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Sample records for site acceptance test

  1. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    Energy Technology Data Exchange (ETDEWEB)

    NNSA/NSO Waste Management Project

    2008-06-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  2. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    International Nuclear Information System (INIS)

    NNSA/NSO Waste Management Project

    2008-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

  3. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

    1999-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

  4. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    International Nuclear Information System (INIS)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-01-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

  5. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

  6. Nevada test site waste acceptance criteria

    International Nuclear Information System (INIS)

    1996-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  7. Nevada test site waste acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  8. Nevada Test Site Waste Acceptance Criteria, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

  9. Nevada Test Site Waste Acceptance Criteria, December 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

  10. Nevada Test Site waste acceptance criteria [Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-08-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  11. Nevada Test Site waste acceptance criteria [Revision 1

    International Nuclear Information System (INIS)

    None

    1997-01-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  12. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2009-05-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  13. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    International Nuclear Information System (INIS)

    2009-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  14. Nevada test site defense waste acceptance criteria, certification, and transfer requirements

    International Nuclear Information System (INIS)

    1988-10-01

    The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

  15. Development of OSSA(Operation Service Support Agreement) Simulator and Site Acceptance Test

    Energy Technology Data Exchange (ETDEWEB)

    Park, DaeSeung; Ahn, Sung-Jin; Lee, Jong-Beom [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Building the nuclear power plant is on the schedule, remaining question is who could operate the NPP after the construction is finished. OSSA is known as Operation Service Support Agreement, it is the contract between KHNP(Korea Hydro and Nuclear Power Co.,) and ENEC(Emirates Nuclear Energy Corporation) for United Arab Emirates Nuclear Power Plant operations support. The contract is mostly about the safety and reliability operations and as well as of the training of UAE operators to have better experiences. UAE operators needed to be trained and tested before they come to UAE for operate the NPP. The OSSA simulator was built because operator shall not make any mistakes even if the plant is not yet constructed. Simulator Training is a key for getting experiences without operating the actual plant, because the nuclear power plant never used as the test in real situations. Operators’ requirement is to have more than 2 years at site experiences and also they have to be trained 5 to 8 months of the training. The experience such as the site acceptance test will lead the future nuclear industry to meet the global standard and to lead the safety of the NPP. Under the OSSA agreement 400 KHNP experts will support the operations. Most of the operators were trained at the OSSA simulator which is most reliable simulator that can demonstrate satisfactory performance for the simulator.

  16. Shielding requirements on-site loading and acceptance testing on the Leksell gamma knife

    International Nuclear Information System (INIS)

    Maitz, A.H.; Lunsford, L.D.; Wu, A.; Lindner, G.; Flickinger, J.C.

    1990-01-01

    On August 14, 1987, the first stereotactic radiosurgical procedure using the gamma knife was performed in North America. Located in a self-contained radiosurgical suite in the basement of Presbyterian-University Hospital in Pittsburgh, Pennsylvania. This device uses 201 highly focused beams 60Co for the single-treatment closed-skull irradiation of brain lesions localized by stereotactic techniques (radiosurgery). One hundred and fifty-two patients with intracranial arteriovenous malformations or brain tumors were treated in the first year of operation. The Presbyterian University Hospital of Pittsburgh gamma knife is the first such unit in which the 60Co sources were loaded on-site. This effort required us to solve some difficult and unusual problems encountered during site preparation, delivery, and loading of the unit in a busy hospital setting. The solutions developed enabled installation and use of the gamma knife with minimal disruption of hospital activities while maintaining acceptable levels of exposure to radiation. Environmental surveys performed during the loading of the 201 radioactive sources (total, 219 TBq) confirmed that on-site loading is possible and practical. Our experience in the design, construction, and implementation of the first North American gamma knife supports the practicality and safety of on-site loading and may be of value in the planning and development of future gamma knife installations

  17. Siting and public acceptance

    International Nuclear Information System (INIS)

    De Lise, Pasquale.

    1977-01-01

    The paper discusses the problem of nuclear power plant siting according to presently applicable legislation in Italy, taking into account urban and environmental aspects. Act No 393 of 2 August 1975 on the siting of nuclear plants introduced a significant change in that prior to its adoption, the competence to license nuclear installations was divided amongst so many bodies that approval was inevitably delayed. Act No. 393 lays down the siting procedure which involves authorities at regional and State level and provides a step by step consultation of the Communes concerned and gives them a time limit for replying to the proposed project, while enabling the necessary scientific, environmental and urban investigations to be made. Thus although ultimate decisions rest with the State, the regional bodies representing the public have a voice in them. In such planning the authorities must take into account the public interest, from the environmental and social angles as well as political and economic interests. (NEA) [fr

  18. Displacement compressors - acceptance tests

    CERN Document Server

    International Organization for Standardization. Geneva

    1996-01-01

    ISO 1217:2009 specifies methods for acceptance tests regarding volume rate of flow and power requirements of displacement compressors. It also specifies methods for testing liquid-ring type compressors and the operating and testing conditions which apply when a full performance test is specified.

  19. Cone penetrometer acceptance test report

    Energy Technology Data Exchange (ETDEWEB)

    Boechler, G.N.

    1996-09-19

    This Acceptance Test Report (ATR) documents the results of acceptance test procedure WHC-SD-WM-ATR-151. Included in this report is a summary of the tests, the results and issues, the signature and sign- off ATP pages, and a summarized table of the specification vs. ATP section that satisfied the specification.

  20. First Stage Acceptance Test

    Science.gov (United States)

    1960-01-01

    This photograph shows the intense smoke and fire created by the five F-1 engines from a test firing of the Saturn V first stage (S-1C) in the S-1C test stand at the Marshall Space Flight Center. The towering 363-foot Saturn V was a multi-stage, multi-engine launch vehicle standing taller than the Statue of Liberty. Altogether, the Saturn V engines produced as much power as 85 Hoover Dams.

  1. L-286, Acceptance Test Record

    International Nuclear Information System (INIS)

    HARMON, B.C.

    2000-01-01

    This document provides a detailed account of how the acceptance testing was conducted for Project L-286, ''200E Area Sanitary Water Plant Effluent Stream Reduction''. The testing of the L-286 instrumentation system was conducted under the direct supervision

  2. Hanford Site Solid Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  3. Hanford Site Solid Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    1993-01-01

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

  4. Nitrogen trailer acceptance test report

    International Nuclear Information System (INIS)

    Kostelnik, A.J.

    1996-01-01

    This Acceptance Test Report documents compliance with the requirements of specification WHC-S-0249. The equipment was tested according to WHC-SD-WM-ATP-108 Rev.0. The equipment being tested is a portable contained nitrogen supply. The test was conducted at Norco's facility

  5. Field studies to determine acceptable levels of contamination at former UK nuclear testing sites, Maralinga and Emu in Australia

    International Nuclear Information System (INIS)

    Davy, D.R.

    1988-01-01

    The Maralinga and Emu regions of South Australia were used between 1953 and 1961 for the UK nuclear weapon development program. Two types of trials were conducted - the major trials involved the detonation of fission weapons and the minor trials dealt with weapon design and operational safety. In 1986, as a result of the findings of the Royal Commission on Nuclear Testing in Australia, the UK and Australian governments agreed to set up a Technical Assessment Group (TAG) with one American, two Australian and two British members to review the Maralinga-Emu situation. TAG was to advise on a series of clean-up options and their associated costs and examine land-use options ranging from unrestricted use by the traditional Aboriginal land owners to options involving various degrees of administrative and physical control. In its interim report, presented in May 1986, TAG observed that the existing data base was inadequate and suggested a series of field and laboratory studies that would partly correct this situation. Six of these studies were concerned with redefining the existing levels of contamination and establishing acceptable levels of contamination for a range of land-use options. This paper discusses the rationale, organisational support, scope and experimental protocol adopted for each of the six studies

  6. W-025, acceptance test report

    International Nuclear Information System (INIS)

    Roscha, V.

    1994-01-01

    This acceptance test report (ATR) has been prepared to establish the results of the field testing conducted on W-025 to demonstrate that the electrical/instrumentation systems functioned as intended by design. This is part of the RMW Land Disposal Facility

  7. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  8. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2010-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  9. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  10. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2012-02-28

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  11. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2012-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  12. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Ellefson, M.D.

    1998-01-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

  13. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  14. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2013-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  15. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

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

    1991-09-01

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

  16. Acceptance test procedure for Project W-280

    International Nuclear Information System (INIS)

    Stites, C.G.

    1994-01-01

    This Document is the Acceptance Test Procedure for 200 Area C and SY Tank Farm Lighting Upgrade. This Acceptance Test Procedure has been prepared to demonstrate that the Tank Farm Lighting Systems function correctly as required by project criteria and as intended by design

  17. MITS Data Acquisition Subsystem Acceptance Test procedure

    International Nuclear Information System (INIS)

    Allison, R.

    1980-01-01

    This is an acceptance procedure for the Data Acquisition Subsystem of the Machine Interface Test System (MITS). Prerequisites, requirements, and detailed step-by-step instruction are presented for inspecting and performance testing the subsystem

  18. Aircraft Assessment and Acceptance Testing.

    Science.gov (United States)

    1980-05-01

    telaque le pilote automatique, et lautomnanette, lee syst.-mes de stabilit6 artificielle etc.. A5 - La v~rification des dispositifs de odcuritd B - Essais...signals should be monitored on an oscilloscope, and modulation meter to assist in diagnosis or reasons for poor intelligibility . 7 Qualitative...conditioning in origin, so tests of the effect on com- munications intelligibility should be made in the flight regime that is operationally most

  19. DACS upgrade acceptance test report

    International Nuclear Information System (INIS)

    Zuehlke, A.C.

    1994-01-01

    The DACS, which is housed in a trailer located just outside of the north fence at the SY tank farm, receives input signals from a variety of sensors located in and around the SY-101 tank. These sensors provide information such as: (1) tank vapor space and ventilation system H 2 concentration; (2) tank waste temperature; (3) tank pressure; (4) waste density; (5) operating pump parameters such as speed, flow, rotational position, discharge pressure, and internal temperature; (6) strain (for major equipment); and (7) waste level. The output of these sensors is conditioned and transmitted to the DACS computers where these signals are displayed, recorded, and monitored for out-of-specification conditions. If abnormal conditions are detected, then, in certain situations, the DACS automatically generates alarms and causes the system to abort pump operations. The report documents testing performed per WHC-SD-WM-ATP-082. Rev. 0-13

  20. Acceptance Test Plan for ANSYS Software

    International Nuclear Information System (INIS)

    CREA, B.A.

    2000-01-01

    This plan governs the acceptance testing of the ANSYS software (Full Mechanical Release 5.5) for use on Project Word Management Contract (PHMC) computer systems (either UNIX or Microsoft Windows/NT). There are two phases to the acceptance testing covered by this test plan: program execution in accordance with the guidance provided in installation manuals; and ensuring results of the execution are consistent with the expected physical behavior of the system being modeled

  1. Cone penetrometer moisture probe acceptance test report

    International Nuclear Information System (INIS)

    Barnes, G.A.

    1996-01-01

    This Acceptance Test Report (ATR) documents the results of WHC-SD-WM-ATP-146 (Prototype Cone Penetrometer Moisture Probe Acceptance Test Procedure) and WHC-SD-WM-ATP-145 (Cone Penetrometer Moisture Probe Acceptance Test Procedure). The master copy of WHC-SD-WM-ATP-145 can be found in Appendix A and the master copy of WHC-SD-WM-ATP-146 can be found in Appendix B. Also included with this report is a matrix showing design criteria of the cone penetrometer moisture probe and the verification method used (Appendix C)

  2. Generator acceptance test and inspection report

    International Nuclear Information System (INIS)

    Johns, B.R.

    1997-01-01

    This Acceptance Test Report(ATR) is the completed testing and inspection of the new portable generator. The testing and inspection is to verify that the generator provided by the vendor meets the requirements of specification WHC-S-0252, Revision 2. Attached is various other documentation to support the inspection and testing

  3. Gas characterization system software acceptance test procedure

    International Nuclear Information System (INIS)

    Vo, C.V.

    1996-01-01

    This document details the Software Acceptance Testing of gas characterization systems. The gas characterization systems will be used to monitor the vapor spaces of waste tanks known to contain measurable concentrations of flammable gases

  4. Gas characterization system software acceptance test report

    International Nuclear Information System (INIS)

    Vo, C.V.

    1996-01-01

    This document details the results of software acceptance testing of gas characterization systems. The gas characterization systems will be used to monitor the vapor spaces of waste tanks known to contain measurable concentrations of flammable gases

  5. RISK ANALYSES USED IN ACCEPTANCE TESTING

    Directory of Open Access Journals (Sweden)

    Oxana STOROJ

    2016-06-01

    Full Text Available This article is talking about risk based testing approach in user acceptance testing UAT (User Acceptance Testing. There are presented definitions of risk and risk based testing. In addition, we are talking about risks that can appear during UAT and we are describing the process of testing based on risks. We propose some techniques and methods of identifying risks such as using Brainstorming, Delphi method,probability analysis method and others. Also, risk traceability matrix is presented as a method of prioritizing risks.

  6. Acceptance test procedure for core sample trucks

    International Nuclear Information System (INIS)

    Smalley, J.L.

    1995-01-01

    The purpose of this Acceptance Test Procedure is to provide instruction and documentation for acceptance testing of the rotary mode core sample trucks, HO-68K-4600 and HO-68K-4647. The rotary mode core sample trucks were based upon the design of the second core sample truck (HO-68K-4345) which was constructed to implement rotary mode sampling of the waste tanks at Hanford. Acceptance testing of the rotary mode core sample trucks will verify that the design requirements have been met. All testing will be non-radioactive and stand-in materials shall be used to simulate waste tank conditions. Compressed air will be substituted for nitrogen during the majority of testing, with nitrogen being used only for flow characterization

  7. Approaches to gaining public acceptance of repository siting

    International Nuclear Information System (INIS)

    Numark, N.J.; Wonder, E.F.

    1989-01-01

    An eight-country survey reveals a diversity of strategies that have been followed for siting radioactive waste repositories, as well as a range of levels of public acceptance of siting efforts. Although the strategies are not necessarily interchangeable from country to country, certain inferences may be drawn from worldwide siting experience regarding ways to maximize public acceptance. Furthermore, waste management organizations in these countries have placed varying amounts of stock in technical review by outside experts and in a range of communications strategies as means of improving public acceptance. Our survey of worldwide experience also allows some general observations to be made regarding the effectiveness of these efforts. Combining a strategy that elevates public acceptance to part of the overall mission of siting a waste management facility with strategies for appropriate communications and external technical review may be necessary and sufficient for gaining improvements in public acceptance of proposed repository sites

  8. Preparation of acceptance tests and criteria for the Test Blanket Systems to be operated in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Cuquel, B. [AIRBUS Defence and Space S.A.S., 13115 Saint Paul Lez Durance (France); Demange, D.; Ghidersa, B.-E. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Giancarli, L.M.; Iseli, M.; Jourdan, T. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Pascal, R.; Ring, W. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

    2015-10-15

    Highlights: • Initial guideline for acceptance testing and acceptance criteria for Test Blanket Systems in ITER. • These tests complement those required by the applicable codes and standards, and regulations. • Completion of TBS manufacture will be followed by Factory Acceptance Testing, prior to shipment. • Next steps are “Reception Inspection Tests”, and on-site pre-installation and components tests. • This guideline allows the detailing of the TBS specific test plans and their scheduling. - Abstract: This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for the TBS, starting from the end-product at the ITER Members factories, and to generally define the type of tests that have to be performed on the ITER site after shipment, and/or prior to the systems final commissioning phase.

  9. Acceptance test report for the AY-102 ENRAF densitometer

    International Nuclear Information System (INIS)

    Huber, J.H.

    1998-01-01

    On February 11, 1998, the AY-1 02, Riser 15E ENRAF Densitometer was acceptance tested per HNF-SD-WM-ATP-077. The test was performed at the Department of Energy's Hanford Site, 200 East Area, building MO-407. The test validated the functionality of the Densitometer for use by project W-320, C-1 06 Retrieval. The purpose of the test procedure was to verify the functionality of the ENRAF Series 854 ATG densitometer. Typically, all ENRAF Series 854 ATGs are acceptance tested before transport to the field. The ATP, as performed for level gauges, sets default program values within the gauge and verifies the gauge's force transducer calibration

  10. Acceptance test report for core sample trucks 3 and 4

    International Nuclear Information System (INIS)

    Corbett, J.E.

    1996-01-01

    The purpose of this Acceptance Test Report is to provide documentation for the acceptance testing of the rotary mode core sample trucks 3 and 4, designated as HO-68K-4600 and HO-68K-4647, respectively. This report conforms to the guidelines established in WHC-IP-1026, ''Engineering Practice Guidelines,'' Appendix M, ''Acceptance Test Procedures and Reports.'' Rotary mode core sample trucks 3 and 4 were based upon the design of the second core sample truck (HO-68K-4345) which was constructed to implement rotary mode sampling of the waste tanks at Hanford. Successful completion of acceptance testing on June 30, 1995 verified that all design requirements were met. This report is divided into four sections, beginning with general information. Acceptance testing was performed on trucks 3 and 4 during the months of March through June, 1995. All testing was performed at the ''Rock Slinger'' test site in the 200 West area. The sequence of testing was determined by equipment availability, and the initial revision of the Acceptance Test Procedure (ATP) was used for both trucks. Testing was directed by ICF-KH, with the support of WHC Characterization Equipment Engineering and Characterization Project Operations. Testing was completed per the ATP without discrepancies or deviations, except as noted

  11. Breathing air trailer acceptance test report

    International Nuclear Information System (INIS)

    Kostelnik, A.J.

    1996-01-01

    This Acceptance Test Report documents compliance with the requirements of specification WHC-S-0251, Rev.0 and ECNs 613530 and 606113. The equipment was tested according to WHC-SD-WM-ATP-104. The equipment tested is a Breathing Air Supply Trailer purchased as a design and fabrication procurement activity. The ATP was written by the Seller and was performed by the Seller with representatives of the Westinghouse Hanford Company witnessing portions of the test at the Seller's location

  12. W-087 Acceptance test procedure. Revision 1

    International Nuclear Information System (INIS)

    Joshi, A.W.

    1997-01-01

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks

  13. W-087 Acceptance test procedure. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Joshi, A.W.

    1997-06-10

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks.

  14. Acceptance test report: Backup power system

    International Nuclear Information System (INIS)

    Cole, D.B.

    1996-01-01

    Acceptance Test Report for construction functional testing of Project W-030 Backup Power System. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. Backup power includes a single 125 KW diesel generator, three 10-kva uninterruptible power supply units, and all necessary control

  15. Acceptance test report 2721-Z upgrades

    International Nuclear Information System (INIS)

    Keck, R.D.

    1998-01-01

    This test procedure provides instructions for acceptance testing of modifications to the 2721-Z diesel-generator system made by Project C-189. The modifications include (1) replacing the generator NUMA-LOGIC controller with connection to the PFP distributed control system (DCS), (2) replacing ATSI with a breaker switching scheme for 2736-ZB backup power and (3) providing a method for generator load and system testing

  16. Diesel generator trailer acceptance test procedure

    International Nuclear Information System (INIS)

    Kostelnik, A.J.

    1994-01-01

    This Acceptance Test Procedure (ATP) will document compliance with the requirements of WHC-S-0252 Rev. 1 and ECNs 609271, and 609272. The equipment being tested is a 150KW Diesel Generator mounted on a trailer with switchgear. The unit was purchased as a Design and Fabrication procurement activity. The ATP was written by the Seller and will be performed by the Seller with representatives of the Westinghouse Hanford Company witnessing the test at the Seller's location

  17. Void fraction instrument acceptance test procedure

    International Nuclear Information System (INIS)

    Stokes, T.I.; Pearce, K.L.

    1994-01-01

    This document presents the results of the acceptance test for the mechanical and electrical features (not specifically addressed by the software ATP) of the void fraction instrument (VFI). Acceptance testing of the VFI, control console, and decontamination spray assembly was conducted in the 306E building high bay and area adjacent to the facility. The VFI was tested in the horizontal position supported in multiple locations on rolling tables. The control console was located next to the VFI pneumatic control assembly. The VFI system was operated exactly as is expected in the tank farm, with the following exceptions: power was provided from a building outlet and the VFI was horizontal. The testing described in this document verifies that the mechanical and electrical features are operating as designed and that the unit is ready for field service

  18. W-026, acceptance test report manipulator system

    International Nuclear Information System (INIS)

    Watson, T.L.

