixture/vermiculite form-stable composite phase change material had suitable thermal properties and good thermal reliability for the application of thermal energy storage in building energy efficiency.

  16. Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy - low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris

    International Nuclear Information System (INIS)

    Sagara, Hiroshi; Tomikawa, Hirofumi; Watahiki, Masaru; Kuno, Yusuke

    2014-01-01

    The technologies applied to the analysis of the Three Mile Island accident were examined in a feasibility study of gamma spectrometry of molten core material from the Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy. The focus is on low-volatile fission products and heavy metal inventory analysis, and the fundamental characteristics of gamma-rays from fuel debris with respect to passive measurements. The inventory ratios of the low-volatile lanthanides, "1"5"4Eu and "1"4"4Ce, to special nuclear materials were evaluated by the entire core inventories in units 1, 2, and 3 with an estimated uncertainty of 9%-13% at the 1σ level for homogenized molten fuel material. The uncertainty is expected to be larger locally owing to the use of the irradiation cycle averaging approach. The ratios were also evaluated as a function of burnup for specific fuel debris with an estimated uncertainty of 13%-25% at the 1σ level for units 1 and 2, and most of the fuels in unit 3, although the uncertainty regarding the separated mixed oxide fuel in unit 3 would be significantly higher owing to the burnup dependence approach. Source photon spectra were also examined and cooling-time-dependent data sets were prepared. The fundamental characteristics of high-energy gamma-rays from fuel debris were investigated by a bare-sphere model transport calculation. Mass attenuation coefficients of fuel debris were evaluated to be insensitive to its possible composition in a high-energy region. The leakage photon ratio was evaluated using a variety of parameters, and a significant impact was confirmed for a certain size of fuel debris. Its correlation was summarized with respect to the leakage photopeak ratio of source "1"5"4Eu. Finally, a preliminary study using a hypothetical canister model of fuel debris based on the experience at Three Mile Island was presented, and future plans were introduced. (author)

  17. Generation of point isotropic source dose buildup factor data for the PFBR special concretes in a form compatible for usage in point kernel computer code QAD-CGGP

    International Nuclear Information System (INIS)

    Radhakrishnan, G.

    2003-01-01

    Full text: Around the PFBR (Prototype Fast Breeder Reactor) reactor assembly, in the peripheral shields special concretes of density 2.4 g/cm 3 and 3.6 g/cm 3 are to be used in complex geometrical shapes. Point-kernel computer code like QAD-CGGP, written for complex shield geometry comes in handy for the shield design optimization of peripheral shields. QAD-CGGP requires data base for the buildup factor data and it contains only ordinary concrete of density 2.3 g/cm 3 . In order to extend the data base for the PFBR special concretes, point isotropic source dose buildup factors have been generated by Monte Carlo method using the computer code MCNP-4A. For the above mentioned special concretes, buildup factor data have been generated in the energy range 0.5 MeV to 10.0 MeV with the thickness ranging from 1 mean free paths (mfp) to 40 mfp. Capo's formula fit of the buildup factor data compatible with QAD-CGGP has been attempted

  18. Conjoint Forming - Technologies for Simultaneous Forming and Joining

    International Nuclear Information System (INIS)

    Groche, P; Wohletz, S; Mann, A; Krech, M; Monnerjahn, V

    2016-01-01

    The market demand for new products optimized for e. g. lightweight applications or smart components leads to new challenges in production engineering. Hybrid structures represent one promising approach. They aim at higher product performance by using a suitable combination of different materials. The developments of hybrid structures stimulate the research on joining of dissimilar materials. Since they allow for joining dissimilar materials without external heating technologies based on joining by plastic deformation seem to be of special attractiveness. The paper at hand discusses the conjoint forming approach. This approach combines forming and joining in one process. Two or more workpieces are joined while at least one workpiece is plastically deformed. After presenting the fundamental joining mechanisms, the conjoint forming approach is discussed comprehensively. Examples of conjoint processes demonstrate the effectiveness and reveal the underlying phenomena. (paper)

  19. Form-Stable Phase Change Materials Based on Eutectic Mixture of Tetradecanol and Fatty Acids for Building Energy Storage: Preparation and Performance Analysis

    Directory of Open Access Journals (Sweden)