    1997-01-01

    The purpose of the WRAP Manipulator System Acceptance Test Plan (ATP) is to verify that the 4 glovebox sets of WRAP manipulator components, including rail/carriage, slave arm, master controller and auxiliary equipment, meets the requirements of the functional segments of 14590 specification. The demonstration of performance elements of the ATP are performed as a part of the Assembly specifications. Manipulator integration is integrated in the performance testing of the gloveboxes. Each requirement of the Assembly specification will be carried out in conjunction with glovebox performance tests

  19. Acceptance Testing Of Web Applications With Test Description Language

    Directory of Open Access Journals (Sweden)

    Łukasz Olek

    2014-01-01

    Full Text Available Acceptance tests are usually created by a client after a part of a system is implemented. However, some methodologies propose the elaboration of test cases before implementing a system. This approach increases the probability of system implementation that fulfills requirements, but may be problematic for customers and testers. To allow acceptance testing in such conditions, we propose to define test cases by recording them on an interactive mockup (a low detailed user-interface prototype. The paper focuses on Test Description Language, a notation used to store test cases.

  20. Conversion of Semipalatinsk test site

    International Nuclear Information System (INIS)

    Cherepnin, Yu. S.

    1997-01-01

    The conversion of the former defense enterprises of STS (Semipalatinsk Test Sate) started under very difficult conditions, when not only research and production activity, but all social life of Kurchatov city were conversed which was caused by a fast curtailment and restationing of Russian military units from the test site. A real risk of a complete destruction of the whole research and production structure of the city existed. From this point of view, the decision of the Republic of Kazakhstan Government to create the National Nuclear Center on the base of the test site research enterprises was actual and timely. During 1993, three research institutes of NNC RK - Institute of Atomic Energy, Institute of Geophysics Research and Institute of Radiation Safety and Environment were established. This decision, under conditions of the Ussr disintegration and liquidation of the test site military divisions, allowed to preserve the qualified personnel, to provide and follow-up the operation of nuclear dangerous facilities, to develop and start the realization of the full scale conversion program.At present time, directions and structure of basic research work in NNC RK are as follows: - liquidation of nuclear explosions consequences; - liquidation of technological infrastructure used for preparation and conduction of nuclear weapon testing; - creation of technology, equipment and places for acceptance and storage of radioactive wastes; - working out of atomic energy development conception in Kazakhstan; - study of reactor core melt behavior under severe accidents in NPP; - development of methods and means of nuclear testing detection, continuous monitoring of nuclear explosions; - experimental work on a study of structure materials behavior of ITER thermonuclear reactor; - creation of industries requiring a lage implementation of science

  1. Acceptance Test Plan for Fourth-Generation Corrosion Monitoring Cabinet

    International Nuclear Information System (INIS)

    NORMAN, E.C.

    2000-01-01

    This Acceptance Test Plan (ATP) will document the satisfactory operation of the third-generation corrosion monitoring cabinet (Hiline Engineering Part No.0004-CHM-072-C01). This ATP will be performed by the manufacturer of the cabinet prior to delivery to the site. The objective of this procedure is to demonstrate and document the acceptance of the corrosion monitoring cabinet. The test will consist of a continuity test of the cabinet wiring from the end of cable to be connected to corrosion probe, through the appropriate intrinsic safety barriers and out to the 15 pin D-shell connectors to be connected to the corrosion monitoring instrument. Additional testing will be performed using a constant current and voltage source provided by the corrosion monitoring hardware manufacturer to verify proper operation of corrosion monitoring instrumentation

  2. Acceptance Test Report for 241-U compressed air system

    International Nuclear Information System (INIS)

    Freeman, R.D.

    1994-01-01

    This Acceptance Test Report (ATR) documents the results of acceptance testing of a newly upgraded compressed air system at 241-U Farm. The system was installed and the test successfully performed under work package 2W-92-01027

  3. Acceptance Testing of Thermoluminescent Dosimeter Holders.

    Science.gov (United States)

    Romanyukha, Alexander; Grypp, Matthew D; Sharp, Thad J; DiRito, John N; Nelson, Martin E; Mavrogianis, Stanley T; Torres, Jeancarlo; Benevides, Luis A

    2018-05-01

    The U.S. Navy uses the Harshaw 8840/8841 dosimetric (DT-702/PD) system, which employs LiF:Mg,Cu,P thermoluminescent dosimeters (TLDs), developed and produced by Thermo Fisher Scientific (TFS). The dosimeter consists of four LiF:Mg,Cu,P elements, mounted in Teflon® on an aluminum card and placed in a plastic holder. The holder contains a unique filter for each chip made of copper, acrylonitrile butadiene styrene (ABS), Mylar®, and tin. For accredited dosimetry labs, the ISO/IEC 17025:2005(E) requires an acceptance procedure for all new equipment. The Naval Dosimetry Center (NDC) has developed and tested a new non-destructive procedure, which enables the verification and the evaluation of embedded filters in the holders. Testing is based on attenuation measurements of low-energy radiation transmitted through each filter in a representative sample group of holders to verify that the correct filter type and thickness are present. The measured response ratios are then compared with the expected response ratios. In addition, each element's measured response is compared to the mean response of the group. The test was designed and tested to identify significant nonconformities, such as missing copper or tin filters, double copper or double tin filters, or other nonconformities that may impact TLD response ratios. During the implementation of the developed procedure, testing revealed a holder with a double copper filter. To complete the evaluation, the impact of the nonconformities on proficiency testing was examined. The evaluation revealed failures in proficiency testing categories III and IV when these dosimeters were irradiated to high-energy betas.

  4. Specification and acceptance testing of radiotherapy treatment planning systems

    International Nuclear Information System (INIS)

    2007-04-01

    Quality assurance (QA) in the radiation therapy treatment planning process is essential to ensure accurate dose delivery to the patient and to minimize the possibility of accidental exposure. The computerized radiotherapy treatment planning systems (RTPSs) are now widely available in industrialized and developing countries and it is of special importance to support hospitals in Member States in developing procedures for acceptance testing, commissioning and QA of their RTPSs. Responding to these needs, a group of experts developed an IAEA publication with such recommendations, which was published in 2004 as IAEA Technical Reports Series No. 430. This report provides a general framework and describes a large number of tests and procedures that should be considered by the users of new RTPSs. However, small hospitals with limited resources or large hospitals with high patient load and limited staff are not always able to perform complete characterization, validation and software testing of algorithms used in RTPSs. Therefore, the IAEA proposed more specific guidelines that provide a step-by-step recommendation for users at hospitals or cancer centres how to implement acceptance and commissioning procedures for newly purchased RTPSs. The current publication was developed in the framework of the Coordinated Research Project on Development of Procedures for Quality Assurance for Dosimetry Calculations in Radiotherapy and uses the International Electrotechnical Commission (IEC) standard IEC 62083, Requirements for the Safety of Radiotherapy Treatment Planning Systems as its basis. The report addresses the procedures for specification and acceptance testing of RTPSs to be used by both manufacturers and users at the hospitals. Recommendations are provided for specific tests to be performed at the manufacturing facility known as type tests, and for acceptance tests to be performed at the hospital known as site tests. The purpose of acceptance testing is to demonstrate to the

  5. Computer-Based Testing: Test Site Security.

    Science.gov (United States)

    Rosen, Gerald A.

    Computer-based testing places great burdens on all involved parties to ensure test security. A task analysis of test site security might identify the areas of protecting the test, protecting the data, and protecting the environment as essential issues in test security. Protecting the test involves transmission of the examinations, identifying the…

  6. Planning and acceptance testing of MV therapy installations

    International Nuclear Information System (INIS)

    Almond, Peter R.; Horton, John L.

    1995-01-01

    Purpose: This course is designed for practitioners and beginners in brachytherapy. The aim is to review biological principles equipment are aware of all aspects involved. The object is to cover in a broad overview the considerations that go into selecting, installing, testing and accepting megavoltage therapy equipment and to provide a resource for more detailed information. Planning and acceptance testing of a megavoltage therapy installation is a major undertaking for any size group, institution or department. It can take approximately two years from the time a decision is made to get a machine to where the first patient is treated. Because the equipment and site preparation are expensive, and most of the machines are complex and can be supplied by several different manufacturers, it is imperative that a great deal of thought and care go into the decision: the aim being that the specifications of the machine that is installed meet the immediate need of the department and the needs for the projected lifetime of the equipment. A general survey of the types of equipment available will be presented. This will concentrate on general purpose linear accelerators, although Cobalt 60 machines, microtrons and special purpose machines (intra-operative equipment) will also be covered. General descriptions of the machines along with typical specifications will be given. Selecting the best machine to meet specific needs can be quite complex and criteria for making the selection are presented in a series of twelve steps. site selection and room design, including the console area, are also critical. The general principles for shielding calculations will be provided. Critical to any installation is the acceptance testing of the equipment including material and radiation oncology performance tests. These tests will be outlined. A reading list of suitable references describing in detail many of the aspects of this course will be provided

  7. Managing Hanford Site solid waste through strict acceptance criteria

    International Nuclear Information System (INIS)

    Jasen, W.G.; Pierce, R.D.; Willis, N.P.

    1993-02-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

  8. Open-field test site

    Science.gov (United States)

    Gyoda, Koichi; Shinozuka, Takashi

    1995-06-01

    An open-field test site with measurement equipment, a turn table, antenna positioners, and measurement auxiliary equipment was remodelled at the CRL north-site. This paper introduces the configuration, specifications and characteristics of this new open-field test site. Measured 3-m and 10-m site attenuations are in good agreement with theoretical values, and this means that this site is suitable for using 3-m and 10-m method EMI/EMC measurements. The site is expected to be effective for antenna measurement, antenna calibration, and studies on EMI/EMC measurement methods.

  9. Acceptance test for 900 MWe PWR unit replacement steam generators

    International Nuclear Information System (INIS)

    Gourguechon, B.

    1993-01-01

    During the first half of 1994, the Gravelines 1 steam generators will be replaced (SG replacement procedure). The new SG's differ from the former components notably by the alloy used for the tube bundle, in this case, the high chromium content Inconel 690. So, from this standpoint, they are to be considered as PWR 900 replacement SG first models and their thermal efficiency has consequently to be assessed. This will provide an opportunity of ensuring that the performance of the components delivered is in compliance with requirements and of making the necessary provisions if significant deviations are observed. The EFMT branch, which has been in charge of the instrumentation and acceptance of the different SG first models since the first PWR plants were commissioned, will be responsible for the acceptance tests and the ultimate validation of a performance assessment procedure applicable to the future replacement steam generators. The methods and tests proposed for SG expert appraisal are based on consideration of the importance of primary measurement quality for satisfactory SG assessment and of the new test facilities with which the 900 and 1 300 PWR plants are gradually being equipped. These facilities provide an on-site computer environment for tests compatible with the tools (PATTERN, etc.) used at EFMT and in other departments. This test is the first of this kind performed by EFMT and the test facility of a nuclear power plant. (author). 6 figs

  10. MCO Engineering Test Report Fuel Basket Handling Grapple Acceptance Test

    International Nuclear Information System (INIS)

    CHENAULT, D.M.

    2000-01-01

    Acceptance testing of the production SNF Fuel Basket lift grapples to the required 150 percent maximum lift load is documented herein. The report shows the results affirming the proof test passage. The primary objective of this test was to confirm the load rating of the grapple per applicable requirements of ANSI 14 6 American National Standard For Radioactive Materials Special Lifting Devices for Shipping Containers Weighing 10,000 pounds (4500kg) or More. The above Standard requires a load test of 150% of the design load which must be held for a minimum of 10 minutes followed by a Liquid Penetrant or Magnetic Particle examination of critical areas and welds in accordance with the ANSI/ASME Boiler and Pressure Vessel Code 1989 Section 111 Division 1 section NF 5350

  11. SP-100 Test Site

    International Nuclear Information System (INIS)

    Cox, C.M.; Mahaffey, M.K.; Miller, W.C.

    1988-01-01

    Preparatory activities are well under way at Hanford to convert the 309 Containment Building and its associated service wing to a 2.5 MWt nuclear test facility for the SP-100 Ground Engineering System (GES) test. Preliminary design is complete, encompassing facility modifications, a secondary heat transport system, a large vacuum system to enclose the high temperature reactor, a test assembly cell and handling system, control and data processing systems, and safety and auxiliary systems. The design makes extensive use of existing equipment to minimize technical risk and cost. Refurbishment of this equipment is 75% complete. The facility has been cleared of obstructing equipment from its earlier reactor test. Current activities are focusing on definitive design and preparation of the Preliminary Safety Analysis Report (PSAR) aimed at procurement and construction approvals and schedules to achieve reactor criticality by January 1992. 6 refs

  12. Conclusions regarding geotechnical acceptability of the WIPP site

    International Nuclear Information System (INIS)

    Weart, W.D.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP) was authorized by Congress in 1980 as an unlicensed research and development (R and D) facility to demonstrate the safe disposal of radioactive wastes arising from the defense activities and programs of the United States. WIPP is now being constructed in southeast New Mexico, using salt beds about 655 m below the surface of the ground. Construction of the full WIPP facility will not commence until a preliminary underground excavation phase, called Site and Preliminary Design Validation (SPDV), is satisfactorily concluded in the summer of 1983. This SPDV program permits confirmation of subsurface geology, in drifts at planned facility depth that extend for 1555 m in a north-south direction, and in the two vertical shafts that provide access to these drifts. The subsurface studies are nearing completion, and it is therefore appropriate to draw conclusions regarding the geotechnical acceptability of the WIPP site. Four geotechnical elements are discussed: dissolution, deformation, hydrologic regime, and natural resources

  13. Topographical mapping system for radiological and hazardous environments acceptance testing

    International Nuclear Information System (INIS)

    Armstrong, G.A.; Dochat, G.R.

    1997-01-01

    During the summer of 1996, the Topographical Mapping System (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the Interactive Computer-Enhanced Remote-Viewing System (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and ICERVS was initiated by the US Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention

  14. Topographical mapping system for radiological and hazardous environments acceptance testing

    Science.gov (United States)

    Armstrong, Gary A.; Dochat, G. R.

    1997-09-01

    During the summer of 1996, the topographical mapping system (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the interactive computer-enhanced remote-viewing system (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and the ICERVS was initiated by the U.S. Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention.

  15. Underground Nuclear Testing Program, Nevada Test Site

    International Nuclear Information System (INIS)

    1975-09-01

    The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

  16. Double tracks test site characterization report

    International Nuclear Information System (INIS)

    1996-05-01

    This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy's (DOE) Streamlined Approach for Environmental Restoration (SAFER)

  17. User acceptance testing a step-by-step guide

    CERN Document Server

    Hambling, Brian

    2013-01-01

    Every information system brought into service in every type of organisation requires user acceptance testing. This book is a hands-on manual for non-testing specialists to plan and carry out an effective acceptance test of an information system. It also identifies ways of making the process as simple and cost-effective as possible.

  18. Acceptance test procedure for High Pressure Water Jet System

    International Nuclear Information System (INIS)

    Crystal, J.B.

    1995-01-01

    The overall objective of the acceptance test is to demonstrate a combined system. This includes associated tools and equipment necessary to perform cleaning in the 105 K East Basin (KE) for achieving optimum reduction in the level of contamination/dose rate on canisters prior to removal from the KE Basin and subsequent packaging for disposal. Acceptance tests shall include necessary hardware to achieve acceptance of the cleaning phase of canisters. This acceptance test procedure will define the acceptance testing criteria of the high pressure water jet cleaning fixture. The focus of this procedure will be to provide guidelines and instructions to control, evaluate and document the acceptance testing for cleaning effectiveness and method(s) of removing the contaminated surface layer from the canister presently identified in KE Basin. Additionally, the desired result of the acceptance test will be to deliver to K Basins a thoroughly tested and proven system for underwater decontamination and dose reduction. This report discusses the acceptance test procedure for the High Pressure Water Jet

  19. Acceptance of Colonoscopy Requires more than Test Tolerance

    Directory of Open Access Journals (Sweden)

    Amanda Condon

    2008-01-01

    Full Text Available BACKGROUND: Colon cancer screening, including colonoscopy, lags behind other forms of cancer screening for participation rates. The intrinsic nature of the endoscopic procedure may be an important barrier that limits patients from finding this test acceptable and affects willingness to undergo screening. With colon cancer screening programs emerging in Canada, test characteristics and their impact on acceptance warrant consideration.

  20. Evaluation of acceptance strength tests for concrete pavements.

    Science.gov (United States)

    2005-06-30

    The North Carolina Department of Transportation has used traditionally flexural strength tests for acceptance : testing of Portland cement concrete pavements. This report summarizes a research project implemented to : investigate the feasibility of u...

  1. Enraf Series 854 advanced technology gauge (ATG) acceptance test procedure

    International Nuclear Information System (INIS)

    Huber, J.H.

    1996-01-01

    This Acceptance Test Procedure was written to test the Enraf Series 854 Advanced Technology Gauge (ATG) prior to installation in the Tank Farms. The procedure sets various parameters and verifies that the gauge is functional

  2. Operator coil monitoring Acceptance Test Procedure

    International Nuclear Information System (INIS)

    Erhart, M.F.

    1995-01-01

    The readiness of the Data Acquisition and Control System (DACS) to provide monitoring and control of the Programmable Logic Controller (PLC) abort coils from the Master and RSS stations will be systematically tested during performance of this procedure. It should be noted that these are not physical abort coils but software coils controlled by the software's ladder logic. The readiness of the DACS to properly interface with the ENRAF wire level gauge installed in the SY-101 storage tank will also be tested. During this test, a verification of all abort coil indications will be conducted at the DACS Development Facility in the 306E Building by injecting an input signal for each DACS sensor that has an associated abort coil until the abort coil actuates, and then ensuring that the status of the abort coil indicated at the Master and RSS stations is correct. Each abort coil will also be tested to ensure that the ''ENABLE'' and ''DISABLE'' controls from the Master and RSS stations function correctly, and only with the use of proper passwords

  3. Reevaluating NIMBY: Evolving Public Fear and Acceptance in Siting a Nuclear Waste Facility

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins-Smith, Hank C.; Silva, Carol L.; Nowlin, Matthew C.; deLozier, Grant (Dept. of Political Science, Univ. of Oklahoma, Norman, OK (United States))

    2010-09-15

    The not-in-my-backyard (NIMBY) syndrome has long been the focus of academic and policy research. We test several competing hypothesis concerning the sources of NIMBY sentiments, including demographics, proximity, political ideology and partisanship, and the unfolding policy process over time. To test these hypotheses we use survey data collected in New Mexico dealing with risk perceptions and acceptance related to the Waste Isolation Pilot Project (WIPP), a permanent storage site for radioactive waste located near Carlsbad, New Mexico. WIPP became operational and received its first shipment of waste on March 26, 1999. This study tracks the changes of risk perception and acceptance over a decade, using measures taken from 35 statewide surveys of New Mexico citizens spanning the 11-year period from fall 1990 to summer 2001. This time span includes periods before and after WIPP became operational. We find that acceptance of WIPP is greater among those in the most proximate counties to WIPP. Surprisingly, and contrary to expectations drawn from the broader literature, acceptance is also greater among those who live closest to the nuclear waste transportation route. We also find that ideology, partisanship, government approval and broader environmental concerns influence support for WIPP acceptance. Finally, the sequence of procedural steps taken toward formal approval of WIPP by government agencies proved to be important to public acceptance, the most significant being the opening of the WIPP facility itself

  4. Reevaluating NIMBY: Evolving Public Fear and Acceptance in Siting a Nuclear Waste Facility

    International Nuclear Information System (INIS)

    Jenkins-Smith, Hank C.; Silva, Carol L.; Nowlin, Matthew C.; de Lozier, Grant

    2010-09-01

    The not-in-my-backyard (NIMBY) syndrome has long been the focus of academic and policy research. We test several competing hypothesis concerning the sources of NIMBY sentiments, including demographics, proximity, political ideology and partisanship, and the unfolding policy process over time. To test these hypotheses we use survey data collected in New Mexico dealing with risk perceptions and acceptance related to the Waste Isolation Pilot Project (WIPP), a permanent storage site for radioactive waste located near Carlsbad, New Mexico. WIPP became operational and received its first shipment of waste on March 26, 1999. This study tracks the changes of risk perception and acceptance over a decade, using measures taken from 35 statewide surveys of New Mexico citizens spanning the 11-year period from fall 1990 to summer 2001. This time span includes periods before and after WIPP became operational. We find that acceptance of WIPP is greater among those in the most proximate counties to WIPP. Surprisingly, and contrary to expectations drawn from the broader literature, acceptance is also greater among those who live closest to the nuclear waste transportation route. We also find that ideology, partisanship, government approval and broader environmental concerns influence support for WIPP acceptance. Finally, the sequence of procedural steps taken toward formal approval of WIPP by government agencies proved to be important to public acceptance, the most significant being the opening of the WIPP facility itself

  5. GMS/DACS interface acceptance test procedure

    International Nuclear Information System (INIS)

    Zuehlke, A.C.