    Yiran li

    2013-10-01

    Full Text Available This paper is focused on preparation and performance analysis of a series of form-stable phase change materials (FSPCMs, based on eutectic mixtures as phase change materials (PCMs for thermal energy storage and high-density polyethylene (HDPE-ethylene-vinyl acetate (EVA polymer as supporting materials. The PCMs were eutectic mixtures of tetradecanol (TD–capric acid (CA, TD–lauric acid (LA, and TD–myristic acid (MA, which were rarely explored before. Thermal properties of eutectic mixtures and FSPCMs were measured by differential scanning calorimeter (DSC. The onset melting/solidification temperatures of form-stable PCMs were 19.13 °C/13.32 °C (FS TD–CA PCM, 24.53 °C/24.92 °C (FS TD–LA PCM, and 33.15 °C/30.72 °C (FS TD–MA PCM, respectively, and latent heats were almost greater than 90 J/g. The surface morphologies and chemical stability of form-stable PCM were surveyed by scanning electron microscopy (SEM and Fourier-transform infrared (FT-IR spectroscopy, respectively. The thermal cycling test revealed that the thermal reliability of these three form-stable PCMs was good. Thermal storage/release experiment indicated melting/solidification time was shortened by introducing 10 wt % aluminum powder (AP. It is concluded that these FSPCMs can act as potential building thermal storage materials in terms of their satisfactory thermal properties.

  20. Form-Stable Phase Change Materials Based on Eutectic Mixture of Tetradecanol and Fatty Acids for Building Energy Storage: Preparation and Performance Analysis.

    Science.gov (United States)

    Huang, Jingyu; Lu, Shilei; Kong, Xiangfei; Liu, Shangbao; Li, Yiran

    2013-10-22

    This paper is focused on preparation and performance analysis of a series of form-stable phase change materials (FSPCMs), based on eutectic mixtures as phase change materials (PCMs) for thermal energy storage and high-density polyethylene (HDPE)-ethylene-vinyl acetate (EVA) polymer as supporting materials. The PCMs were eutectic mixtures of tetradecanol (TD)-capric acid (CA), TD-lauric acid (LA), and TD-myristic acid (MA), which were rarely explored before. Thermal properties of eutectic mixtures and FSPCMs were measured by differential scanning calorimeter (DSC). The onset melting/solidification temperatures of form-stable PCMs were 19.13 °C/13.32 °C (FS TD-CA PCM), 24.53 °C/24.92 °C (FS TD-LA PCM), and 33.15 °C/30.72 °C (FS TD-MA PCM), respectively, and latent heats were almost greater than 90 J/g. The surface morphologies and chemical stability of form-stable PCM were surveyed by scanning electron microscopy (SEM) and Fourier-transform infrared (FT-IR) spectroscopy, respectively. The thermal cycling test revealed that the thermal reliability of these three form-stable PCMs was good. Thermal storage/release experiment indicated melting/solidification time was shortened by introducing 10 wt % aluminum powder (AP). It is concluded that these FSPCMs can act as potential building thermal storage materials in terms of their satisfactory thermal properties.

  1. Studies on the different forms of material reacting with antiinsulin antibodies in the fetal and adult rat

    International Nuclear Information System (INIS)

    Felix, J.M.; Sutter-Dub, M.T.; Legrele, C.; Reims Univ., 51

    1975-01-01

    The nature of peak B (MW = 10-12,000, proinsulin) and peak C (MW = 50-100,000, 'big big' insulin) materials detected by the double antibody (DA) procedure in elution profiles of rat sera after Sephadex G 50 or G 100 chromatography (cf. preceding companion paper) is further investigated. Peak B is converted by mild tryptic digestion in an immunoreactive material behaving in rechromatography exactly like insulin monomer. Peak C is less easily detected by the dextran coated charcoal (DCC) method; it resists 8 M urea 37 0 C for 1 hr, is not an artifact due to the complement system; its relative importance is very much reduced in pancreatic extracts or perifusates. Incubation of biologically active 125 I labelled insulin in rat sera results in appearance of labelled material behaving on chromatography like peak C natural material, having the electrophoretic mobility of rat α 1 globulins and albumin, and resisting 8 M urea, acidic pHs and 0.5 M NaCl. Similar incubation in buffer supplemented with bovine albumin results in appearance of a labelled material having the electrophoretic mobility of beef albumin; N-ethyl-maleimide provides against this binding, which might result from (S-S)-(SH) interchanges. Rat α globulins and albumin (but not beef albumin) cross-react with the DA procedure; they do not react with the DCC method. Insulin bound to plasma proteins react with both methods. It is suggested that peak C material, as detected by the DA method in rat serum, consists both of insulin covalently bound to plasma proteins and of certain plasma proteins; the DCC method detects only bound insulin. In streptozotocin treated rats, peak C material persists after the complete disappearance of insulin and proinsulin when detected by the (DA) procedure, but disappears when detected by the DCC procedure. (orig.) [de

  2. Studies on the different forms of material reacting with antiinsulin antibodies in the fetal and adult rat

    Energy Technology Data Exchange (ETDEWEB)

    Felix, J M; Sutter-Dub, M T; Legrele, C [Reims Univ., 51 (France). Lab. de Physiologie Animale; Reims Univ., 51 (France). Centre de Biologie et de Biochimie du Developpement)

    1975-09-01

    The nature of peak B (MW = 10-12,000, proinsulin) and peak C (MW = 50-100,000, 'big big' insulin) materials detected by the double antibody (DA) procedure in elution profiles of rat sera after Sephadex G 50 or G 100 chromatography (cf. preceding companion paper) is further investigated. Peak B is converted by mild tryptic digestion in an immunoreactive material behaving in rechromatography exactly like insulin monomer. Peak C is less easily detected by the dextran coated charcoal (DCC) method; it resists 8 M urea 37/sup 0/C for 1 hr, is not an artifact due to the complement system; its relative importance is very much reduced in pancreatic extracts or perifusates. Incubation of biologically active /sup 125/I labelled insulin in rat sera results in appearance of labelled material behaving on chromatography like peak C natural material, having the electrophoretic mobility of rat ..cap alpha../sub 1/ globulins and albumin, and resisting 8 M urea, acidic pHs and 0.5 M NaCl. Similar incubation in buffer supplemented with bovine albumin results in appearance of a labelled material having the electrophoretic mobility of beef albumin; N-ethyl-maleimide provides against this binding, which might result from (S-S)-(SH) interchanges. Rat ..cap alpha.. globulins and albumin (but not beef albumin) cross-react with the DA procedure; they do not react with the DCC method. Insulin bound to plasma proteins react with both methods. It is suggested that peak C material, as detected by the DA method in rat serum, consists both of insulin covalently bound to plasma proteins and of certain plasma proteins; the DCC method detects only bound insulin. In streptozotocin treated rats, peak C material persists after the complete disappearance of insulin and proinsulin when detected by the (DA) procedure, but disappears when detected by the DCC procedure.

  3. Environmental assessment for renewal of special nuclear material, License No. SUB-1010 (Docket No. 40-8027)

    International Nuclear Information System (INIS)

    1985-08-01

    The proposed action is the renewal of the license necessary for continued operation of the SFC production plant at Gore, Oklahoma. The plant has been in operation with authority to use source material for the production of UF 6 since February 1970. In addition to facilities for production of UF 6 the site also includes: (1) a storage area for drums of uranium ore concentrates received from uranium mills, (2) a uranium sampling facility, (3) bulk storage of hazardous chemicals such as hydrofluoric (HF), nitric (HNO 3 ), and sulfuric (H 2 SO 4 ) acids and tributyl phosphate-hexane solvent, (4) a facility for electrolytic production of fluorine from HF, (5) separate treatment systems and storage ponds for radiological and nonradiological liquid wastes, and (6) a program for disposal of raffinate from a solvent extraction system in the UF 6 production as fertilizer on land owned by SFC. 13 figs., 30 tabs

  4. Trace element determination in plant material by means of instrumental neutron activation analysis (INAA) with special reference to molybdenum

    International Nuclear Information System (INIS)

    Schnier, C.; Schnug, E.

    1981-01-01

    The instrumental neutron activation analysis (INAA) permits a non-destructive multielement determination of minute trace element concentrations in organic material. No sample preparation except drying is required. Especially for the determination of molybdenum the INAA offers great advantages compared to the methods used in agricultural chemistry where complicated enrichment and extraction steps are needed. Contamination by reagents or loss of elements are not potential sources of errors. The principle, the advantages and disadvantages of INAA are described. The method is demonstrated with the example of celery samples from an experiment with five different nitrogen fertilizers on contaminated soil and of cabbage samples from an uncontaminated region. Besides molybdenum, 19 other elements (Na, K, Ca, Sc, Cr, Fe, Co, Zn, As, Se, Br, Rb, Cd, Sb, Ba, La, W, Au, Th) are determined. (orig.) [de