    1994-01-01

    The readiness of the Data Acquisition and Control System (DACS) to provide monitoring of existing, and newly installed, instrumentation associated with the SY-101 tank Gas Monitoring Systems will be systematically evaluated by performance of this procedure. All new alarms will be verified to function at the required setpoints. The change of I/O Drop 17 to I/O Drop 13 will be checked to verify that all associated alarms and screen displays are correct. All new or changed Control Screens which provide operator interface with the Gas Monitoring Systems readouts during operations will be verified to be adequate and correct. The DACS, which is housed in a trailer located just outside of the north fence at the SY tank farm, receives input signals from a variety of sensors located in and around the SY-101 tank. These sensors provide information such as: tank vapor space and ventilation system H 2 concentration; tank waste temperature; tank pressure; waste density; operating pump parameters such as speed, flow, rotational position, discharge pressure, and internal temperature; strain (for major equipment); and waste level. The output of these sensors is conditioned and transmitted to the DACS computers where these signals are displayed, recorded, and monitored for out-of-specification conditions. If abnormal conditions are detected, then, in certain situations, the DACS automatically generates alarms and causes the system to abort pump operations. The portions of the system to be tested include: new RGA5 gas monitor; existing gas chromatographs; FTIR; B ampersand K (Photo) NH 3 equipment; any new or changed Genesis screens; and I/O Drop 13

  6. Acceptance test report for the Westinghouse 100 ton hydraulic trailer

    International Nuclear Information System (INIS)

    Barrett, R.A.

    1995-01-01

    The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP's facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson's facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified

  7. Factory Acceptance Test Procedure Westinghouse 100 ton Hydraulic Trailer

    International Nuclear Information System (INIS)

    Aftanas, B.L.

    1994-01-01

    This Factory Acceptance Test Procedure (FAT) is for the Westinghouse 100 Ton Hydraulic Trailer. The trailer will be used for the removal of the 101-SY pump. This procedure includes: safety check and safety procedures; pre-operation check out; startup; leveling trailer; functional/proofload test; proofload testing; and rolling load test

  8. Sharing Data between Mobile Devices, Connected Vehicles and Infrastructure Task 6: Prototype Acceptance Test Summary Report

    Science.gov (United States)

    2017-10-30

    The Task 6 Prototype Acceptance Test Summary Report summarizes the results of Acceptance Testing carried out at Battelle facilities in accordance with the Task 6 Acceptance Test Plan. The Acceptance Tests were designed to verify that the prototype sy...

  9. Specification and acceptance testing of nuclear medicine equipment

    International Nuclear Information System (INIS)

    Wegst, A.V.; Erickson, J.J.

    1984-01-01

    The purchase of nuclear medicine equipment is of prime importance in the operation of a clinical service. Failure to properly evaluate the potential uses of the instrumentation and the various operational characteristics of the equipment can often result in the purchase of inappropriate or inferior instruments. The magnitude of the purchase in terms of time and financial investments make it imperative that the purchase be approached in a systematic manner. Consideration of both the intended clinical functions and personnel requirements is important. It is necessary also to evaluate the ability of the equipment vendor to support the instrumentation after the purchase has been completed and the equipment installed in the clinical site. The desired specifications of the instrument characteristics should be stated in terms that can be verified by acceptance testing. The complexity of modern instrumentation and the sensitivity of it to the environment require the buyer to take into account the potential problems of controlling the temperature, humidity, and electrical power of the installation site. If properly and systematically approached, the purchase of new nuclear medicine instrumentation can result in the acquisition of a powerful diagnostic tool which will have a useful lifetime of many years. If not so approached, it may result in the expenditure of a large amount of money and personnel time without the concomitant return in useful clinical service. (author)

  10. Acceptance test procedure MICON software exhaust fan control modifications; TOPICAL

    International Nuclear Information System (INIS)

    SILVAN, G.R.

    1999-01-01

    This acceptance test verifies the MICON program changes for the new automatic transfer switch ATS-2 alarms, the Closed Loop Cooling isolator status, the CB-3 position alarm, and the alarms for the new emergency fan damper backup air compressor

  11. Intelligent Network Flow Optimization (INFLO) prototype acceptance test summary.

    Science.gov (United States)

    2015-05-01

    This report summarizes the results of System Acceptance Testing for the implementation of the Intelligent Network : Flow Optimization (INFLO) Prototype bundle within the Dynamic Mobility Applications (DMA) portion of the Connected : Vehicle Program. ...

  12. Nevada Test Site closure program

    International Nuclear Information System (INIS)

    Shenk, D.P.

    1994-08-01

    This report is a summary of the history, design and development, procurement, fabrication, installation and operation of the closures used as containment devices on underground nuclear tests at the Nevada Test Site. It also addresses the closure program mothball and start-up procedures. The Closure Program Document Index and equipment inventories, included as appendices, serve as location directories for future document reference and equipment use

  13. Acceptance testing and commissioning of a new model HDR afterloader

    International Nuclear Information System (INIS)

    McDermott, Patrick N.; Somnay, Archana R.; Alecu, Rodica

    1996-01-01

    We have recently performed acceptance testing procedures and have commissioned a new model HDR afterloader, the Varian VariSource with ''Intelligent Drive.'' Our site was one of the first installations worldwide. It is our intent to describe our tests and the results of the tests particularly as they may differ from other afterloaders. The Ir-192 source is unique among afterloaders marketed in the US in that it is very slender (OD of source wire is 0.59 mm) and relatively long (two 0.5 cm sources for a total active length of 1.0 cm). A check of source homogeneity by autoradiograph as urged by the US Nuclear Regulatory Commission demonstrates no detectable source inhomogeneity. Reentrant well ionization chambers are calibrated in the US with a 3.5 mm long source at Accredited Dosimetry Calibration Laboratories. Therefore calibration needs to be considered with some care. Calibration of the first delivered source with a well ionization chamber indicated agreement with the manufacturer's stated activity to within 0.5%. Source positioning is checked with a device called a 'cam scale'. Tests have been carried out on this system and it has been found to accurately indicate source position to within ±0.5 mm. Timer accuracy has been found to be better than 0.1% for dwell times of several hundred seconds. The intelligent drive system and the small source diameter allow the source wire to negotiate paths with small radius of curvature. A series of tests have been made in which the source is forced to negotiate 'U' turns of decreasing radius of curvature. A 4.7 F, 100 cm long catheter was used for these tests and the 'U' turn was positioned at approximately 90 cm. Under these conditions, the VariSource was consistently able to traverse a 1.25 cm radius of curvature, which is better than the manufacturer's stated limit of 1.5 cm

  14. W-026, transuranic waste (TRU) glovebox acceptance test report

    International Nuclear Information System (INIS)

    Leist, K.J.

    1998-01-01

    On July 18, 1997, the Transuranic (TRU) glovebox was tested using glovebox acceptance test procedure 13021A-86. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, sorting table, lidder/delidder device and the TRU empty drum compactor were also conducted. As of February 25, 1998, 10 of the 102 test exceptions that affect the TRU glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test exceptions are provided as appendices to this report

  15. WRAP low level waste (LLW) glovebox acceptance test report

    International Nuclear Information System (INIS)

    Leist, K.J.

    1998-01-01

    In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report

  16. WRAP low level waste (LLW) glovebox acceptance test report

    Energy Technology Data Exchange (ETDEWEB)

    Leist, K.J.

    1998-02-17

    In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report.

  17. Site acceptability and power availability: needed institutional changes

    International Nuclear Information System (INIS)

    Haggard, J.E.

    1975-01-01

    Timely assurance of power plant site availability is threatened by institutional inabilities to resolve often competing environmental/energy requirements. Institutional changes are needed. The issue of site approval should be separated from that of plant approval. A ''one-stop'' forum for site approval, modeled after Washington State's Thermal Power Plant Siting Act, is needed. The one-stop process utilizes one forum composed of officials drawn from all agencies involved in site related issues. A joint Federal/State Siting Council, with sole jurisdiction over site approval, is recommended. The State Council would have a determinative vote on all issues not otherwise preempted by federal legislation. 21 references. (U.S.)

  18. PUREX SAMCONS uninterruptible power supply (UPS) acceptance test report

    International Nuclear Information System (INIS)

    Blackaby, W.B.

    1997-01-01

    This Acceptance Test Report for the PUREX Surveillance and Monitoring and Control System (SAMCONS) Uninterruptible Power Supply (UPS) Acceptance Test Procedure validates the operation of the UPS, all alarming and display functions and the ability of the UPS to supply power to the SAMCONS as designed. The proper installation of the PUREX SAMCONS Trailer UPS components and wiring will be systematically evaluated by performance of this procedure. Proper operation of the SAMCONS computer UPS will be verified by performance of a timed functional load test, and verification of associated alarms and trouble indications. This test procedure will be performed in the SAMCONS Trailer and will include verification of receipt of alarms at the SAMCONS computer stations. This test may be performed at any time after the completion of HNF-SD-CP-ATP-083, PUREX Surveillance and Monitoring and Control System (SAMCONS) Acceptance Test Procedure, when computer display and alarm functions have been proven to operate correctly

  19. Surface moisture measurement system acceptance testing work plan

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1996-01-01

    This work plan addresses testing of the Surface Moisture Measurement System (SMMS) at the Fuels and Materials Examination Facility (FMEF). The purpose of this plan is to define the scope of work, identify organizational responsibilities, describe test control requirements, and provide estimated costs and schedule associated with acceptance testing

  20. Surface moisture measurement system hardware acceptance test procedure

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1996-01-01

    The purpose of this acceptance test procedure is to verify that the mechanical and electrical features of the Surface Moisture Measurement System are operating as designed and that the unit is ready for field service. This procedure will be used in conjunction with a software acceptance test procedure, which addresses testing of software and electrical features not addressed in this document. Hardware testing will be performed at the 306E Facility in the 300 Area and the Fuels and Materials Examination Facility in the 400 Area. These systems were developed primarily in support of Tank Waste Remediation System (TWRS) Safety Programs for moisture measurement in organic and ferrocyanide watch list tanks

  1. Neutron absorber qualification and acceptance testing from the designer's perspective

    International Nuclear Information System (INIS)

    Bracey, W.; Chiocca, R.

    2004-01-01

    Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3σ. The original and current bases for the reduced 10 B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and process controls

  2. Acceptance Test Procedure for New Pumping and Instrumentation Control Skid M

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This Acceptance Test Procedure (ATP) verifies proper construction per the design drawings and tests for proper functioning of the Pumping and Instrumentation Control (PIC) skid ''M''. The Scope section lists the systems and functions to be checked. This ATP will be performed at the Site Fabrication Service's (SFS) shop upon completion of construction of the PIC skid

  3. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''V''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) verifies proper construction per the design drawings and tests for proper functioning of the Pumping Instrumentation and Control (PIC) skid ''V''. The scope section lists the systems and functions to be checked. This ATP will be performed at the Site Fabrication Services (SFS) shop upon completion of the construction of the PIC skid

  4. 105K West Isolation Barrier Acceptance Test results

    International Nuclear Information System (INIS)

    McCracken, K.J.; Irwin, J.J.

    1995-01-01

    The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KW/100K. The tests were performed in accordance with the test plan and acceptance test procedure. The test report contains the test data. This document compares the test data against the criteria. A discussion of the leak rate analytical characterization describes how the flow characteristics flow rate will be determined using the test data from the test report. Two modes of water loss were considered; basin and/or discharge chute leakage, and evaporation. An initial test established baseline leakage data and instrumentation performance. Test 2 evaluated the sealing performance of the isolation barrier by inducing an 11 in. (27.9 cm) level differential across the barrier. The leak rate at this 11 in. (27.9 cm) level is extrapolated to the 16 ft. (4.9 m) level differential postulated in the DBE post seismic event. If the leak rate, adjusted for evaporation and basin leakage (determined from Test 1), is less than the SAR limit of 1,500 gph (5,680 lph) at a 16 ft (4.9 m) level differential, the barriers pass the acceptance test

  5. Acceptance test report MICON software exhaust fan control

    International Nuclear Information System (INIS)

    Keck, R.D.

    1998-01-01

    This test procedure specifies instructions for acceptance testing of software for exhaust fan control under Project ESPT (Energy Savings Performance Contract). The software controls the operation of two emergency exhaust fans when there is a power failure. This report details the results of acceptance testing for the MICON software upgrades. One of the modifications is that only one of the emergency fans will operate at all times. If the operating fan shuts off or fails, the other fan will start and the operating fan will be stopped

  6. Initial acceptance test experience with FFTF plant equipment

    International Nuclear Information System (INIS)

    Brown, R.K.; Coleman, K.A.; Mahaffey, M.K.; McCargar, C.G.; Young, M.W.

    1978-09-01

    The purpose of this paper is to examine the initial acceptance test experience of certain pieces of auxiliary equipment of the Fast Flux Test Facility (FFTF). The scope focuses on the DHX blowers and drive train, inert gas blowers, H and V containment isolation valves, and the Surveillance and In-service Inspection (SISI) transporter and trolley. For each type of equipment, the discussion includes a summary of the design and system function, installation history, preoperational acceptance testing procedures and results, and unusual events and resolutions

  7. Acceptance test report, plutonium finishing plant life safety upgrade

    International Nuclear Information System (INIS)

    Hodge, S.G.

    1994-01-01

    This acceptance Test Procedure (ATP) has been prepared to demonstrate that modifications to the Fir Protection systems function as required by project criteria. The ATP will test the Fire Alarm Control Panels, Flow Alarm Pressure Switch, Heat Detectors, Smoke Detectors, Flow Switches, Manual Pull Stations, and Gong/Door By Pass Switches

  8. Acceptance test report for portable exhauster POR-007/Skid E

    International Nuclear Information System (INIS)

    Kriskovich, J.R.

    1998-01-01

    This document describes Acceptance Testing performed on Portable Exhauster POR-007/Skid E. It includes measurements of bearing vibration levels, pressure decay testing, programmable logic controller interlocks, high vacuum, flow and pressure control functional testing. The purpose of Acceptance testing documented by this report was to demonstrate compliance of the exhausters with the performance criteria established within HNF-0490, Rev. 1 following a repair and upgrade effort at Hanford. In addition, data obtained during this testing is required for the resolution of outstanding Non-conformance Reports (NCR), and finally, to demonstrate the functionality of the associated software for the pressure control and high vacuum exhauster operating modes provided for by W-320. Additional testing not required by the ATP was also performed to assist in the disposition and close out of receiving inspection report and for application design information (system curve). Results of this testing are also captured within this document

  9. Multiport riser and flange assemblies acceptance test report

    International Nuclear Information System (INIS)

    Precechtel, D.R.; Schroeder, B.K.

    1994-01-01

    This document presents the results of the acceptance test for the multiport riser (MPR) and multiport flange (MPF) assemblies. The accepted MPR and MPF assemblies will be used in support of the hydrogen mitigation project for double-shell waste tank 241-SY-101 and other related projects. The testing described in this document verifies that the mechanical and interface features are operating as designed and that the unit is ready for field service. The objectives of the acceptance testing were as follows: Basic equipment functions and mechanical interfaces were verified; Installation and removal of equipment were demonstrated to the degree possible; Operation of the decon spray system and all valving was confirmed; and the accumulated leak rate of the MPR and MPF assemblies was determined

  10. Acceptance test report for the Westinghouse 100 ton hydraulic trailer

    Energy Technology Data Exchange (ETDEWEB)

    Barrett, R.A.

    1995-03-06

    The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP`s facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson`s facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified.

  11. Acceptance test for graphite components and construction status of HTTR

    International Nuclear Information System (INIS)

    Iyoku, T.; Ishihara, M.; Maruyama, S.; Shiozawa, S.; Tsuji, N.; Miki, T.

    1996-01-01

    In March, 1991, the Japan Atomic Energy Research Institute (JAERI) started to constructed the High Temperature engineering Test Reactor(HTTR) which is a 30-MW(thermal) helium gas-cooled reactor with a core composed of prismatic graphite blocks piled on the core support graphite structures. Two types of graphite materials are used in the HTTR. One is the garde IG-110, isotropic fine grain graphite, another is the grade PGX, medium-to-fine grained molded graphite. These materials were selected on the basis of the appropriate properties required by the HTTR reactor design. Industry-wide standards for an acceptance test of graphite materials used as main components of a nuclear reactor had not been established. The acceptance standard for graphite components of the HTTR, therefore, was drafted by JAERI and reviewed by specialists outside JAERI. The acceptance standard consists of the material testing, non-destructive examination such as the ultrasonic and eddy current testings, dimensional and visual inspections and assembly test. Ultrasonic and eddy current testings are applied to graphite logs to detect an internal flaw and to graphite components to detect a surface flaw, respectively. The assembly test is performed at the works, prior to their installation in the reactor pressure vessel, to examine fabricating precision of each component and alignment of piled-up structures. The graphite components of the HTTR had been tested on the basis of the acceptance standard. It was confirmed that the graphite manufacturing process was well controlled and high quality graphite components were provided to the HTTR. All graphite components except for the fuel graphite blocks are to be installed in the reactor pressure vessel of the HTTR in September 1995. The paper describes the construction status of the HTTR focusing on the graphite components. The acceptance test results are also presented in this paper. (author). Figs

  12. ENRAF Series 854 Advanced Technology Gauge (ATG) Acceptance Test Procedure

    International Nuclear Information System (INIS)

    HUBER, J.H.

    1999-01-01

    This procedure provides acceptance testing for Enraf Series 854 level gauges used to monitor levels in Hanford Waste Storage Tanks. The test will verify that the gauge functions according to the manufacturer's instructions and specifications and is properly setup prior to being delivered to the tank farm area. This ATP does not set up the gauge for any specific tank, but is generalized to permit testing the gauge prior to installation package preparation

  13. In situ vitrification large-scale operational acceptance test analysis

    International Nuclear Information System (INIS)

    Buelt, J.L.; Carter, J.G.

    1986-05-01

    A thermal treatment process is currently under study to provide possible enhancement of in-place stabilization of transuranic and chemically contaminated soil sites. The process is known as in situ vitrification (ISV). In situ vitrification is a remedial action process that destroys solid and liquid organic contaminants and incorporates radionuclides into a glass-like material that renders contaminants substantially less mobile and less likely to impact the environment. A large-scale operational acceptance test (LSOAT) was recently completed in which more than 180 t of vitrified soil were produced in each of three adjacent settings. The LSOAT demonstrated that the process conforms to the functional design criteria necessary for the large-scale radioactive test (LSRT) to be conducted following verification of the performance capabilities of the process. The energy requirements and vitrified block size, shape, and mass are sufficiently equivalent to those predicted by the ISV mathematical model to confirm its usefulness as a predictive tool. The LSOAT demonstrated an electrode replacement technique, which can be used if an electrode fails, and techniques have been identified to minimize air oxidation, thereby extending electrode life. A statistical analysis was employed during the LSOAT to identify graphite collars and an insulative surface as successful cold cap subsidence techniques. The LSOAT also showed that even under worst-case conditions, the off-gas system exceeds the flow requirements necessary to maintain a negative pressure on the hood covering the area being vitrified. The retention of simulated radionuclides and chemicals in the soil and off-gas system exceeds requirements so that projected emissions are one to two orders of magnitude below the maximum permissible concentrations of contaminants at the stack

  14. Evidentiary requirements to identify potentially acceptable sites (PAS) in crystalline rock

    International Nuclear Information System (INIS)

    Comella, P.A.; Smith, B.H.

    1985-01-01

    This report contains information on the evidentiary requirements to identify potentially acceptable sites in crystalline rock for waste disposal. Topics addressed include: chronology, key regulatory assumptions, statutory framework for identifying potentially acceptable sites, application of 10 disqualifiers, consideration of favorable and potentially adverse conditions, a composite favorability analysis, and a proposed outline for PAS identification decision document

  15. End-user Acceptance of Online Shopping Sites in India

    OpenAIRE

    Bolar K; Shaw B

    2015-01-01

    Online shopping sites have recently gained momentum in India. Since the ecommerce industry is in infancy state, customer (end user) satisfaction with the online shopping is the prime concern because decreasing customer satisfaction leads to negative electronic word of mouth (eWOM) which is very severe for the business. Through a dataset gathered from 127 online shopping customers in with respect to online shopping sites in India, this study investigates the role of website quality, informatio...

  16. Buffer mass test - Site documentation

    International Nuclear Information System (INIS)

    Pusch, R.

    1983-10-01

    The purpose of this report is to compile test site data that are assumed to be of importance for the interpretation of the Buffer Mass Test. Since this test mainly concerns water uptake and migration processes in the integrated rock/backfill system and the development of temperature fields in this system, the work has been focused on the constitution and hydrology of the rock. The major constitutional rock feature of interest for the BMT is the frequency and distribution of joints and fractures. The development of models for water uptake into the highly compacted bentonite in the heater holes requires a very detailed fracture survey. The present investigation shows that two of the holes (no. 1 and 2) are located in richly fractured rock, while the others are located in fracture-poor to moderately fractured rock. The hydrological conditions of the rock in the BMT area are characterized by water pressures of as much as 100 m water head at a few meters distance from the test site. The average hydraulic conductivity of the rock that confines the BMT tunnel has been estimated at about 10 -10 m/s by Lawrence Laboratory. The actual distribution of the water that enters the tunnel has been estimated by observing the successive moistening after having switched off the ventilation, and this has offered basis of predicting the rate and uniformity of the water uptake in the tunnel backfill. As to the heater holes the detailed fracture patterns and various inflow measurements have yielded a similar basis. The report also gives major data on the rock temperature, gas conditions, mineralogy, rock mechanics, and groundwater chemistry for BMT purposes. (author)

  17. HWVP compliance with the Hanford site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Bromm, R.; Ornelas, J.; Fundingsland, S.; Shah, K.

    1993-01-01

    In order to ensure that the Hanford Waste Vitrification Project (HWVP) will meet solid waste acceptance criteria, a review of the criteria was performed. The primary purpose of the study was to evaluate the modifications that will be required to bring the HWVP into compliance for secondary waste which will be generated during normal operations of the facility. To accomplish this objective, the current HWVP design was evaluated based on the criteria established. Once the non-compliance areas and potentially non-compliance areas were identified, alternative plant design modifications were proposed. This paper summarizes the results and recommendations of that study

  18. Acceptance test report MICON software exhaust fan control modifications; TOPICAL

    International Nuclear Information System (INIS)

    SILVAN, G.R.

    1999-01-01

    This report documents the results the acceptance test HNF-4108 which verifies the MICON program changes for the new automatic transfer switch ATS-2 alarms, the Closed Loop Cooling isolator status, the CB-3 position alarm, the alarms for the new emergency fan damper backup air compressor, and the generator sequencer logic

  19. Automatically generated acceptance test: A software reliability experiment

    Science.gov (United States)

    Protzel, Peter W.

    1988-01-01

    This study presents results of a software reliability experiment investigating the feasibility of a new error detection method. The method can be used as an acceptance test and is solely based on empirical data about the behavior of internal states of a program. The experimental design uses the existing environment of a multi-version experiment previously conducted at the NASA Langley Research Center, in which the launch interceptor problem is used as a model. This allows the controlled experimental investigation of versions with well-known single and multiple faults, and the availability of an oracle permits the determination of the error detection performance of the test. Fault interaction phenomena are observed that have an amplifying effect on the number of error occurrences. Preliminary results indicate that all faults examined so far are detected by the acceptance test. This shows promise for further investigations, and for the employment of this test method on other applications.

  20. Acceptability of HIV self-testing: a systematic literature review.

    Science.gov (United States)

    Krause, Janne; Subklew-Sehume, Friederike; Kenyon, Chris; Colebunders, Robert

    2013-08-08

    The uptake of HIV testing and counselling services remains low in risk groups around the world. Fear of stigmatisation, discrimination and breach of confidentiality results in low service usage among risk groups. HIV self-testing (HST) is a confidential HIV testing option that enables people to find out their status in the privacy of their homes. We evaluated the acceptability of HST and the benefits and challenges linked to the introduction of HST. A literature review was conducted on the acceptability of HST in projects in which HST was offered to study participants. Besides acceptability rates of HST, accuracy rates of self-testing, referral rates of HIV-positive individuals into medical care, disclosure rates and rates of first-time testers were assessed. In addition, the utilisation rate of a telephone hotline for counselling issues and clients` attitudes towards HST were extracted. Eleven studies met the inclusion criteria (HST had been offered effectively to study participants and had been administered by participants themselves) and demonstrated universally high acceptability of HST among study populations. Studies included populations from resource poor settings (Kenya and Malawi) and from high-income countries (USA, Spain and Singapore). The majority of study participants were able to perform HST accurately with no or little support from trained staff. Participants appreciated the confidentiality and privacy but felt that the provision of adequate counselling services was inadequate. The review demonstrates that HST is an acceptable testing alternative for risk groups and can be performed accurately by the majority of self-testers. Clients especially value the privacy and confidentiality of HST. Linkage to counselling as well as to treatment and care services remain major challenges.

  1. PUREX (SAMCONS) uninterruptible power supply (UPS) acceptance test procedure

    International Nuclear Information System (INIS)

    Blackaby, W.B.

    1997-01-01

    This Acceptance Test Procedure for the PUREX Surveillance and Monitoring and Control System (SAMCONS) Uninterruptible Power Supply (UPS) provides for testing and verifying the proper operation of the control panel alarms and trouble functions, the 6roper functioning of the AC inverter, ability of the battery supply to maintain the SAMCONS load for a minimum of two hours , and proper interaction with the SAMCONS Video graphic displays for alarm displays

  2. Effects of Site and Cultivar on Consumer Acceptance of Pomegranate.

    Science.gov (United States)

    Chater, John M; Merhaut, Donald J; Jia, Zhenyu; Arpaia, Mary Lu; Mauk, Peggy A; Preece, John E

    2018-05-01

    Pomegranate (Punica granatum L.) is an important fruit in many cultures. The fruit and juice have risen in popularity as it was discovered that pomegranate has relatively high antioxidant activity compared to most other fruits. In this study, six cultivars were utilized to determine consumer acceptance compared to the industry standard, 'Wonderful,' which comprises 90% to 95% of commercial production in the United States. Fruit were sourced from 2 cultivar field trials, one in inland Riverside, California, and one in coastal Ventura County, California. Cultivars selected for the study included 'Eversweet,' 'Green Globe,' 'Haku Botan,' 'Loffani,' 'Phoenicia,' 'Wonderful,' and 'cv. 857,' an heirloom cultivar from Ventura County, CA, U.S.A. Pomegranate arils were subject to sensory evaluation by 87 untrained consumer panelists in late 2016. Panelists were given pomegranate arils and asked to score the samples using a 9-point Hedonic scale for the following fruit quality traits: aril color, sweetness, tartness, seed hardness, bitterness, and overall desirability. There were significant differences among cultivars for all traits assessed by the sensory panelists. There were differences in acceptance among consumers for 'Wonderful' depending on if it was grown on the coast versus inland, and consumers preferred inland- versus coastal-grown 'Wonderful.' 'Wonderful' pomegranate was associated with cultivars that consumers scored low on desirability for bitterness. Cultivars that scored well in overall desirability compared with 'Wonderful' were 'cv. 857,' 'Eversweet,' 'Green Globe,' and 'Phoenicia.' Consumer sensory panels are important to determine scientifically which cultivars are desired by the public. These panels allowed for the determination of which pomegranate cultivars are liked or disliked by consumers and why. If the pomegranate growers know the most desirable cultivars for consumers, they are more likely to adopt and plant them, thus potentially increasing the

  3. Atomic test site (south Australia)

    International Nuclear Information System (INIS)

    Godman, N.A.; Cousins, Jim; Hamilton, Archie.

    1993-01-01

    The debate, which lasted about half an hour, is reported verbatin. It was prompted by the campaign by the Maralinga people of South Australia to have their traditional lands restored to them. Between 1953 and 1957 the United Kingdom government carried out of atomic tests and several hundred minor trials on the lands. A clean-up programme had taken place in 1967 but further decontamination was needed before the area is safe for traditional aboriginal life and culture. A small area will remain contaminated with plutonium for thousands of years. The cost and who would pay, the Australian or UK government was being negotiated. The UK government's position was that the site is remote, the health risk is slight and the clean-up operation of 1967 was acknowledged as satisfactory by the Australian government. (UK)

  4. Appropriate User Acceptance Criteria For New Social Media Sites

    OpenAIRE

    Mirsat Yeşiltepe

    2016-01-01

    Nowadays social media sites have attracted many of users and they have become the mostly commonly used websites for public. These websites are used by individuals, small and even big organizations for various purposes, such as meeting your old friends, sharing your own experiences, sharing pictures and videos, promoting businesses, sharing knowledge etc. Their popularity is increasing at an increasing rate. User’s needs are endless so there will be some new area for creating...

  5. CCS acceptability: social site characterization and advancing awareness at prospective storage sites in Poland and Scotland

    International Nuclear Information System (INIS)

    Brunsting, Suzanne; Mastop, Jessanne; Kaiser, Marta; Zimmer, Rene; Shackley, Simon; Mabon, Leslie; Howell, Rhys

    2015-01-01

    This paper summarizes the work on the social dimension conducted within the EU FP7 SiteChar project. The most important aim of the research was to advance public awareness and draw lessons for successful public engagement activities when developing a CO 2 storage permit application. To this end, social site characterization (e.g. representative surveys) and public participation activities (focus conference) were conducted at two prospective Carbon Capture and Storage (CCS) sites: an onshore site in Poland and an offshore site in Scotland. The research consisted of four steps over a time period of 1.5 year, from early 2011 to mid-2012. The first step consisted of four related qualitative and quantitative research activities to provide a social characterization of the areas: desk research, stakeholder interviews, media analyses, and a survey among representative samples of the local community. The aim was to identify: - stakeholders or interested parties; - factors that may drive their perceptions of and attitudes towards CCS. Results were used to as input for the second step, in which a new format for public engagement named 'focus conferences' was tested at both sites involving a small sample of the local community. The third step consisted of making available generic as well as site-specific information to the general and local public, by: - setting up a bilingual set of information pages on the project web site suitable for a lay audience; - organizing information meetings at both sites that were open to all who took interest. The fourth step consisted of a second survey among a new representative sample of the local community. The survey was largely identical to the survey in step 1 to enable the monitoring of changes in awareness, knowledge and opinions over time. Results provide insight in the way local CCS plans may be perceived by the local stakeholders, how this can be reliably assessed at early stage without raising unnecessary concerns, and how

  6. Surface moisture measurement system hardware acceptance test report

    Energy Technology Data Exchange (ETDEWEB)

    Ritter, G.A., Westinghouse Hanford

    1996-05-28

    This document summarizes the results of the hardware acceptance test for the Surface Moisture Measurement System (SMMS). This test verified that the mechanical and electrical features of the SMMS functioned as designed and that the unit is ready for field service. The bulk of hardware testing was performed at the 306E Facility in the 300 Area and the Fuels and Materials Examination Facility in the 400 Area. The SMMS was developed primarily in support of Tank Waste Remediation System (TWRS) Safety Programs for moisture measurement in organic and ferrocyanide watch list tanks.

  7. MCO combustible gas management leak test acceptance criteria; TOPICAL

    International Nuclear Information System (INIS)

    SHERRELL, D.L.

    1999-01-01

    Existing leak test acceptance criteria for mechanically sealed and weld sealed multi-canister overpacks (MCO) were evaluated to ensure that MCOs can be handled and stored in stagnant air without compromising the Spent Nuclear Fuel Project's overall strategy to prevent accumulation of combustible gas mixtures within MCO's or within their surroundings. The document concludes that the integrated leak test acceptance criteria for mechanically sealed and weld sealed MCOs (1 x 10(sup -5) std cc/sec and 1 x 10(sup -7) std cc/sec, respectively) are adequate to meet all current and foreseeable needs of the project, including capability to demonstrate compliance with the NFPA 60 Paragraph 3-3 requirement to maintain hydrogen concentrations[within the air atmosphere CSB tubes] t or below 1 vol% (i.e., at or below 25% of the LFL)

  8. Project W-049H Collection System Acceptance Test

    International Nuclear Information System (INIS)

    Buckles, D.I.

    1994-01-01

    The Acceptance Test Procedure (ATP) Program for Project W-049H covers the following activities: Disposal system, Collection system, Instrumentation and control system. Each activity has its own ATP. The purpose of the ATPs is to verify that the systems have been constructed in accordance with the construction documents and to demonstrate that the systems function as required by the Project criteria. This ATP has been prepared to demonstrate that the Collection System Instrumentation functions as required by project criteria

  9. Acceptance Rate of HIV Testing among Women Seeking Induced ...

    African Journals Online (AJOL)

    A l\\'aide d\\'un questionnaire semi-structuré et auto-administré, nous avons interviewé 1051 femmes qui recherchaient l\\'avortement provoqué dans quatre cliniques selectionnées au hazard à Benin City entre janvier et septembre 2002. Les échantillons sanguins de celles qui ont accepté le test du VIH ont été collectés et ont ...

  10. Acceptance test plan for the Waste Information Control System

    International Nuclear Information System (INIS)

    Flynn, D.F.

    1994-01-01

    This document describes the acceptance test plan for the WICS system. The Westinghouse Hanford Company (WHC) Hazardous Material Control Group (HMC) of the 222-S Laboratory has requested the development of a system to help resolve many of the difficulties associated with tracking and data collection of containers and drums of waste. This system has been identified as Waste Information and Control System (WICS). The request for developing and implementing WICS has been made to the Automation and Simulation Engineering Group (ASE)

  11. Nevada Test Site Wetlands Assessment

    Energy Technology Data Exchange (ETDEWEB)

    D. J. Hansen

    1997-05-01

    This report identifies 16 Nevada Test Site (NTS) natural water sources that may be classified by the U.S. Army Corps of Engineers (USACE) as jurisdictional wetlands and identifies eight water sources that may be classified as waters of the United States. These water sources are rare, localized habitats on the NTS that are important to regional wildlife and to isolated populations of water tolerant plants and aquatic organisms. No field investigations on the NTS have been conducted in the past to identify those natural water sources which would be protected as rare habitats and which may fall under regulatory authority of the Clean Water Act (CWA) of 1997. This report identifies and summarizes previous studies of NTS natural water sources, and identifies the current DOE management practices related to the protection of NTS wetlands. This report also presents management goals specific for NTS wetlands that incorporate the intent of existing wetlands legislation, the principles of ecosystem management, and the interests of regional land managers and other stakeholders.

  12. 242A Distributed Control System Year 2000 Acceptance Test Report

    Energy Technology Data Exchange (ETDEWEB)

    TEATS, M.C.

    1999-08-31

    This report documents acceptance test results for the 242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. This report documents the test results obtained by acceptance testing as directed by procedure HNF-2695. This verification procedure will document the initial testing and evaluation of the potential 242-A Distributed Control System (DCS) operating difficulties across the year 2000 boundary and the calendar adjustments needed for the leap year. Baseline system performance data will be recorded using current, as-is operating system software. Data will also be collected for operating system software that has been modified to correct year 2000 problems. This verification procedure is intended to be generic such that it may be performed on any D/3{trademark} (GSE Process Solutions, Inc.) distributed control system that runs with the VMSTM (Digital Equipment Corporation) operating system. This test may be run on simulation or production systems depending upon facility status. On production systems, DCS outages will occur nine times throughout performance of the test. These outages are expected to last about 10 minutes each.

  13. Acceptance test report for portable exhauster POR-008/Skid F

    International Nuclear Information System (INIS)

    Kriskovich, J.R.

    1998-01-01

    Portable Exhauster POR-008 was procured via HNF-0490, Specification for a Portable Exhausted System for Waste Tank Ventilation. Prior to taking ownership, acceptance testing was performed at the vendors. However at the conclusion of testing a number of issues remained that required resolution before the exhausters could be used by Project W-320. The purpose of acceptance testing documented by this report was to demonstrate compliance of the exhausters with the performance criteria established within HNF-O49O, Rev. 1 following a repair and upgrade effort at Hanford. In addition, data obtained during this testing is required for the resolution of outstanding Non-conformance Reports (NCR), and finally, to demonstrate the functionality of the associated software for the pressure control and high vacuum exhauster operating modes provided for by W-320. Additional testing not required by the ATP was also performed to assist in the disposition and close out of receiving inspection report and for application design information (system curve). Results of this testing are also captured within this document

  14. Acceptance test report for 241-AW process air system

    International Nuclear Information System (INIS)

    Kostelnik, A.J.

    1994-01-01

    The acceptance test procedure (ATP) for the compressed air system at building 241-AW-273 was completed on March 11, 1993. The system was upgraded to provide a reliable source of compressed air to the tank farm. The upgrade included the demolition of the existing air compressor and associated piping, as well as the installation of a new air compressor with a closed loop cooling system. A compressed air cross-tie was added to allow the process air compressor to function as a back-up to the existing instrument air compressor. The purpose of the ATP was to achieve three primary objectives: verify system upgrade in accordance with the design media; provide functional test of system components and controls; and prepare the system for the Operational Test. The ATP was successfully completed with thirteen exceptions, which were resolved prior to completing the acceptance test. The repaired exceptions had no impact to safety or the environment and are briefly summarized. Testing ensured that the system was installed per design, that its components function as required and that it is ready for operational testing and subsequent turnover to operations

  15. 242A Distributed Control System Year 2000 Acceptance Test Report

    International Nuclear Information System (INIS)

    TEATS, M.C.

    1999-01-01

    This report documents acceptance test results for the 242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. This report documents the test results obtained by acceptance testing as directed by procedure HNF-2695. This verification procedure will document the initial testing and evaluation of the potential 242-A Distributed Control System (DCS) operating difficulties across the year 2000 boundary and the calendar adjustments needed for the leap year. Baseline system performance data will be recorded using current, as-is operating system software. Data will also be collected for operating system software that has been modified to correct year 2000 problems. This verification procedure is intended to be generic such that it may be performed on any D/3(trademark) (GSE Process Solutions, Inc.) distributed control system that runs with the VMSTM (Digital Equipment Corporation) operating system. This test may be run on simulation or production systems depending upon facility status. On production systems, DCS outages will occur nine times throughout performance of the test. These outages are expected to last about 10 minutes each

  16. Project W-049H collection system Acceptance Test Procedure

    International Nuclear Information System (INIS)

    Carrigan, M.C.

    1994-01-01

    The purpose of this Acceptance Test Procedure (ATP) for the Project W-049H, Treated Effluent Disposal Facility, is to verify that the collection system equipment installed as Pump Station No. 1 (225-W) and Pump Station No. 2 (225-E) have been installed in accordance with the design documents and function as required by the project criteria. This will be a wet test with potable water being introduced into the pump pits to test for leakage. Potable water will also be employed in the testing of the pumps and related mechanical equipment. All Instrument and Control equipment related to the pump stations will be checked electronically with simulated inputs/outputs when actual input/output signals are unavailable. Water from Pump Station 1 will be moved through the TEDF piping system and discharged into the disposal ponds. This will check the proper function of the air/vac valves not tested during construction, and the automated samplers

  17. Dissolution test for low-activity waste product acceptance

    International Nuclear Information System (INIS)

    Ebert, W. L.

    1998-01-01

    We have measured the mean and standard deviation of the solution concentrations of B, Na, and Si attained in replicate dissolution tests conducted at temperatures of 20, 40, and 70 C, for durations of 3 and 7 days, and at glass/water mass ratios of 1:10 and 1:1. These and other tests were conducted to evaluate the adequacy of the test methods specified in privatization contracts and to develop a data base that can be used to evaluate the reliability of reported results for tests performed on the waste products. Tests were conducted with a glass that we formulated to be similar to low-activity waste products that will be produced during the remediation of Hanford tank wastes. Statistical analyses indicated that, while the mean concentrations of B, Na, and Si were affected by the values of test parameters, the standard deviation of replicate tests was not. The precision of the tests was determined primarily by uncertainties in the analysis of the test solutions. Replicate measurements of other glass properties that must be reported for Hanford low-activity waste products were measured to evaluate the possible adoption of the glass used in these tests as a standard test material for the product acceptance process

  18. Review of the Factory Acceptance Tests and Cold Tests of the W7-X Superconducting Magnets

    International Nuclear Information System (INIS)

    Ehmler, H.; Baldzuhn, J.; Genini, L.

    2006-01-01

    The W7-X magnet system consists of 50 non-planar coils of five different types and 20 planar coils of two different types. Factory acceptance tests of the non-planar coils are carried out at the manufacturer site of Babcock-Noell, Germany, and for the planar coils at Tesla Engineering, UK. They consist of electrical insulation checks, mass flow measurements and leak tests. In the test facility of CEA Saclay, France, each coil is cooled down to ∼ 6 K and operated at nominal current. At least one coil of each type is quenched by increasing the inlet temperature. The characteristic parameters of the quench tests (temperature, pressure, speed of normal-conducting zone, etc.) will be presented. Coils of the same type show a uniform behavior. The occurrences of leaks during cool-down on planar coils revealed quality problems with aluminum welds and stress corrosion of stainless steel tubes at the soldered connections with copper heat sinks. AC tests (impulse and impedance tests) were applied to detect short circuits during the fabrication of the winding packs. High voltage DC tests under vacuum and low gas pressure (Paschen-minimum conditions) revealed electrical insulation defects, which had not been found using standard high-voltage tests. These were mainly due to voids and cavities present in the winding pack after vacuum impregnation, insufficient glass-epoxy wrapped insulation and inappropriate design of the Kapton insulated quench detection cables. The mass flow measurements of the superconductor showed that the deviation between individual double layers of the coils is within acceptable limits. Two winding packs were given up by the supplier because of a superconductor blockage with resin and a short circuited winding, respectively. All other quality issues could be resolved by repair or changes in the components. The coil instrumentation with temperature sensors seems to be adequate. The strain gauges need improvements in temperature compensation and gluing

  19. Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

    Energy Technology Data Exchange (ETDEWEB)

    Carilli, Jhon T. [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States); Krenzien, Susan K. [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)

    2013-07-01

    The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

  20. Acceptance test report: Field test of mixer pump for 241-AN-107 caustic addition project

    International Nuclear Information System (INIS)

    Leshikar, G.A.