  5. SECTIONAL AREA CALCULATION OF MATERIAL REMOVED FROM BLANK WHILE FORMING SPACE BETWEEN TWO TEETH OF SATELLITE GEAR OF PLANETARY PIN TOOTH REDUCER

    Directory of Open Access Journals (Sweden)

    N. G. Yankevich

    2009-01-01

    Full Text Available One of the most important values while forming gear wheels is a material section area Sс which is to be removed by a tool in the process of forming a space between two teeth in one pass. Cutting resistance which is proportional  to section area of  the layer to be cut and, correspondingly, a thermodynamic intensity in the polishing zone depend on Sс value.The paper proposes relations for calculation of a material section area Sс which is to be removed from a blank while forming a space between two teeth of a satellite gear of a planetary pin tooth reducer.Measurements being made in the AutoCAD packet have shown that any corrections of the profile do not make a significant influence on a section area Sс.

  6. Report on the FY 1999 survey on long-term energy technology strategy/basic survey for working out industrial technology strategy. Technology strategy by field (formed raw material field); 1999 nendo choki energy gijutsu senryaku nado ni kansuru chosa hokokusho. Sangyo gijutsu senryaku sakutei kiban chosa (bun'yabetsu gijutsu senryaku (sokeizai bun'ya))

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The paper described the results of the survey of the formed raw material field in relation to the FY 1999 long-term energy technology strategy. In the advancing international specialization, efforts are being made for the secure basic base technology force and cost reduction required for competition, and at the same time the aim is not to retain/improve all the formed raw material technologies, but to discriminate the materials in the aspects except the cost. By promoting the reformation into the proposed type industry, it is necessary to work out the bold strategy including the review of the system/structure for promoting the strategic technology innovation by aiming at the important formed raw material technology which can be a life line for the assembly industry, in particular. Concretely, the comprehensive technology system which concentrated a variety of engineering knowledge/information was constructed. The system is shifted to the one that adopted information/communication technology. The conversion in the early time to the proposed type industry is attempted. Japan acquires capability for heightening the level of technology, by which Japan will continue leading the formed raw material technology to the world's top level. Japan realizes the network consisting of the industry, university and government. The environment is realized where new personnel will naturally enter the formed raw material industry and bottom up the total technology force. (NEDO)

  7. Undercuts by Laser Shock Forming

    International Nuclear Information System (INIS)

    Wielage, Hanna; Vollertsen, Frank

    2011-01-01

    In laser shock forming TEA-CO 2 -laser induced shock waves are used to form metal foils, such as aluminum or copper. The process utilizes an initiated plasma shock wave on the target surface, which leads to a forming of the foil. A challenge in forming technologies is the manufacturing of undercuts. By conventional forming methods these special forms are not feasible. In this article, it is presented that undercuts in the micro range can be produced by laser shock deep drawing. Different drawing die diameters, drawing die depths and the material aluminum in the thicknesses 20 and 50 μm were investigated. It will be presented that smaller die diameters facilitate undercuts compared to bigger die diameters. The phenomena can be explained by Barlow's formula. Furthermore, it is shown which maximum undercut depth at different die diameters can be reached. To this end, cross-sections of the different parameter combinations are displayed.

  8. Investigation into the Fiber Orientation Effect on the Formability of GLARE Materials in the Stamp Forming Process

    Science.gov (United States)

    Liu, Shichen; Lang, Lihui; Sherkatghanad, Ehsan; Wang, Yao; Xu, Wencai

    2018-04-01

    Glass-reinforced aluminum laminate (GLARE) is a new class of fiber metal laminates (FMLs) which has the advantages such as high tensile strength, outstanding fatigue, impact resistance, and excellent corrosion properties. GLARE has been extensively applied in advanced aerospace and automobile industries. However, the deformation behavior of the glass fiber during forming must be studied to the benefits of the good-quality part we form. In this research, we focus on the effect of fiber layer orientation on the GLARE laminate formability in stamp forming process. Experimental and numerical analysis of stamping a hemisphere part in different fiber orientation is investigated. The results indicate that unidirectional and multi-directional fiber in the middle layer make a significant effect on the thinning and also surface forming quality of the three layer sheet. Furthermore, the stress-strain distribution of the aluminum alloy and the unique anisotropic property of the fiber layer exhibit that fiber layer orientation can also affect the forming depths as well as the fracture modes of the laminate. According to the obtained results, it is revealed that multi-directional fiber layers are a good alternative compared to the unidirectional fibers especially when a better formability is the purpose.