    1997-01-01

    The field acceptance test of a 75 HP mixer pump (Hazleton serial number N-20801) installed in Tank 241-AN-107 was conducted from October 1995 thru February 1996. The objectives defined in the acceptance test were successfully met, with two exceptions recorded. The acceptance test encompassed field verification of mixer pump turntable rotation set-up and operation, verification that the pump instrumentation functions within established limits, facilitation of baseline data collection from the mixer pump mounted ultrasonic instrumentation, verification of mixer pump water flush system operation and validation of a procedure for its operation, and several brief test runs (bump) of the mixer pump

  1. Ship Systems Survivability Test Site

    Data.gov (United States)

    Federal Laboratory Consortium — Area for testing survivability of shipboard systems to include electrical, communications, and fire suppression. Multipurpose test range for supporting gun firing,...

  2. Acceptance test report for project C-157 ''T-Plant electrical upgrade''

    International Nuclear Information System (INIS)

    Jeppson, L.A.

    1997-01-01

    This Acceptance Test Report (ATR) documents for record purposes the field results, acceptance, and approvals of the completed acceptance test per WHC-SD-Cl57-ATP-001, Rev. 0, ''Acceptance Test Proceedure for Project C-157 'T Plant Electrical Upgrade''' The test was completed and approved without any problems or exceptions

  3. Acceptance test report for project C-157 ``T-Plant electrical upgrade``

    Energy Technology Data Exchange (ETDEWEB)

    Jeppson, L.A.

    1997-08-05

    This Acceptance Test Report (ATR) documents for record purposes the field results, acceptance, and approvals of the completed acceptance test per WHC-SD-Cl57-ATP-001, Rev. 0, ``Acceptance Test Proceedure for Project C-157 `T Plant Electrical Upgrade``` The test was completed and approved without any problems or exceptions.

  4. Acceptance test procedure for SY Tank Farm replacement exhauster unit

    Energy Technology Data Exchange (ETDEWEB)

    Becken, G.W.

    1994-12-16

    The proper functioning of a new 241-SY Tank Farm replacement exhauster will be acceptance tested, to establish operability and to provide an operational baseline for the equipment. During this test, a verification of all of the alarm and control circuits associated with the exhaust, which provide operating controls and/or signals to local and remote alarm/annunciator panels, shall be performed. Test signals for sensors that provide alarms, warnings, and/or interlocks will be applied to verify that alarm, warning, and interlock setpoints are correct. Alarm and warning lights, controls, and local and remote readouts for the exhauster will be verified to be adequate for proper operation of the exhauster. Testing per this procedure shall be conducted in two phases. The first phase of testing, to verify alarm, warning, and interlock setpoints primarily, will be performed in the MO-566 Fab Shop. The second phase of testing, to verify proper operation and acceptable interface with other tank farm systems, will be conducted after the exhauster and all associated support and monitoring equipment have been installed in the SY Tank Farm. The exhauster, which is mounted on a skid and which will eventually be located in the SY tank farm, receives input signals from a variety of sensors mounted on the skid and associated equipment. These sensors provide information such as: exhauster system inlet vacuum pressure; prefilter and HEPA filter differential pressures; exhaust stack sampler status; exhaust fan status; system status (running/shut down); and radiation monitoring systems status. The output of these sensors is transmitted to the exhauster annunciator panel where the signals are displayed and monitored for out-of-specification conditions.

  5. Acceptance testing and quality assurance of Simulix evolution radiotherapy simulator

    International Nuclear Information System (INIS)

    Sinha, Ashutosh; Singh, Navin; Gurjar, Om Prakash; Bagdare, Priyusha

    2015-01-01

    The success of radiotherapy depends on precise treatment simulation and proper patient positioning. The simulator is a conventional radiographic and fluoroscopic system which emulates the geometrical positions of radiotherapy treatment unit. Hence, the acceptance tests and quality assurance (QA) of the simulator are important prior to its commissioning for the safe and precise clinical use. The verification of mechanical and optical readouts, field size, isocenter, optical and radiation field congruence were performed. The X-ray beam parameters were tested for kVp, mAs and consistency of radiation output. The flat panel detector performance was checked with respect to resolution, low contrast sensitivity (LCS), automatic dose rate control (ADRC), and gray image resolution (GIR). Gantry, table, and imaging system collision possibility was checked. Radiation survey around the room was also performed. The field size test for digital readout and on graph paper, the results of isocenter checkup for rotation of gantry, collimator, and couch, and the deviations observed in auto stop for various movements were found within the tolerance limits. Optical field and radiation field was found congruent. All the lasers were found aligned with the established isocenter. Maximum deviation for set and measured kV was found to be 3% in fluoro mode. The maximum deviation observed in mAs was 1.5% in 3-point as well as in 2-point film exposed mode. The X-ray output was found consistent. The results of tests for resolution, LCS, ADRC, and GIR of the flat panel detector were within tolerance limits. All the six safety interlocks were found working. Radiation level around the room was found within the acceptable limits. All the tests carried out were found within the tolerance limits. The data which has been taken in this study will provide basic support to the routine QA of the simulator. (author)

  6. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid N

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5489. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''N''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

  7. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid M

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5073. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''M''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

  8. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid L

    Energy Technology Data Exchange (ETDEWEB)

    KOCH, M.R.

    1999-11-09

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5055. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''L''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document.

  9. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid L

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5055. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''L''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

  10. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid M

    Energy Technology Data Exchange (ETDEWEB)

    KOCH, M.R.

    1999-12-13

    This is a Test Report for Acceptance Test Procedure (ATP) RPP-5073. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''M''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document.

  11. Acceptance test procedure, 241-SY-101 Flexible Receiver System, Phase III testing

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1994-01-01

    This Acceptance Test Procedure is for the 241-SY-101 Flexible Receiver System, Phase III Testing. This procedure will test the sealing integrity of the Flexible Receiver System to ensure that release of waste and aerosols will be minimized during the removal of the test mixer pump from tank SY-101

  12. Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 1 testing

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1995-01-01

    This document summarizes the results of the Phase 1 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). This acceptance test consisted of a pressure-decay/leak test of the containment bag to verify that the seams along the length of the bag had been adequately sealed. The sealing integrity of the FRS must be verified to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at Lancs Industries in Kirkland, Washington on January 17, 1995. The bag temperature-compensated pressure loss of 575 Pa was below the acceptance criteria of 625 Pa and the test results were therefore found to be acceptable. The bag manufacturer estimates that 80--90% of the pressure loss is attributed to leakage around the bag inflation valve where the pressure gage was connected. A leak detector was applied over the entire bag during the pre-tests and no leakage was found. Furthermore, the leak rate corresponding to this pressure loss is very small when compared to the acceptable leak rate of the completely assembled FRS. The sealing integrity of the assembled FRS is verified in Phase 3 testing

  13. Acceptance of HIV testing among women attending antenatal care in south-western Uganda: risk factors and reasons for test refusal.

    Science.gov (United States)

    Dahl, V; Mellhammar, L; Bajunirwe, F; Björkman, P

    2008-07-01

    A problem commonly encountered in programs for prevention of mother-to-child-transmission (PMTCT) of HIV in sub-Saharan Africa is low rates of HIV test acceptance among pregnant women. In this study, we examined risk factors and reasons for HIV test refusal among 432 women attending three antenatal care clinics offering PMTCT in urban and semi-urban parts of the Mbarara district, Uganda. Structured interviews were performed following pre-test counselling. Three-hundred-eighty women were included in the study, 323 (85%) of whom accepted HIV testing. In multivariate analysis, testing site (Site A: OR = 1.0; Site B: OR = 3.08; 95%CI: 1.12-8.46; Site C: OR = 5.93; 95%CI: 2.94-11.98), age between 30 and 34 years (refusal. Testing sites operating for longer durations had higher rates of acceptance. The most common reasons claimed for test refusal were: lack of access to antiretroviral therapy (ART) for HIV-infected women (88%; n=57), a need to discuss with partner before decision (82%; n=57) and fear of partner's reaction (54%; n=57). Comparison with previous periods showed that the acceptance rate increased with the duration of the program. Our study identified risk factors for HIV test refusal among pregnant women in Uganda and common reasons for not accepting testing. These findings may suggest modifications and improvements in the performance of HIV testing in this and similar populations.

  14. Environmentally acceptable endpoints for PAHs at a manufactured gas plant site

    Energy Technology Data Exchange (ETDEWEB)

    Stroo, H.F.; Jensen, R.; Loehr, R.C.; Nakles, D.V.; Fairbrother, A.; Liban, C.B. [ThermoRetec Corp., Carson, CA (USA)

    2000-09-01

    Samples from a former manufactured gas plant (MGP) site in Santa Barbara, CA were tested to evaluate the environmentally acceptable endpoints (EAE) process for setting risk-based cleanup criteria. The research was part of an ongoing effort to develop and demonstrate a protocol for assessing risk-based criteria for MGP sites that incorporates the availability of polycyclic aromatic hydrocarbons (PAHs). Six soil samples were subjected to a battery of physical and biological tests that focused on determining the 'availability' of the soil-bound contaminants to groundwater, ecological receptors, and human receptors. Results demonstrated that sorption to soil, matrix effects, aging, and treatment can significantly reduce chemical availability. Including these reduced availability results in risk assessment calculations yielded environmentally protective cleanup levels almost 3-10 times greater than levels derived using California default risk assessment assumptions. Using an EAE-based approach for MGP soils, especially those containing lampblack, could provide more realistic risk assessment. 23 refs., 6 tabs.

  15. Acceptance Test Report for Fourth-Generation Hanford Corrosion Monitoring Cabinet

    International Nuclear Information System (INIS)

    NORMAN, E.C.

    2000-01-01

    This Acceptance Test Plan (ATP) will document the satisfactory operation of the third-generation corrosion monitoring cabinet (Hiline Engineering Part No.0004-CHM-072-C01). This ATP will be performed by the manufacturer of the cabinet prior to delivery to the site. The objective of this procedure is to demonstrate and document the acceptance of the corrosion monitoring cabinet. The test will consist of a continuity test of the cabinet wiring from the end of cable to be connected to corrosion probe, through the appropriate intrinsic safety barriers and out to the 15 pin D-shell connectors to be connected to the corrosion monitoring instrument. Additional testing will be performed using a constant current and voltage source provided by the corrosion monitoring hardware manufacturer to verify proper operation of corrosion monitoring instrumentation

  16. Grimsel Test Site: heat test, final report

    International Nuclear Information System (INIS)

    Schneefuss, J.; Glaess, F.; Gommlich, G.; Schmidt, M.

    1989-05-01

    The Swiss concept for the storage of radioactive waste consists in placing it in compact, dense rock formations. An experiment 'Heat Test' carried out by the 'Gesellschaft fuer Strahlen- und Umweltforschung' in Nagra's Grimsel rock laboratory simulated the heat production of stored radioactive waste. The aim was to evaluate processes for the demonstration of the suitability of a final repository for heat-producing radioactive waste in cristalline rock, to investigate the thermic, mechanic and hydraulic reactions to an artificial heat source, and to develop corresponding calculating models. The duration of the tests was about 3 years. In this report the measured thermic, mechanic and hydraulic reactions are documented and discussed in detail. A simple, rotation symmetrical FEM-model was used for the preparatory and experiment-accompanying modelling of the thermomechanical conditions in the heat test. The test showed that suitable measuring methods for the surveillance of the geomechanics of a final repository are available and that the reactions of the crystalline host rock to the heat source remain locally limited and can be modelled with relatively small effort. 29 refs., 33 figs., 10 tabs

  17. Controlled Archaeological Test Site (CATS) Facility

    Data.gov (United States)

    Federal Laboratory Consortium — CATS facility is at the Construction Engineering Research Laboratory (CERL), Champaign, IL. This 1-acre test site includes a variety of subsurface features carefully...

  18. 78 FR 38411 - Vogtle Electric Generating Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria

    Science.gov (United States)

    2013-06-26

    ... Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests...

  19. Acceptance test procedure for Project W-049H

    International Nuclear Information System (INIS)

    Buckles, D.I.

    1994-01-01

    The Acceptance Test Procedure (ATP) program for Project W-049H (200 Area Treated Effluent Disposal Facility [TEDF]) covers three activities as follows: (1) Disposal System; (2) Collection System; and (3) Instrumentation and Control System. Each activity has its own ATP. The purpose of the ATPs is to reverify that the systems have been constructed in accordance with the construction documents and to demonstrate that the systems function as required by the Project criteria. The Disposal System ATP covers the testing of the following: disposal line flowmeters, room air temperatures in the Disposal Station Sampling Building, effluent valves and position indicators, disposal pond level monitors, automated sampler, pressure relief valves, and overflow diversion sluice gates. The Collection System ATP covers the testing of the two pump stations and all equipment installed therein. The Instrumentation and Control (I and C) ATP covers the testing of the entire TEDF I and C system. This includes 3 OCS units, modem, and GPLI cabinets in the ETC control room; 2 pump stations; disposal station sampling building; and all LCUs installed in the field

  20. Loss on Ignition Furnace Acceptance and Operability Test Procedure

    International Nuclear Information System (INIS)

    JOHNSTON, D.C.

    2000-01-01

    The purpose of this Acceptance Test Procedure and Operability Test Procedure (ATP/OTP)is to verify the operability of newly installed Loss on Ignition (LOI) equipment, including a model 1608FL CMTM Furnace, a dessicator, and balance. The operability of the furnace will be verified. The arrangement of the equipment placed in Glovebox 157-3/4 to perform LOI testing on samples supplied from the Thermal Stabilization line will be verified. In addition to verifying proper operation of the furnace, this ATP/OTP will also verify the air flow through the filters, verify a damper setting to establish and maintain the required differential pressure between the glovebox and the room pressure, and test the integrity of the newly installed HEPA filter. In order to provide objective evidence of proper performance of the furnace, the furnace must heat 15 crucibles, mounted on a crucible rack, to 1000 C, according to a program entered into the furnace controller located outside the glovebox. The glovebox differential pressure will be set to provide the 0.5 to 2.0 inches of water (gauge) negative pressure inside the glovebox with an expected airflow of 100 to 125 cubic feet per minute (cfm) through the inlet filter. The glovebox inlet G1 filter will be flow tested to ensure the integrity of the filter connections and the efficiency of the filter medium. The newly installed windows and glovebox extension, as well as all disturbed joints, will be sonically tested via ultra probe to verify no leaks are present. The procedure for DOS testing of the filter is found in Appendix A

  1. Loss on Ignition Furnace Acceptance and Operability Test Procedure

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSON, D.C.

    2000-06-01

    The purpose of this Acceptance Test Procedure and Operability Test Procedure (ATP/OTP)is to verify the operability of newly installed LOI equipment, including a model 1608FL CM{trademark} Furnace, a dessicator, and balance. The operability of the furnace will be verified. The arrangement of the equipment placed in Glovebox 157-3/4 to perform Loss on Ignition (LOI) testing on samples supplied from the Thermal Stabilization line will be verified. In addition to verifying proper operation of the furnace, this ATP/OTP will also verify the air flow through the filters, verify a damper setting to establish and maintain the required differential pressure between the glovebox and the room pressure, and test the integrity of the newly installed HEPA filter. In order to provide objective evidence of proper performance of the furnace, the furnace must heat 15 crucibles, mounted on a crucible rack, to 1000 C, according to a program entered into the furnace controller located outside the glovebox. The glovebox differential pressure will be set to provide the 0.5 to 2.0 inches of water (gauge) negative pressure inside the glovebox with an airflow of 100 to 125 cubic feet per minute (cfm) through the inlet filter. The glovebox inlet Glfilter will he flow tested to ensure the integrity of the filter connections and the efficiency of the filter medium. The newly installed windows and glovebox extension, as well as all disturbed joints, will be sonically tested via ultra probe to verify no leaks are present. The procedure for DOS testing of the filter is found in Appendix A.

  2. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid ''P''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Report (ATR) provides the test results for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''P''. The ATR summaries the results and provides a copy of the ATP and inspections in the Appendix

  3. Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid Q

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Report (ATR) provides the test results for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''Q''. The ATR summaries the results and provides a copy of the ATP and inspections in the Appendix

  4. Test marketing and consumer acceptance of irradiated meat products

    International Nuclear Information System (INIS)

    Xu Zhicheng; Feng Zhixiong; Jiang Peizhen

    2001-01-01

    This study consists of two parts: irradiation processing of cooked meat and irradiation preservation of prepackaged chilled fresh cut meats. Irradiation of prepackaged pickled meat products dipped in grains stillage at a dose 6-8 kGy eliminated common food-borne microorganisms, such as E. Coli and other microbial pathogens and extended the shelf life of the product to 10 days at 5 deg. C. Test marketing of 40,000 bags (about 10,000 kg) of the product in more than 100 supermarkets in the city of Shanghai showed no untoward problem with consumer acceptance. Irradiation of prepackaged chilled fresh cut pork at a dose 3 kGy led to inactivation of microbial pathogens and parasites with a concomitant reduction in numbers of common spoilage microorganisms and extension of shelf life of the product for 30 days at 5 deg. C. The cost benefit and marketing applications were evaluated. (author)

  5. Colloid research for the Nevada Test Site

    International Nuclear Information System (INIS)

    Bryant, E.A.

    1992-05-01

    Research is needed to understand the role of particulates in the migration of radionuclides away from the sites of nuclear tests at the Nevada Test Site. The process of testing itself may produce a reservoir of particles to serve as vectors for the transport of long-lived radionuclides in groundwater. Exploratory experiments indicate the presence of numerous particulates in the vicinity of the Cambric test but a much lower loading in a nearby well that has been pumped continuously for 15 years. Recent groundwater colloid research is briefly reviewed to identify sampling and characterization methods that may be applicable at the Nevada Test Site

  6. Nevada Test Site Environmental Report 2004

    International Nuclear Information System (INIS)

    BECHTEL NEVADA

    2005-01-01

    The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders

  7. Nevada Test Site Environmental Report 2005, Attachment A - Site Description

    International Nuclear Information System (INIS)

    Cathy A. Wills

    2006-01-01

    This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report

  8. Nevada Test Site Environmental Report 2005, Attachment A - Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2006-10-01

    This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  9. Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 3 testing

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1995-01-01

    This document summarizes the results of the phase 3 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The purpose of this acceptance test is to verify the sealing integrity of the FRS to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at the 306E Facility in the 300 area from January 10, 1995 to January 17, 1995. The Phase 3 test consisted of two parts. Part one was a water leak test of the seal between the blast shield and mock load distribution frame (LDF) to ensure that significant contamination of the pump pit and waste interaction with the aluminum impact-limiting material under the LDF are prevented during the pump removal operation. The second part of this acceptance test was an air leak test of the assembled flexible receiver system. The purpose of this test was to verify that the release of hazardous aerosols will be minimized if the tank dome pressure becomes slightly positive during the decontamination of the mixer pump

  10. Biological and chemical tests of contaminated soils to determine bioavailability and environmentally acceptable endpoints (EAE)

    International Nuclear Information System (INIS)

    Montgomery, C.R.; Menzie, C.A.; Pauwells, S.J.

    1995-01-01

    The understanding of the concept of bioavailability of soil contaminants to receptors and its use in supporting the development of EAE is growing but still incomplete. Nonetheless, there is increased awareness of the importance of such data to determine acceptable cleanup levels and achieve timely site closures. This presentation discusses a framework for biological and chemical testing of contaminated soils developed as part of a Gas Research Institute (GRI) project entitled ''Environmentally Acceptable Endpoints in Soil Using a Risk Based Approach to Contaminated Site Management Based on Bioavailability of Chemicals in Soil.'' The presentation reviews the GRI program, and summarizes the findings of the biological and chemical testing section published in the GRI report. The three primary components of the presentation are: (1) defining the concept of bioavailability within the existing risk assessment paradigm, (2) assessing the usefulness of the existing tests to measure bioavailability and test frameworks used to interpret these measurements, and (3) suggesting how a small selection of relevant tests could be incorporated into a flexible testing scheme for soils to address this issue

  11. Nevada Test Site Environmental Report 2007 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills

    2008-09-01

    This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  12. Threshold Assessment: Definition of Acceptable Sites as Part of Site Selection for the Japanese HLW Program

    International Nuclear Information System (INIS)

    McKenna, S.A.; Wakasugi, Keiichiro; Webb, E.K.; Makino, Hitoshi; Ishihara, Yoshinao; Ijiri, Yuji; Sawada, Atsushi; Baba, Tomoko; Ishiguro, Katsuhiko; Umeki, Hiroyuki

    2000-01-01

    For the last ten years, the Japanese High-Level Nuclear Waste (HLW) repository program has focused on assessing the feasibility of a basic repository concept, which resulted in the recently published H12 Report. As Japan enters the implementation phase, a new organization must identify, screen and choose potential repository sites. Thus, a rapid mechanism for determining the likelihood of site suitability is critical. The threshold approach, described here, is a simple mechanism for defining the likelihood that a site is suitable given estimates of several critical parameters. We rely on the results of a companion paper, which described a probabilistic performance assessment simulation of the HLW reference case in the H12 report. The most critical two or three input parameters are plotted against each other and treated as spatial variables. Geostatistics is used to interpret the spatial correlation, which in turn is used to simulate multiple realizations of the parameter value maps. By combining an array of realizations, we can look at the probability that a given site, as represented by estimates of this combination of parameters, would be good host for a repository site

  13. 78 FR 53483 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

    Science.gov (United States)

    2013-08-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00025; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

  14. 78 FR 53484 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4

    Science.gov (United States)

    2013-08-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

  15. 78 FR 65007 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

    Science.gov (United States)

    2013-10-30

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion...

  16. ISOLOK VALVE ACCEPTANCE TESTING FOR DWPF SME SAMPLING PROCESS

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, T.; Hera, K.; Coleman, C.; Jones, M.; Wiedenman, B.

    2011-12-05

    Evaluation of the Defense Waste Processing Facility (DWPF) Chemical Process Cell (CPC) cycle time identified several opportunities to improve the CPC processing time. Of the opportunities, a focus area related to optimizing the equipment and efficiency of the sample turnaround time for DWPF Analytical Laboratory was identified. The Mechanical Systems & Custom Equipment Development (MS&CED) Section of the Savannah River National Laboratory (SRNL) evaluated the possibility of using an Isolok{reg_sign} sampling valve as an alternative to the Hydragard{reg_sign} valve for taking process samples. Previous viability testing was conducted with favorable results using the Isolok sampler and reported in SRNL-STI-2010-00749 (1). This task has the potential to improve operability, reduce maintenance time and decrease CPC cycle time. This report summarizes the results from acceptance testing which was requested in Task Technical Request (TTR) HLW-DWPF-TTR-2010-0036 (2) and which was conducted as outlined in Task Technical and Quality Assurance Plan (TTQAP) SRNL-RP-2011-00145 (3). The Isolok to be tested is the same model which was tested, qualified, and installed in the Sludge Receipt Adjustment Tank (SRAT) sample system. RW-0333P QA requirements apply to this task. This task was to qualify the Isolok sampler for use in the DWPF Slurry Mix Evaporator (SME) sampling process. The Hydragard, which is the current baseline sampling method, was used for comparison to the Isolok sampling data. The Isolok sampler is an air powered grab sampler used to 'pull' a sample volume from a process line. The operation of the sampler is shown in Figure 1. The image on the left shows the Isolok's spool extended into the process line and the image on the right shows the sampler retracted and then dispensing the liquid into the sampling container. To determine tank homogeneity, a Coliwasa sampler was used to grab samples at a high and low location within the mixing tank. Data from

  17. Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

    International Nuclear Information System (INIS)

    Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

    1979-01-01

    The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

  18. Defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System

    International Nuclear Information System (INIS)

    Hudson, J.D.

    1996-04-01

    This document provides a methodology for defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System (RCSTS). This methodology includes characterization, transport analysis, and control. A framework is described for each of these functions. A tool was developed for performing the calculations associated with the transport analysis. This tool, a worksheet that is available in formats acceptable for a variety of PC spreadsheet programs, enables a comparison of the pressure required to transport a given slurry at a rate that particulate suspension is maintained to the pressure drop available from the RCSTS

  19. Evaluation of the Acceptability of Potential Depleted Uranium Hexafluoride Conversion Products at the Envirocare Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    Croff, A.G.

    2001-01-11

    The purpose of this report is to review and document the capability of potential products of depleted UF{sub 6} conversion to meet the current waste acceptance criteria and other regulatory requirements for disposal at the facility in Clive, Utah, owned by Envirocare of Utah, Inc. The investigation was conducted by identifying issues potentially related to disposal of depleted uranium (DU) products at Envirocare and conducting an initial analysis of them. Discussions were then held with representatives of Envirocare, the state of Utah (which is a NRC Agreement State and, thus, is the cognizant regulatory authority for Envirocare), and DOE Oak Ridge Operations. Provisional issue resolution was then established based on the analysis and discussions and documented in a draft report. The draft report was then reviewed by those providing information and revisions were made, which resulted in this document. Issues that were examined for resolution were (1) license receipt limits for U isotopes; (2) DU product classification as Class A waste; (3) use of non-DOE disposal sites for disposal of DOE material; (4) historical NRC views; (5) definition of chemical reactivity; (6) presence of mobile radionuclides; and (7) National Environmental Policy Act coverage of disposal. The conclusion of this analysis is that an amendment to the Envirocare license issued on October 5, 2000, has reduced the uncertainties regarding disposal of the DU product at Envirocare to the point that they are now comparable with uncertainties associated with the disposal of the DU product at the Nevada Test Site that were discussed in an earlier report.

  20. Nevada Test Site Environmental Report 2008 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2009-09-01

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  1. Nevada Test Site Environmental Report 2009, Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills, ed.

    2010-09-13

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  2. Acceptance test procedure for the 105-KW isolation barrier leak rate

    International Nuclear Information System (INIS)

    McCracken, K.J.

    1995-01-01

    This acceptance test procedure shall be used to: First establish a basin water loss rate prior to installation of the two isolation barriers between the main basin and the discharge chute in K-Basin West. Second, perform an acceptance test to verify an acceptable leakage rate through the barrier seals. This Acceptance Test Procedure (ATP) has been prepared in accordance with CM-6-1 EP 4.2, Standard Engineering Practices

  3. 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

  4. Radiological Situation at the Bomb Test Sites

    International Nuclear Information System (INIS)

    Valkovic, V.

    1998-01-01

    An overview of radiological situation at the selected bomb test sites is presented. The report is based on the reports and measurements performed by IAEA while the author was a head of its Physics-Chemistry-Instrumentation Laboratory. Radiological conditions at Bikini Atoll (USA testing ground), Mururoa and Fangataufa Atolls (French testing ground) and Semipalatinsk (SSSR testing ground) have been discussed in some details. (author)

  5. Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 2 testing

    International Nuclear Information System (INIS)

    Ritter, G.A.

    1995-01-01

    This document summarizes the results of the Phase 2 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the test mixer pump currently installed in Tank 241-SY-101. The purpose of this acceptance test is to verify the strength of the containment bag and bag bottom cinching mechanism. It is postulated that 68 gallons of waste could be trapped inside the pump internals. The bag must be capable of supporting this waste if it shakes loose and drains to the bottom of the bag after the bag bottom has been cinched closed. This acceptance test was performed at the Maintenance and Storage Facility (MASF) Facility in the 400 area on January 23, 1995. The bag assembly supported the weight of 920 kg (2,020 lbs) of water with no leakage or damage to the bag. This value meets the acceptance criteria of 910 kg of water and therefore the results were found to be acceptable. The maximum volume of liquid expected to be held up in the pump internals is 258 L (68 gallons), which corresponds to 410 kg. This test weight gives just over a safety factor of 2. The bag also supported a small shock load while it was filled with water when the crane hoisted the bag assembly up and down. Based on the strength rating of the bag components, the bag assembly should support 2--3 times the test weight of 910 kg

  6. Nevada Test Site Environmental Report 2003

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Nevada

    2004-10-01

    The Nevada Test Site Environmental Report 2003 was prepared by Bechtel Nevada to meet the requirements and guidelines of the U.S. Department of Energy and the information needs of the public. This report is meant to be useful to members of the public, public officials, regulators, and Nevada Test Site contractors. The Executive Summary strives to present in a concise format the purpose of the document, the NTS mission and major programs, a summary of radiological releases and doses to the public resulting from site operations, a summary of non-radiological releases, and an overview of the Nevada Test Site Environmental Management System. The Executive Summary, combined with the following Compliance Summary, are written to meet all the objectives of the report and to be stand-alone sections for those who choose not to read the entire document.

  7. Determinations of TSD facility acceptability under the CERCLA Off-Site Rule

    International Nuclear Information System (INIS)

    1997-06-01

    On September 22, 1993, the US Environmental Protection Agency (EPA) published the ''Off-Site Rule'' to implement section 121(d)(3) of the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). CERCLA section 121(d)(3) requires that wastes generated as a result of remediation activities taken under CERCLA authority and transferred off-site be managed only at facilities that comply with the Resource Conservation and Recovery Act. In 1994, the DOE's Office of Environmental Policy and Assistance (OEPA), RCRA/CERCLA Division (EH-413) published a CERCLA Information Brief titled ''The Off-Site Rule'' which describes the content of the Off-Site Rule and clarifies some of its implications for DOE remedial actions under CERCLA. Additionally, EH-413 published the Guide on Selecting Compliant Off-Site Hazardous Waste Treatment, Storage and Disposal Facilities which provides a regulatory roadmap for accomplishing off-site transfers of environmental restoration and process hazardous waste at DOE facilities in a manner compliant with the Off-Site Rule and other relevant Federal regulations. Those guidance documents concentrate primarily on DOE's perspective as a hazardous waste generator. The purpose of this Information Brief is to address the implications of the Off-Site Rule for DOE-owned hazardous waste treatment, storage or disposal facilities that accept CERCLA remediation wastes from off-site locations

  8. Philips Gemini TF64 PET/CT Acceptance Testing

    International Nuclear Information System (INIS)

    González Gonzalez, Joaquín J.; Calderón Marin, Carlos F.; Varela Corona, Consuelo; Machado Tejeda, Adalberto; González Correa, Héctor J.

    2016-01-01

    The Philips Gemini TF64 is the first PET/CT scanner installed in Cuba at the Institute of Oncology and Radiobiology in 2014. It is a third generation fully tridimensional whole body PET scanner with time-of-flight (TOF) technology combined with a 64-slice Brilliance CT scanner. The CT detector module contains 672x64 solid state detector, incorporating GOS scintillators, optical diodes and electronic signal channels arranged in 64 side by side arcs, with 672 detectors in each arc. There are sixteen 0.75 mm individual detector elements around the center and four 1.5 mm elements at each end, resulting in a 24 mm total detection length. The PET detector consists of 28 pixelar modules of a 23x44 array of 4x4x22 mm3 of LYSO crystals arranged in an Anger-logic detector design. The hardware coincidence-timing window for this scanner is set at 4 ns and delayed coincidence window technique is used to estimate the random coincidences in collected data. In this study the performance characteristics of PET/CT scanner were measured as part of the program tests of acceptance for clinical use.Methodology. The performance characteristics of CT scanner were evaluated by manufacturer protocol using Philips system performance phantom. Some additional geometrical tests were performed by the user. The intrinsic measurements of energy resolution as well as timing resolution, which define the TOF performance of PET scanner, were performed following the recommendations of manufacturer using 18 F. Spatial resolution, sensitivity, scatter fraction, counting rate performance, image quality and accuracy were measured according to the NEMA NU-2 2007 procedures. Additionally, to characterize the effect of TOF reconstruction on lesion contrast and noise, the standard NEMA torso phantom was reconstructed with and without TOF capability. The accuracy of PET/CT image registration was tested according to the manufacturer protocol using an image alignment calibration holder with 6 point sources of 22

  9. Interdisciplinary hydrogeologic site characterization at the Nevada Test Site

    International Nuclear Information System (INIS)

    Hawkins, W.L.; Wagoner, J.L.; Drellack, S.L.

    1992-01-01

    The Nevada Test Site was established in 1950 as a continental area for testing nuclear devices. Hydrogeologic investigations began in earnest with the US Geological Survey mapping much of the area from 1960 to 1965. Since 1963, all nuclear detonations have been underground. Most tests are conducted in vertical shafts, but a small percentage are conducted in tunnels. The majority of detonation points are above the water table, primarily in volcanic rocks, but sometimes in alluvium. Hydrogeologic investigations began in earnest with the US Geological Survey's mapping of much of the NTS region from 1960 to 1965. Following the BANEBERRY test in December 1970, which produced an accidental release of radioactivity to the atmosphere, the US Department of Energy (then the Atomic Energy Commission) established the Containment Evaluation Panel (CEP). Results of interdisciplinary hydrogeologic investigations for each test location are included in a Containment Prospectus which is thoroughly reviewed by the CEP

  10. Acceptance Test Report for the 241-AZ-101 Ultrasonic Interface Level Analyzer

    International Nuclear Information System (INIS)

    ANDREWS, J.E.

    2000-01-01

    This document comprises the Acceptance Test Report for the 241-AZ-101 Ultrasonic Interface Level Analyzer. This document presents the results of Acceptance Testing of the 241-AZ-101 Ultrasonic Interface Level Analyzers (URSILLAs). Testing of the URSILLAs was performed in accordance with ATP-260-001, ''URSILLA Pre-installation Acceptance Test Procedure''. The objective of the testing was to verify that all equipment and components function in accordance with design specifications and original equipment manufacturer's specifications

  11. Nevada Test Site Environmental Report 2004

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2005-10-01

    The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders.

  12. Assessment of Public Acceptability in LILW Repository Site Selection Process in Slovenia

    International Nuclear Information System (INIS)

    Zeleznik, N.; Kralj, M.; Polic, M.; Kos, D.

    2006-01-01

    Slovenian national agency for radioactive waste management ARAO has after longer period of preparation activities started with the more direct work on the site selection process for low and intermediate level waste (LILW) repository. In November 2004, the official administrative procedure for the siting of the repository started with the First public conference on spatial planning issues carried out by the Ministry of Environment and Spatial Planning together with ARAO. Just after the conference the Program for the preparation of the Detailed plan of national importance for the LILW repository was accepted by the Ministry. ARAO invited in the beginning of December 2004 all local communities in Slovenia (except 3 of them which have already refused to cooperate) to participate and volunteer a site or area in their local community for further investigation. The invitation for the application of local communities provided clear instructions on how to participate in further determination of potentially suitable sites and under what conditions. By the beginning of April 2005 ARAO finished the bidding process with 8 applications of local communities which decided to participate in the further site selection for LILW repository. Due to the financial and other limitations (human resources, spatial planning procedure, etc.) only in maximum three local communities further characterization could be performed. Therefore prefeasibility study of all volunteer local communities was conducted in which besides technical, environmental and spatial availability also public acceptability should be assessed. For assessment of public acceptability the methodology has been prepared which includes objective parameters of local environment (such as demographic data, economy, infrastructure and social issues in relation to the repository) as well as subjective values (attitudes of individual groups - opinion makers, politicians and all residents - to the sitting and construction of LILW

  13. Nevada Test Site Environmental Report 2008

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2009-09-01

    The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

  14. Nevada Test Site Environmental Report 2008 Summary

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2009-09-01

    The Nevada Test Site Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

  15. Nevada Test Site annual site environmental report, 1989

    Energy Technology Data Exchange (ETDEWEB)

    Wruble, D T; McDowell, E M [eds.

    1990-11-01

    Prior to 1989 annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the offsite radiological surveillance program conducted by the US Environmental Protection Agency (EPA), Environmental Monitoring Systems Laboratory, Las Vegas, Nevada, were reported separately by that Agency. Beginning with this 1989 annual Site environmental report for the NTS, these two documents are being combined into a single report to provide a more comprehensive annual documentation of the environmental protection program conducted for the nuclear testing program and other nuclear and non-nuclear activities at the Site. The two agencies have coordinated preparation of this combined onsite and offsite report through sharing of information on environmental releases and meteorological, hydrological, and other supporting data used in dose-estimate calculations. 57 refs., 52 figs., 65 tabs.

  16. Rehabilitation of former nuclear test sites in Australia

    International Nuclear Information System (INIS)

    1990-01-01

    A range of options with indicative cost estimates and timescale has been defined for clean-up of the former British nuclear test sites at Maralinga and Emu in South Australia. The situation at the former test sites on the Monte Bello Islands has been reported separately. The predominant contributor to potential radiation dose at the test sites is residual plutonium contamination of soil which may be incorporated into the body through inhalation of resuspended dust. Acceptable levels of radioactive soil contamination based upon organ doses from incorporated plutonium and the associated health detriment are proposed by the Technical Assessment Group for a series of land-use options ranging from fully unrestricted habitation by Aboriginals including the case of high dependence on local plants and animals for food: to casual access by Aboriginals assuming retained or, if necessary, extended fences. The area of land affected and the quantity of soil and other material with more than the proposed limit of contamination as well as a range of remedial measures for reduction of the contamination to a level acceptable for each of the land-use options has been assessed and methods proposed for safe disposal of the contaminated materials. The associated costs of these remedial measures and disposal methods have also been estimated. 28 refs., 71 tabs., 45 figs

  17. Acceptance Test Report for Gamma Carts A and B

    International Nuclear Information System (INIS)

    FULLER, P.J.

    2000-01-01

    Report of Shop Test of the Gamma Cart System to be used in the AZ-101 Mixer Pump Demonstration Test. Reports of the hardware and software tests. The objective of the testing was to verify in the shop that the hardware and software operated according to design specifications before field-testing and installation

  18. Nevada Test Site Environmental Report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills

    2008-09-01

    The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

  19. Nevada Test Site Environmental Report 2007

    International Nuclear Information System (INIS)

    Cathy Wills

    2008-01-01

    The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report

  20. Nevada Test Site Environmental Report 2007 Summary

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills

    2008-09-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2007 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

  1. Thermocouple module halt acceptance test report for tank 241-SY-101 DACS-1

    International Nuclear Information System (INIS)

    Larsen, D.C.

    1998-01-01

    Testing was started on February 24, 1998 and completed on February 25, 1998. The completed procedure consists of 4 acceptance test sections, 6.1 through 6.4. Three test exceptions were identified during the procedure. The first test exception was determined to be unrelated to the ATP and unfortunate that the instrument failed during the ATP. The next two test exceptions were disposition as acceptable because the alarming functions worked correctly in identifying a problem when software communications were interrupted. The test was completed satisfactorily over 2 days. The remainder of the acceptance test report is the completed test procedure

  2. Geologic structure of Semipalatinsk test site territory

    International Nuclear Information System (INIS)

    Ergaliev, G.Kh.; Myasnikov, A.K.; Nikitina, O.I.; Sergeeva, L.V.

    2000-01-01

    This article gives a short description of the territory of Semipalatinsk test site. Poor knowledge of the region is noted, and it tells us about new data on stratigraphy and geology of Paleozoic layers, obtained after termination of underground nuclear explosions. The paper contains a list a questions on stratigraphy, structural, tectonic and geologic formation of the territory, that require additional study. (author)

  3. Nevada Test Site Environmental Report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills, ed.

    2010-09-13

    The Nevada Test Site Environmental Report 2009 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ Nevada Test Site Environmental Reports (NTSERs) are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx. This NTSER was prepared to satisfy DOE Order DOE O 231.1A, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NTSER summarizes data and compliance status for calendar year 2009 at the Nevada Test Site (NTS) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory (RSL)-Nellis. It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

  4. Assessment of public acceptability in site selection process. The methodology and the results

    International Nuclear Information System (INIS)

    Zeleznik, N.; Kralj, M.; Polic, M.; Kos, D.; Pek Drapal, D.

    2005-01-01

    The site selection process for the low and intermediate radioactive waste (LILW) repository in Slovenia follows the mixed mode approach according to the model proposed by IAEA. After finishing the conceptual and planning stage in 1999, and after identification of the potentially suitable areas in the area survey stage in 2001, ARAO (Agency for radwaste management) invited all municipalities to volunteer in the procedure of placing the LILW repository in the physical environment. A positive response was received from eight municipalities, though three municipalities later resigned from it. A selection between twelve locations in these five municipalities had to be done because Slovenian procedure provides for only three locations to be further evaluated in the stage of identification of potentially suitable sites. A pre-feasibility study of the public acceptability, together with the technical aspects (safety, technical functionality, economic, environmental and spatial aspects) was performed. The aspect of public acceptability included objective and subjective evaluation criteria. The former included information obtained from studies of demography, data on local economy, infrastructure and eventual environmental problems, media analysis, and earlier public opinion polls. The latter included data obtained from topical workshops, free phone line, telephone interviews with the general public and personal interviews with representatives of decision makers and public opinion leaders, as well as a public opinion poll in all included communities. Evaluated municipalities were ranked regarding their social suitability for the radioactive waste site. (author)

  5. Acceptance Test Report for the 241-AN-107 Enraf Advanced Technology Gauges

    International Nuclear Information System (INIS)

    Dowell, J.L.; Enderlin, V.R.