  9. Materialism.

    Science.gov (United States)

    Melnyk, Andrew

    2012-05-01

    Materialism is nearly universally assumed by cognitive scientists. Intuitively, materialism says that a person's mental states are nothing over and above his or her material states, while dualism denies this. Philosophers have introduced concepts (e.g., realization and supervenience) to assist in formulating the theses of materialism and dualism with more precision, and distinguished among importantly different versions of each view (e.g., eliminative materialism, substance dualism, and emergentism). They have also clarified the logic of arguments that use empirical findings to support materialism. Finally, they have devised various objections to materialism, objections that therefore serve also as arguments for dualism. These objections typically center around two features of mental states that materialism has had trouble in accommodating. The first feature is intentionality, the property of representing, or being about, objects, properties, and states of affairs external to the mental states. The second feature is phenomenal consciousness, the property possessed by many mental states of there being something it is like for the subject of the mental state to be in that mental state. WIREs Cogn Sci 2012, 3:281-292. doi: 10.1002/wcs.1174 For further resources related to this article, please visit the WIREs website. Copyright © 2012 John Wiley & Sons, Ltd.

  10. Corrosion behaviour of container materials for the disposal of high-level waste forms in rock salt formations

    International Nuclear Information System (INIS)

    Smailos, E.; Schwarzkopf, W.; Koester, R.

    1987-05-01

    Extensive laboratory-scale experiments to evaluate the long-term corrosion behaviour of selected materials in brines and first in situ experiments were performed. In the laboratory experiments the materials Ti 99.8-Pd, Hastelloy C4 and hot-rolled low carbon steel as well cast steel, spheroidal cast iron, Si-cast iron and the Ni-Resists type D2 and D4 were investigated. The investigated parameters were: temperature, gamma-radiation and different compositions of salt brines. (orig./PW) [de

  11. Experimental and numerical investigation of form-stable dodecane/hydrophobic fumed silica composite phase change materials for cold energy storage

    International Nuclear Information System (INIS)

    Chen, Jiajie; Ling, Ziye; Fang, Xiaoming; Zhang, Zhengguo

    2015-01-01

    Highlights: • Form-stable dodecane/fumed silica composite for cold storage is prepared. • A suggesting hypothesis that explains infiltration mechanism is proposed. • The performance of the composite phase change material is investigated. • Numerical simulation of system is carried out and results fit well. - Abstract: A kind of form-stable composite phase change materials used for cold thermal energy storage is prepared by absorbing dodecane into the hydrophobic fumed silica. With relatively suitable pore diameter and hydrophobic groups, hydrophobic fumed silica is beneficial to the penetration and infiltration of dodecane and the leakage problem solving. Scanned by electron micrographs and Fourier transformation infrared, the composite phase change material is characterized to be just physical penetration. Besides, the differential scanning calorimeter and thermo gravimetric analysis reveals the high enthalpy, good thermal stability and cycling performance of this composite phase change material. What’s more, Hot-Disk thermal constants analyzer demonstrates that the composite phase change material has low thermal conductivity which is desired in cold storage application. In the experiment, a cold energy storage system is set up and the results from the experiment show that the system has excellent performance of cold storage by incorporating composite phase change material. Apart from that, the experimental data is found to have a great agreement with the numerical simulation which is carried out by using the commercial computational fluid dynamics software FLUENT.

  12. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    International Nuclear Information System (INIS)

    Miller, Thomas M.; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-01-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical

  13. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Thomas M., E-mail: millertm@ornl.gov; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-12-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical.