    1995-06-01

    This Acceptance Test Report covers the results of the execution of the Acceptance Test Procedure for the 241-AN-107 Enraf Advanced Technology Gauges. The test verified the proper operation of the gauges to measure waste density and level in the 241-AN-107 tank

  6. Nuclear test at Semipalatinsk test site and their environmental impacts

    International Nuclear Information System (INIS)

    Logachev, V.A.

    2000-01-01

    This paper present classification of nuclear tests conducted at the Semipalatinsk test site by tier radiation hazards. The Institute of Biophysics of the Russian Ministry of Health established a data base the archival data on radiation situation parameters and compiled an album of radioactive plum footprints. The paper states that external and internal exposure doses received by population lived in the test vicinity can sufficiently reliably assesses using archival data. (author)

  7. Perceptions about the acceptability and prevalence of HIV testing ...

    African Journals Online (AJOL)

    Yoliswa Ntsepe

    2014-07-25

    Jul 25, 2014 ... Keywords: HIV Counselling and Testing, perceptions, stigma, discrimination and confidentiality, ..... was very little self-initiated HIV testing in their communities. ..... women seek help much earlier as it a normalized behaviour,.

  8. Acceptance criteria for the physical protection upgrade rule requirements for fixed sites. Information guide

    International Nuclear Information System (INIS)

    Dwyer, P.

    1980-09-01

    This document has been developed as a tool to assist in providing consistent evaluation of upgraded physical security plans submitted in response to the Physical Protection Upgrade Rule, effective March 25, 1980. It presents a means for assuring licensee compliance with every regulatory requirement of particular significance to the protection of the public health and safety. Acceptance criteria are included to determine the extent to which each licensee meets the regulatory requirements. The format parallels Regulatory Guide 5.52, Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites

  9. Nevada Test Site Radiation Protection Program

    Energy Technology Data Exchange (ETDEWEB)

    Radiological Control Managers' Council, Nevada Test Site

    2007-08-09

    Title 10 Code of Federal Regulations (CFR) 835, 'Occupational Radiation Protection', establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (onsite or offsite) DOE National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration offsite projects.

  10. Nevada Test Site Environmental Report 2005

    International Nuclear Information System (INIS)

    Cathy A. Wills

    2006-01-01

    The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts

  11. Nevada Test Site Environmental Report 2005

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2006-10-01

    The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

  12. Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

    International Nuclear Information System (INIS)

    HOLM, M.J.

    1999-01-01

    This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver devices. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

  13. Mixed waste characterization and certification at the Nevada Test Site

    International Nuclear Information System (INIS)

    Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

    1988-01-01

    The Radioactive Waste Management Project at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste. The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B permit application, pertinent DOE guidelines governing waste acceptance criteria and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with ALARA precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

  14. Mixed waste characterization and certification at the Nevada Test Site

    International Nuclear Information System (INIS)

    Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

    1988-01-01

    The Radioactive Waste Management Project (RWMP) at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste (MW). The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B Permit application, pertinent DOE guidelines governing waste acceptance criteria (WAC) and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with as low as reasonably achievable (ALARA) precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

  15. Hydrogeologic investigations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Hawkins, W.L.; Trudeau, D.A.; Drellack, S.L.

    1992-01-01

    The Nevada Test Site was established in 1950 as a continental area for testing nuclear devices and, since 1963, all nuclear detonations there have been underground. Most tests are conducted in vertical shafts with a small percentage conducted in tunnels. The majority of detonation points are above the water table, primarily in volcanic rocks or alluvium. In the testing areas the water table is 450--700 m below the surface. Pre- and post- event geologic investigations are conducted for each test location and long-term studies assess the impact of underground testing on a more regional scale. Studies in progress have not identified any impact on the regional ground water system from testing, but some local effects have been recognized. In some areas where several large tests have been conducted below the water table, water levels hundreds of meters above the regional water table have been measured and radioactivity has been discovered associated with fractures in a few holes. Flow-through and straddle packer testing has revealed unexpectedly high hydraulic pressures at depth. Recently, a multiple completion monitoring well installed to study three zones has confirmed the existence of a significant upward hydraulic gradient. These observations of local pressurization and fracture flow are being further explored to determine the influence of underground nuclear testing on the regional hydrogeologic system

  16. Project B610 process control configuration acceptance test report

    International Nuclear Information System (INIS)

    Silvan, G.R.

    1995-01-01

    The purpose of this test is to verify the Westinghouse configuration of the MICON A/S Distributed Control System for project B610. The following will be verified: (1) proper assignment and operation of all field inputs to and outputs from the MICON Termination panels; (2) proper operation of all display data on the operators' console; (3) proper operation of all required alarms; and (4) proper operation of all required interlocks. This test only verifies the proper operation of the Westinghouse control configuration (or program). It will not be responsible for verifying proper operation of the MICON hardware or operating software. Neither does it test any of the B610 instrument. The MICON hardware and software has been tested as part of the equipment procurement. Instrumentation and wiring installed under project B620 will be tested under a separate functional test. In some cases, precise transmitter ranges, alarm setpoints, and controller tuning parameters are not available at this time. Therefore, approximate values are used during the test. This should not affect the proper operation of the configuration or the validity of this test. Final values will be assigned during operability testing

  17. Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

    Energy Technology Data Exchange (ETDEWEB)

    BARNES, D.A.

    2000-06-01

    The purpose of this document is to describe tests performed to validate Revision 12.0 of the TMACS Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be communicating to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab.

  18. Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

    International Nuclear Information System (INIS)

    BARNES, D.A.

    2000-01-01

    The purpose of this document is to describe tests performed to validate Revision 12.0 of the TMACS Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be communicating to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

  19. Determinants of the Acceptance of Sustainable Production Strategies among Dairy Farmers: Development and Testing of a Modified Technology Acceptance Model

    Directory of Open Access Journals (Sweden)

    Simona Naspetti

    2017-10-01

    Full Text Available An extended version of the Technology Acceptance Model (TAM was applied by means of Structural Equation Modelling to testing various hypotheses on attitudes and intentions of dairy farmers towards three novel sustainable production strategies, as well as the influence of organic practices and collaborative behaviours, such as information sharing with supply-chain partners. Data on the acceptance of three sustainable production strategies, namely ‘Agro-forestry’, ‘Alternative protein source’, and ‘Prolonged maternal feeding’ were collected by a survey of dairy farmers in six European Union (EU countries (Austria, Belgium, Denmark, Finland, Italy, United Kingdom. We found that perceived usefulness is the key determinant of acceptance, while the intention to adopt a sustainable production strategy may derive from the influence of opinions (and behaviours of relevant others (e.g., leading dairy farmers, family members, advisors showing the role of interactions among farmers and other stakeholders in the adoption of innovations. Finally, the perceived usefulness of all of the investigated strategies is higher for organic farmers, while collaborative patterns reduce the impact of subjective norm on usefulness and overall acceptance. Our findings should encourage policy makers to consider the important role of supply chain management practices, including collaboration, to enhance the sustainability of dairy farming systems.

  20. Acceptance of genetic testing in a general population

    DEFF Research Database (Denmark)

    Aro, A R; Hakonen, A; Hietala, M

    1997-01-01

    in favour of mandatory genetic testing than other respondents. Respondents with university education were more critical towards genetic testing and expressed their worry about eugenics more often than other education groups. In conclusion, there are age, education and gender related differences...

  1. Acceptance test procedure: RMW Land Disposal Facility Project W-025

    International Nuclear Information System (INIS)

    Roscha, V.

    1994-01-01

    This ATP establishes field testing procedures to demonstrate that the electrical/instrumentation system functions as intended by design for the Radioactive Mixed Waste Land Disposal Facility. Procedures are outlined for the field testing of the following: electrical heat trace system; transducers and meter/controllers; pumps; leachate storage tank; and building power and lighting

  2. Perceptions about the acceptability and prevalence of HIV testing ...

    African Journals Online (AJOL)

    HIV counselling and testing (HCT) is considered important because it is an entry point to a comprehensive continuum of care for HIV/AIDS. The South African Department of Health launched an HCT campaign in April 2010, and this reached 13,269,746 people by June 2011, of which 16% tested HIV positive and 400,000 of ...

  3. Retrofit and acceptance test of 30-cm ion thrusters

    Science.gov (United States)

    Poeschel, R. L.

    1981-01-01

    Six 30 cm mercury thrusters were modified to the J-series design and evaluated using standardized test procedures. The thruster performance meets the design objectives (lifetime objective requires verification), and documentation (drawings, etc.) for the design is completed and upgraded. The retrofit modifications are described and the test data for the modifications are presented and discussed.

  4. Test and acceptance from the AE point of view

    International Nuclear Information System (INIS)

    Sommer, W.C.

    1976-01-01

    The power industry has undergone the transition from utilizing construction engineers for startup activities to utilizing test engineers who are responsible for the preparation or execution of a formal test program. This has come about because testing has been given sufficient importance to justify those participating within the industry to establish it as a specialty phase apart from engineering/design and construction. Presently testing is being conducted by those organizations that have either engineered and/or constructed the unit which may be a position of conflict in regards to unbiased test. The tester (third party) concept promotes the repetition, independence, and expertise of a test organization responsible to the utility for certifying that each system has been tested to the design criteria established by others. A move to this concept should result in better generating stations with higher availability because it has been completely tested by an organization with this sole contractual responsibility. The AE, NSSS, and utility would all benefit with possibly no additional costs incurred

  5. Site Release Report for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

    International Nuclear Information System (INIS)

    K.E. Rasmuson

    2002-01-01

    the reclaimed sites. Sixty percent of the reference area means for density, cover, and species richness were compared to the estimated means for the reclaimed sites. Plant density, cover, and species richness at the C-Well Pipeline and UE-25 Large Rocks test site were greater than the success criteria and all key attributes indicated the sites were in acceptable condition. Therefore, these two sites were recommended for release from further monitoring. Of the 29 ground surface facility test pits, 26 met the criterion for density, 21 for cover, and 23 for species richness. When key attributes and conditions of the plant community near each pit were taken into account, 27 of these pits were recommended for release. Success parameters and key attributes at ground surface facility test pits 19 and 20 were inadequate for site release. Transplants of native species were added to these two sites in 2001 to improve density, cover, and species richness

  6. Site Release Reports for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

    Energy Technology Data Exchange (ETDEWEB)

    K.E. Rasmuson

    2002-04-02

    and aspect were chosen for comparison to the reclaimed sites. Sixty percent of the reference area means for density, cover, and species richness were compared to the estimated means for the reclaimed sites. Plant density, cover, and species richness at the C-Well Pipeline and UE-25 Large Rocks test site were greater than the success criteria and all key attributes indicated the sites were in acceptable condition. Therefore, these two sites were recommended for release from further monitoring. Of the 29 ground surface facility test pits, 26 met the criterion for density, 21 for cover, and 23 for species richness. When key attributes and conditions of the plant community near each pit were taken into account, 27 of these pits were recommended for release. Success parameters and key attributes at ground surface facility test pits 19 and 20 were inadequate for site release. Transplants of native species were added to these two sites in 2001 to improve density, cover, and species richness.

  7. Waste retrieval sluicing system data acquisition system acceptance test report

    International Nuclear Information System (INIS)

    Bevins, R.R.

    1998-01-01

    This document describes the test procedure for the Project W-320 Tank C-106 Sluicing Data Acquisition System (W-320 DAS). The Software Test portion will test items identified in the WRSS DAS System Description (SD), HNF-2115. Traceability to HNF-2115 will be via a reference that follows in parenthesis, after the test section title. The Field Test portion will test sensor operability, analog to digital conversion, and alarm setpoints for field instrumentation. The W-320 DAS supplies data to assist thermal modeling of tanks 241-C-106 and 241-AY-102. It is designed to be a central repository for information from sources that would otherwise have to be read, recorded, and integrated manually. Thus, completion of the DAS requires communication with several different data collection devices and output to a usable PC data formats. This test procedure will demonstrate that the DAS functions as required by the project requirements stated in Section 3 of the W-320 DAS System Description, HNF-2115

  8. Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

    International Nuclear Information System (INIS)

    WANDLING, R.R.

    1999-01-01

    The purpose of this document is to describe tests performed to validate Revision 11.2 of the TMACS Monitor and Control System (TMCACS) and verify that the software functions as intended by design. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

  9. Resolve. Version 2.5: Flammable Gas Accident Analysis Tool Acceptance Test Plan and Test Results

    International Nuclear Information System (INIS)

    LAVENDER, J.C.

    2000-01-01

    RESOLVE. Version 2 .5 is designed to quantify the risk and uncertainty of combustion accidents in double-shell tanks (DSTs) and single-shell tanks (SSTs). The purpose of the acceptance testing is to ensure that all of the options and features of the computer code run; to verify that the calculated results are consistent with each other; and to evaluate the effects of the changes to the parameter values on the frequency and consequence trends associated with flammable gas deflagrations or detonations

  10. Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

    International Nuclear Information System (INIS)

    Peeler, D.

    1999-01-01

    'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

  11. Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

    Energy Technology Data Exchange (ETDEWEB)

    Peeler, D.

    1999-06-22

    'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

  12. MAC mini acceptance test procedure, software Version 3.0

    International Nuclear Information System (INIS)

    Russell, V.K.

    1994-01-01

    The K Basins Materials Accounting (MAC) programs had some major improvements made to it to organize the main-tables by Location, Canister, and Material. This ATP describes how the code was to be tested to verify its correctness

  13. willingness to accept hiv testing among caretakers with a child

    African Journals Online (AJOL)

    Esem

    Results: All the 241 caretakers approached to participate agreed to take ... interviewed were female and only 15 were male.233 out .... Workplace HIV Counselling and Testing: A Cluster- ... Francis Bajunirwe and Michael Muzoora, Barriers to.

  14. Acceptability of self-collected vaginal samples for HPV testing in an ...

    African Journals Online (AJOL)

    Objective: To evaluate the acceptability of self-collected vaginal samples for HPV testing in women living in rural and urban areas of ... Conclusion: Acceptability of self-sampling for HPV testing was similarly excellent in both groups despite their difference in terms ... cancer is the leading cause of death caused by cancer in.

  15. Project W-151 flexible receiver radiation detector system acceptance test plan. Revision 1

    International Nuclear Information System (INIS)

    Troyer, G.L.

    1994-01-01

    The attached document is the Acceptance Test Plan for the portion of Project W-151 dealing with acceptance of gamma-ray detectors and associated electronics manufactured at the Idaho National Engineering Laboratory (INEL). The document provides a written basis for testing the detector system, which will take place in the 305 building (300 Area)

  16. Acceptance Test Procedure: SY101 air pallet system

    International Nuclear Information System (INIS)

    Koons, B.M.

    1995-01-01

    The purpose of this test procedure is to verify that the system(s) procured to load the SY-101 Mitigation Test Pump package fulfills its functional requirements. It will also help determine the man dose expected due to handling of the package during the actual event. The scope of this procedure focuses on the ability of the air pallets and container saddles to carry the container package from the new 100 foot concrete pad into 2403-WD where it will be stored awaiting final disposition. This test attempts to simulate the actual event of depositing the SY-101 hydrogen mitigation test pump into the 2403-WD building. However, at the time of testing road modifications required to drive the 100 ton trailer into CWC were not performed. Therefore a flatbed trailer will be use to transport the container to CWC. The time required to off load the container from the 100 ton trailer will be recorded for man dose evaluation on location. The cranes used for this test will also be different than the actual event. This is not considered to be an issue due to minimal effects on man dose

  17. Acceptance Test Report for the 241-AZ-101 Ultrasonic Interface Level Analyzer

    Energy Technology Data Exchange (ETDEWEB)

    ANDREWS, J.E.

    2000-01-27

    This document comprises the Acceptance Test Report for the 241-AZ-101 Ultrasonic Interface Level Analyzer. This document presents the results of Acceptance Testing of the 241-AZ-101 Ultrasonic Interface Level Analyzers (URSILLAs). Testing of the URSILLAs was performed in accordance with ATP-260-001, ''URSILLA Pre-installation Acceptance Test Procedure''. The objective of the testing was to verify that all equipment and components function in accordance with design specifications and original equipment manufacturer's specifications.

  18. Acceptance Test Procedure for New Pumping and Instrumentation Control Skid L

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''L''. The ATP will be performed after the construction of the PIC skid in the shop

  19. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''P''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  20. Acceptance Test Procedure for New Pumping and Instrumentation Control Skid N

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''N''. The ATP will be performed after the construction of the PIC skid in the shop

  1. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid W

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''W''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  2. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid V

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control. (PIC) skid designed as ''V''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  3. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''V''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designated as ''V''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  4. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''Q''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''Q''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  5. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''T''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designated as ''T''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  6. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid T

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing Of the new Pumping Instrumentation and Control (PIC) skid designed as ''T''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  7. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid R

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''R''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  8. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''U''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''U''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

  9. Acceptance test report for the 241-SY-101 Flexible Receiver Gamma Detector System

    International Nuclear Information System (INIS)

    Dowell, J.L.

    1995-01-01

    This Acceptance Test Report is for the 241-SY-101 Flexible Receiver Gamma Detector System. This test verified that the data logger and data converter for the gamma detector system functions as intended

  10. Assessment of national systems for obtaining local acceptance of waste management siting and routing activities

    Energy Technology Data Exchange (ETDEWEB)

    Paige, H.W.; Lipman, D.S.; Owens, J.E.

    1980-07-01

    There is a rich mixture of formal and informal approaches being used in our sister nuclear democracies in their attempts to deal with the difficulties of obtaining local acceptance for siting of waste management facilities and activities. Some of these are meeting with a degree of success not yet achieved in the US. Although this survey documents and assesses many of these approaches, time did not permit addressing in any detail their relevance to common problems in the US. It would appear the US could benefit from a periodic review of the successes and failures of these efforts, including analysis of their applicability to the US system. Of those countries (Germany, Sweden, Switzerland, Japan, Belgium, and the US) who are working to a time table for the preparation of a high-level waste (HLW) repository, Germany is the only country to have gained local siting acceptance for theirs. With this (the most difficult of siting problems) behind them they appear to be in the best overall condition relative to waste management progress and plans. This has been achieved without a particularly favorable political structure, made up for by determination on the part of the political leadership. Of the remaining three countries studied (France, UK and Canada) France, with its AVM production facility, is clearly the world leader in the HLW immobilization aspect of waste management. France, Belgium and the UK appear to have the least favorable political structures and environments for arriving at waste management decisions. US, Switzerland and Canada appear to have the least favorable political structures and environments for arriving at waste management decisions.

  11. Parallel hole collimator acceptance tests for SPECT and planar studies

    International Nuclear Information System (INIS)

    Babicheva, R.R.; Bennie, D.N.; Collins, L.T.; Gruenwald, S.M.

    1998-01-01

    Full text: Different kinds of collimator damage can occur either during shipping or from regular use. Imperfections of construction along the strips or their connections give rise to nonperpendicular hole alignments to the crystal face and can produce potential problems such as ring artifacts and image degradation. Gamma camera collimator hole alignments and integrity were compared in four parallel hole high resolution collimators-two new cast and two used foil collimators, one with damage to the protective surface. [1] The point source flood image of the defective collimator was non-circular as were the images of cast collimators. The image of new foil collimator was circular. [2] High count sheet flood did not show any imperfections. [3] Bone mineral densitometer was used to perform collimated X-ray beam. The collimator was placed on the scanning bed with an X-ray cassette placed directly above it. The damaged area was well demonstrated. [4] The COR offset test was taken at two extreme radii. The offset value with the defective collimator is increased by 0.53 pixel or 129% with increase of COR from radius 14 cm to 28cm. [5] The collimator hole alignment test involves performing multiple measurements of COR along the length of the collimator, and checking for variations in COR with both position of source and angle of rotation. The maximum variation in COR of the defective collimator hole alignment was 1.13 mm. Collimators require testing when new and at regular intervals, or following damage. The point source test can be used for foil collimators. The most sensitive tests were collimated X-ray source, COR offset test and collimator hole alignment

  12. Provider initiated HIV testing and counseling, acceptance and ...

    African Journals Online (AJOL)

    admin

    2007-11-29

    Nov 29, 2007 ... Methods: A facility-based cross-sectional quantitative survey was taken from December 1, 2010 to January 10, 2011 among 414 clients coming .... Debre Berhan Referral Hospital has implemented routine. HIV testing for all out .... (died of) HIV and thinking that they can get the virus showed no association ...