  14. Trilateral Initiative: IAEA authentication and national certification of verification equipment for facilities with classified forms of fissile material

    International Nuclear Information System (INIS)

    Haas, Eckard; Sukhanov, Alexander; Murphy, John

    2001-01-01

    Full text: Within the framework of the Trilateral Initiative, technical challenges have arisen due to the potential of the International Atomic Energy Agency (IAEA) monitoring fissile material with classified characteristics, as well as the IAEA using facility or host country supplied monitoring equipment. In monitoring material with classified characteristics, it is recognized that the host country needs to assure that classified information is not made available to the IAEA inspectors. Thus, any monitoring equipment used to monitor material with classified characteristics has to contain information security capabilities, such as information barriers. But likewise in using host-country-supplied monitoring equipment, regarding the material being monitored the IAEA has to have confidence that the information provided by the equipment is genuine and can be used by the IAEA in fulfilling its obligation to derive conclusions based on independent verification measures. Thus the IAEA needs to go through the process of authenticating the monitoring equipment. In the same way the host country needs to go through the process to assure itself that the monitoring equipment integrated with an information barrier will not divulge any classified information about an inspected sensitive item. Both processes require on large extent identical measures, but partially also may conflict with each other. The fact that monitoring equipment needs to exhibit information security throughout its lifecycle while at the same time be capable of being authenticated necessitates the need for creative technical approaches to be pursued. (author)

  15. An Examination of Prereading Exercises: Recommendations for Form and Instruction on the Comprehension of Written Instructional Material.

    Science.gov (United States)

    Campbell, John Joseph

    This study investigated the effects of prereading exercises on the comprehension of written instructional material. The subjects were 210 community college freshmen who were required to enroll in a developmental reading course. All of the subjects had scored below the eighth percentile on the national norms of the Davis Reading Test. The subjects…

  16. Novelly formed products of the interaction of fuel with construction materials of the 4th unit of Chernobyl NPP

    International Nuclear Information System (INIS)

    Borovoj, A.A.; Galkin, B.Ya.; Krinitsyn, A.P.; Pazukhin, Eh.M.; Kheruvimov, A.N.; Chechcherov, K.P.; Anderson, E.B.

    1991-01-01

    Radiation environment and map of sampling route in the steam distributing collector of the 4th unit of the Chernobyl NPP are described. The results of gamma- and alpha radiometric analyses as well as chemical analysis are presented. Samples of core materials taken from the depth of fuel-containing masses by drilling through reactor vault wall of the damaged power unit are described

  17. Mechanical Properties of Ti-6Al-4V Octahedral Porous Material Unit Formed by Selective Laser Melting

    Directory of Open Access Journals (Sweden)

    Jianfeng Sun

    2012-01-01

    Full Text Available The Ti-6Al-4V octahedral porous material unit is designed to calculate its load. In this paper, ANSYS is adopted for the load simulation of the unit. And a simplified model of dimensional theoretical calculation is established, by which the analytical equation of the fracture load is obtained and the calculation of the load of Ti-6Al-4V is completed. Moreover, selective laser melting is adopted in processing the Ti-6Al-4V porous material unit. The experimental value of fracture load of this material is obtained through compression experiment. The results show that the simulation curves approximate the variation tendency of the elastic deformation of the compression curves; the curves of theoretical calculation approximate the general variation tendency; and the experimental value of fracture load is very close to the theoretical value. Therefore, the theoretical prediction accuracy of fracture load is high, which lays the foundation for the mechanical properties of the octahedral porous material.

  18. Method of approximating the effects of blast mitigation materials on particulate-containing clouds formed by explosions

    International Nuclear Information System (INIS)

    Dyckes, G.W.

    1983-09-01

    A numerical model was developed for predicting the effect of blast mitigation materials on the rise and entrainment rate of explosively driven buoyant clouds containing radiotoxic particles. Model predictions for clouds from unmitigated explosions agree with published observations. More experimental data are needed to assess the validity of predictions for clouds from mitigated explosions

  19. Technical Division quarterly progress report, October 1--December 31, 1977. [Fuel cycle research and development; special materials production

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M. (ed.)

    1978-02-01

    Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for /sup 85/Kr waste; and the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel. The long-term management of defense waste from the ICPP covers post-calcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the Programmatic Environmental Impact Statement on ICPP waste. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, Waste Calcining Facility support, New Waste Calcining Facility support, and effluent monitoring methods evaluation and development. In this category are studies on nuclear materials security, application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat, inplant reactor source term measurements, burnup methods for fast breeder reactor fuels, absolute thermal fission yield measurements, analytical support to light water breeder reactor development, research on analytical methods, and the behavior of environmental species of iodine.

  20. Investigation of active interrogation techniques to detect special nuclear material in maritime environments: Boarded search of a cargo container ship

    International Nuclear Information System (INIS)

    Grogan, Brandon R.; Henkel, James J.; Johnson, Jeffrey O.; Mihalczo, John T.; Miller, Thomas M.; Patton, Bruce W.

    2013-01-01

    The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system