  13. A Muffler Design for Tank Cannon Acceptance Testing

    Science.gov (United States)

    1991-08-01

    designed a muffler to reduce the noise associated with proofing. This muffler is ;maller and lighter than the mufi ±rs tested by CSTA. Figure 1 shows...1 Old Dominion University Mathematics Department ATITN: Dr. Charlie Cooke Norfolk, VA 23508 Aberdeen Proving Ground 2 Dir, USAMSAA ATIN: AMXSY-D, Mr

  14. 10 CFR 36.41 - Construction monitoring and acceptance testing.

    Science.gov (United States)

    2010-01-01

    ... system will operate properly if offsite power is lost and shall verify that the computer has security... system to assure that the requirements in § 36.35 are met for protection of the source rack and the... protection. For panoramic irradiators, the licensee shall test the ability of the heat and smoke detectors to...

  15. MAC mini acceptance test procedures, software Version 3.3

    International Nuclear Information System (INIS)

    Russell, V.K.

    1994-01-01

    The K Basins Materials Accounting (MAC) programs had some improvements made to it to to change slightly the access authorized users had to the modification of critical data. This ATP describes how the code was to be tested to verify its correctness

  16. Test report for run-in acceptance testing of hydrogen mitigation test pump-2

    International Nuclear Information System (INIS)

    Brewer, A.K.; Kolowith, R.

    1995-01-01

    This document provides the results of the run-in test of the replacement mixer pump for the Tank 241-SY-101. The test was conducted at the 400 Area MASF facility between August 12 and September 29, 1994. The report includes findings, analysis, recommendations, and corrective actions taken

  17. Nevada Test Site Environmental Report Summary 2009

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills, ed.

    2010-09-13

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). NNSA/NSO prepares the Nevada Test Site Environmental Report (NTSER) to provide the public an understanding of the environmental monitoring and compliance activities that are conducted on the NTS to protect the public and the environment from radiation hazards and from nonradiological impacts. The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. This summary provides an abbreviated and more readable version of the NTSER. It does not contain detailed descriptions or presentations of monitoring designs, data collection methods, data tables, the NTS environment, or all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

  18. Assessment of national systems for obtaining local acceptance of nuclear waste management siting activities

    International Nuclear Information System (INIS)

    Paige, H.W.; Owens, J.E.

    1984-01-01

    On behalf of the United States Department of Energy (DOE), International Energy Associates Limited (IEAL) of Washington, D.C. has conducted surveys and analyses of fourteen countries' plans and approaches for dealing with the problems of obtaining local siting acceptance for nuclear waste management facilities. It was determined that the following elements of the formal systems generally facilitate and/or expedite waste management siting decisions: (1) a clear-cut pro-nuclear power position on the part of the government; (2) a willingness on the part of the central government to exert (with prudence and restraint) its pre-emptive rights in nuclear matters; (3) political structures in which the heads of regional or provincial governments are appointed by the central government; (4) national laws that link reactor licensing with a detailed plan for waste management; (5) an established and stable policy with regard to reprocessing. In contrast, it was determined that the following elements of the formal system generally hinder waste management siting activities: (1) historically strong local land used veto laws; (2) the use of national referenda for making nuclear decisions; (3) requirements for public hearings. The informal approaches fall into the following five categories: (1) political: e.g. assertion of will by political leaders, activities to enlist support of local politicians, activities to broaden involvement in decision-making; (2) economic: e.g. emphasis on normal benefits, provision for additional economic benefits; (3) siting: e.g. at or near existing nuclear facilities, on government or utility property, at multiple locations to spread the political burden; (4) timing: e.g. decoupling drilling activities from ultimate repository site decision, deliberate deferral to (long-range) future; (5) education: e.g. creation of special government programmes, enlisting of media support

  19. Low-level radioactive waste (LLW) management at the Nevada Test Site (NTS)

    International Nuclear Information System (INIS)

    Becker, B.D.; Gertz, C.P.; Clayton, W.A.; Crowe, B.M.

    1998-01-01

    In 1978, the Department of Energy, Nevada Operations Office (DOE/NV), established a managed LLW disposal project at the Nevada Test Site (NTS). Two, sites which were already accepting limited amounts of on-site generated waste for disposal and off-site generated Transuranic Waste for interim storage, were selected to house the disposal facilities. In those early days, these sites, located about 15 miles apart, afforded the DOE/NV the opportunity to use at least two technologies to manage its waste cost effectively. The Area 5 Radioactive Waste Management Site (RWMS) uses engineered shallow-land burial cells to dispose packaged waste while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. The paper describes the technical attributes of both Area 5 and Area 3 facilities, the acceptance process, the disposal processes, and present and future capacities of both sites

  20. Freshwater algae of the Nevada Test Site

    International Nuclear Information System (INIS)

    Taylor, W.D.; Giles, K.R.

    1979-06-01

    Fifty-two species of freshwater algae were identified in samples collected from the eight known natural springs of the Nevada Test Site. Although several species were widespread, 29 species were site specific. Diatoms provided the greatest variety of species at each spring. Three-fifths of all algal species encountered were diatoms. Well-developed mats of filamentous green algae (Chlorophyta) were common in many of the water tanks associated with the springs and accounted for most of the algal biomass. Major nutrients were adequate, if not abundant, in most spring waters - growth being limited primarily by light and physical habitat. There was some evidence of cesium-137 bioconcentration by algae at several of the springs

  1. The Northern Regional Programme for the acceptance testing of X-ray equipment

    International Nuclear Information System (INIS)

    Faulkner, K.; Harrison, R.M.; Kotre, C.J.; Smith, S.; Davies, M.; Barker, P.

    1989-01-01

    Since 1984 the Regional Medical Physics Department has participated in a regional acceptance testing programme for all X-ray equipment from mobile units to computed tomography scanners. The organizational and radiation physics aspects of the programme are described. Three levels of tests are performed by physicists: the first on installation, the second after 3 months, and the final visit just prior to the end of the manufacturer's warranty. The second test is only performed if any aspect of performance requires rechecking as a result of the first visit. Acceptance test protocols are based on those published by the Institute of Physical Sciences in Medicine. Details of the limiting values for the acceptance test measurements are given. The results of the programme are discussed. In some instances the testing has resulted in modifications to the design and construction of X-ray equipment. Acceptance testing is important in determining a baseline standard of performance against which routine quality assurance may be assessed. (author)

  2. The Northern regional programme for the acceptance testing of X-ray equipment

    International Nuclear Information System (INIS)

    Faulkner, K.; Harrison, R.M.; Kotre, C.J.; Smith, S.; Davies, M.; Barker, P.

    1989-01-01

    Since 1984 the UK Northern Regional Medical Physics Department has participated in a regional acceptance testing programme for all X-ray equipment from mobile units to computed tomography scanners. Organizational and radiation physics aspects of the programme are described. Three levels of tests are performed by physicists: the first on installation, the second after 3 months, the final visit just prior to the end of the manufacturers warranty. The second test is only performed if any aspect of performance requires rechecking as a result of the first. Acceptance test protocols are based on those published by the Institute of Physical Sciences in Medicine. Details limiting values for the acceptance test measurements are given. In some instances testing has resulted in modifications to the design and construction of X-ray equipment. Acceptance testing is important in determining a baseline standard of performance against which routine quality assurance may be assessed. (author)

  3. Solar panel acceptance testing using a pulsed solar simulator

    Science.gov (United States)

    Hershey, T. L.

    1977-01-01

    Utilizing specific parameters as area of an individual cell, number in series and parallel, and established coefficient of current and voltage temperature dependence, a solar array irradiated with one solar constant at AMO and at ambient temperature can be characterized by a current-voltage curve for different intensities, temperatures, and even different configurations. Calibration techniques include: uniformity in area, depth and time, absolute and transfer irradiance standards, dynamic and functional check out procedures. Typical data are given for individual cell (2x2 cm) to complete flat solar array (5x5 feet) with 2660 cells and on cylindrical test items with up to 10,000 cells. The time and energy saving of such testing techniques are emphasized.

  4. Nurses' perceptions, acceptance, and use of a novel in-room pediatric ICU technology: testing an expanded technology acceptance model.

    Science.gov (United States)

    Holden, Richard J; Asan, Onur; Wozniak, Erica M; Flynn, Kathryn E; Scanlon, Matthew C

    2016-11-15

    The value of health information technology (IT) ultimately depends on end users accepting and appropriately using it for patient care. This study examined pediatric intensive care unit nurses' perceptions, acceptance, and use of a novel health IT, the Large Customizable Interactive Monitor. An expanded technology acceptance model was tested by applying stepwise linear regression to data from a standardized survey of 167 nurses. Nurses reported low-moderate ratings of the novel IT's ease of use and low to very low ratings of usefulness, social influence, and training. Perceived ease of use, usefulness for patient/family involvement, and usefulness for care delivery were associated with system satisfaction (R 2  = 70%). Perceived usefulness for care delivery and patient/family social influence were associated with intention to use the system (R 2  = 65%). Satisfaction and intention were associated with actual system use (R 2  = 51%). The findings have implications for research, design, implementation, and policies for nursing informatics, particularly novel nursing IT. Several changes are recommended to improve the design and implementation of the studied IT.

  5. Population dose near the Semipalatinsk test site.

    Science.gov (United States)

    Hille, R; Hill, P; Bouisset, P; Calmet, D; Kluson, J; Seisebaev, A; Smagulov, S

    1998-10-01

    To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 microSv/year for 90Sr. For other radionuclides the internal doses are also negligible.

  6. Population dose near the Semipalatinsk test site

    International Nuclear Information System (INIS)

    Hille, R.; Hill, P.; Kluson, J.; Seisebaev, A.; Smagulov, S.

    1998-01-01

    To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/ year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 μSv/year for 90 Sr. For other radionuclides the internal doses are also negligible. (orig.)

  7. Would you test for 5000 Shillings? HIV risk and willingness to accept HIV testing in Tanzania.

    Science.gov (United States)

    Ostermann, Jan; Brown, Derek S; Mühlbacher, Axel; Njau, Bernard; Thielman, Nathan

    2015-12-01

    Despite substantial public health efforts to increase HIV testing, testing rates have plateaued in many countries and rates of repeat testing for those with ongoing risk are low. To inform policies aimed at increasing uptake of HIV testing, we identified characteristics associated with individuals' willingness-to-accept (WTA) an HIV test in a general population sample and among two high-risk populations in Moshi, Tanzania. In total, 721 individuals, including randomly selected community members (N = 402), female barworkers (N = 135), and male Kilimanjaro mountain porters (N = 184), were asked in a double-bounded contingent valuation format if they would test for HIV in exchange for 2000, 5000 or 10,000 Shillings (approximately $1.30, $3.20, and $6.40, respectively). The study was conducted between September 2012 and February 2013. More than one quarter of participants (196; 27 %) stated they would be willing to test for Tanzania Shilling (TSH) 2000, whereas one in seven (98; 13.6 %) required more than TSH 10,000. The average WTA estimate was TSH 4564 (95 % Confidence Interval: TSH 4201 to 4927). Significant variation in WTA estimates by gender, HIV risk factors and other characteristics plausibly reflects variation in individuals' valuations of benefits of and barriers to testing. WTA estimates were higher among males than females. Among males, WTA was nearly one-third lower for those who reported symptoms of HIV than those who did not. Among females, WTA estimates varied with respondents' education, own and partners' HIV testing history, and lifetime reports of transactional sex. For both genders, the most significant association was observed with respondents' perception of the accuracy of the HIV test; those believing HIV tests to be completely accurate were willing to test for approximately one third less than their counterparts. The mean WTA estimates identified in this study suggest that within the study population, incentivized universal HIV

  8. MBA acceptance test procedures, software Version 1.4

    International Nuclear Information System (INIS)

    Mullaney, J.E.; Russell, V.K.

    1994-01-01

    The Mass Balance Program (MBA) is an adjunct to the Materials Accounting database system, Version 3.4. MBA was written to equip the personnel performing K-Basin encapsulation tasks with a conservative estimate of accumulated sludge during the processing of canisters into and out of the chute. The K Basins Materials Balance programs had some minor improvements made to it to feedback the chute processing status to the operator better. This ATP describes how the code was to be tested to verify its correctness

  9. WRAP low level waste restricted waste management (LLW RWM) glovebox acceptance test report

    International Nuclear Information System (INIS)

    Leist, K.J.

    1997-01-01

    On April 22, 1997, the Low Level Waste Restricted Waste Management (LLW RWM) glovebox was tested using acceptance test procedure 13027A-87. Mr. Robert L. Warmenhoven served as test director, Mr. Kendrick Leist acted as test operator and test witness, and Michael Lane provided miscellaneous software support. The primary focus of the glovebox acceptance test was to examine glovebox control system interlocks, operator Interface Unit (OIU) menus, alarms, and messages. Basic drum port and lift table control sequences were demonstrated. OIU menus, messages, and alarm sequences were examined, with few exceptions noted. Barcode testing was bypassed, due to the lack of installed equipment as well as the switch from basic reliance on fixed bar code readers to the enhanced use of portable bar code readers. Bar code testing was completed during performance of the LLW RWM OTP. Mechanical and control deficiencies were documented as Test Exceptions during performance of this Acceptance Test. These items are attached as Appendix A to this report

  10. Social acceptance process model for ensuring the high-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Wada, Ryutaro; Tanaka, Satoru; Nagasaki, Shinya

    2009-01-01

    Generally speaking, a vast, advanced and unfamiliar science and technology are unacceptable to the public for fear of their unknown nature. Here, the social acceptance process model was examined on the basis of the analysis of the cause phenomenon and numerical grounds, by referring to the problems on the application of literature documentation for location examination of a high-level radioactive waste disposal site in Toyo town in Kochi Pref. in April 2007. In analyzing the Toyo town case, we have found a possibility that the majority of local residents knew very little about the object opposed by the fringe route processing. To ensure a healthy decision making by the public, it is vital to convey fundamental information using sufficient wide-area PR media before the issue becomes actual. After the issue becomes actual, dialog with residents through a careful technology assessment is indispensable. The authors focus attention on the decision-making process of human beings from the social and psychological viewpoints, and point out that it is desirable for promoting social acceptance by adopting two approaches: a direct approach aiming at better intelligibility for the different resident layers and a deductive approach in technological essence. (author)

  11. Probabilistic Requirements (Partial) Verification Methods Best Practices Improvement. Variables Acceptance Sampling Calculators: Empirical Testing. Volume 2

    Science.gov (United States)

    Johnson, Kenneth L.; White, K. Preston, Jr.

    2012-01-01

    The NASA Engineering and Safety Center was requested to improve on the Best Practices document produced for the NESC assessment, Verification of Probabilistic Requirements for the Constellation Program, by giving a recommended procedure for using acceptance sampling by variables techniques as an alternative to the potentially resource-intensive acceptance sampling by attributes method given in the document. In this paper, the results of empirical tests intended to assess the accuracy of acceptance sampling plan calculators implemented for six variable distributions are presented.

  12. Standardization of waste acceptance test methods by the Materials Characterization Center

    International Nuclear Information System (INIS)

    Slate, S.C.

    1985-01-01

    This paper describes the role of standardized test methods in demonstrating the acceptability of high-level waste (HLW) forms for disposal. Key waste acceptance tests are standardized by the Materials Characterization Center (MCC), which the US Department of Energy (DOE) has established as the central agency in the United States for the standardization of test methods for nuclear waste materials. This paper describes the basic three-step process that is used to show that waste is acceptable for disposal and discusses how standardized tests are used in this process. Several of the key test methods and their areas of application are described. Finally, future plans are discussed for using standardized tests to show waste acceptance. 9 refs., 1 tab

  13. Project B610 process control configuration acceptance test procedure

    International Nuclear Information System (INIS)

    Silvan, G.R.

    1994-01-01

    The purpose of this test is to verify the Westinghouse configuration of the MICON A/S Distributed Control System for project B610. The following will be verified: proper assignment and operation of all field inputs to and outputs from the MICON Termination panels; proper operation of all display data on the operator's console; proper operation of all required alarms; and proper operation of all required interlocks. The MICON A/S control system is configured to replace all the control, indication, and alarm panels now located in the Power Control Room. Nine systems are covered by this control configuration, 2736-ZB HVAC, 234-5Z HVAC, Process Vacuum, Dry Air, 291-Z Closed Loop Cooling, Building Accelerometer, Evacuation Siren, Stack CAMs, and Fire. The 2736-ZB HVAC system consists of the ventilation controls for 2736-ZB and 2736-Z as well as alarms for the emergency generators and 232-Z. The 234-5Z HVAC system is the ventilation controls for 235-5Z and 236-Z buildings. Process Vacuum covers the controls for the 26 inch vacuum system. Dry Air covers the controls for the steam and electric air dryers. The 291-Z Closed Loop Cooling system consists of the status indications and alarms for the 291-Z compressor and vacuum pump closed loop cooling system. The rest of closed loop cooling was tested earlier. The Building Accelerometer system consists of the status indications for the two seismic system accelerometers. The Evacuation Siren system includes the controls for the evacuation and take cover sirens. Stack CAMs cover the alarms for the various building ventilation stack continuous air monitors. Finally, the Fire system covers the various fire alarms now located in Room 321-A

  14. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2008-01-01

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells

  15. Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2008-09-01

    The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

  16. Acceptance test report for the Tank 241-C-106 in-tank imaging system

    International Nuclear Information System (INIS)

    Pedersen, L.T.

    1998-01-01

    This document presents the results of Acceptance Testing of the 241-C-106 in-tank video camera imaging system. The purpose of this imaging system is to monitor the Project W-320 sluicing of Tank 241-C-106. The objective of acceptance testing of the 241-C-106 video camera system was to verify that all equipment and components function in accordance with procurement specification requirements and original equipment manufacturer's (OEM) specifications. This document reports the results of the testing

  17. Rehabilitation of nuclear test site at Maralinga

    International Nuclear Information System (INIS)

    Grad, P.

    1997-01-01

    A program to rehabilitate contaminated areas at the Maralinga Nuclear Test Range in South Australia is being undertaken by the Australian Department of Primary Industries and Energy (DPIE). A major part of the program is directed at reducing the risk presented by the contaminated debris buried at Taranaki, Maralinga's most heavily contaminated site. The rehabilitation program is using the insitu vitrification technology developed for the US Department of Energy. The program is now in its third phase, involving the construction of the full-scale treatment plant. This will be completed later this year. The fourth and last phase will involve the treatment of the Taranaki pits. This will commence in 1998. Tests carried out so far indicated that the normalized leach rates for all oxides in the vitrified product were less than 0.1g/m 2 . ills

  18. Nevada test site water-supply wells

    International Nuclear Information System (INIS)

    Gillespie, D.; Donithan, D.; Seaber, P.

    1996-05-01

    A total of 15 water-supply wells are currently being used at the Nevada Test Site (NTS). The purpose of this report is to bring together the information gleaned from investigations of these water-supply wells. This report should serve as a reference on well construction and completion, static water levels, lithologic and hydrologic characteristics of aquifers penetrated, and general water quality of water-supply wells at the NTS. Possible sources for contamination of the water-supply wells are also evaluated. Existing wells and underground nuclear tests conducted near (within 25 meters (m)) or below the water table within 2 kilometers (km) of a water-supply were located and their hydrogeologic relationship to the water-supply well determined

  19. Alternatives to animal testing: research, trends, validation, regulatory acceptance.

    Science.gov (United States)

    Huggins, Jane

    2003-01-01

    Current trends and issues in the development of alternatives to the use of animals in biomedical experimentation are discussed in this position paper. Eight topics are considered and include refinement of acute toxicity assays; eye corrosion/irritation alternatives; skin corrosion/irritation alternatives; contact sensitization alternatives; developmental/reproductive testing alternatives; genetic engineering (transgenic) assays; toxicogenomics; and validation of alternative methods. The discussion of refinement of acute toxicity assays is focused primarily on developments with regard to reduction of the number of animals used in the LD(50) assay. However, the substitution of humane endpoints such as clinical signs of toxicity for lethality in these assays is also evaluated. Alternative assays for eye corrosion/irritation as well as those for skin corrosion/irritation are described with particular attention paid to the outcomes, both successful and unsuccessful, of several validation efforts. Alternative assays for contact sensitization and developmental/reproductive toxicity are presented as examples of methods designed for the examination of interactions between toxins and somewhat more complex physiological systems. Moreover, genetic engineering and toxicogenomics are discussed with an eye toward the future of biological experimentation in general. The implications of gene manipulation for research animals, specifically, are also examined. Finally, validation methods are investigated as to their effectiveness, or lack thereof, and suggestions for their standardization and improvement, as well as implementation are reviewed.

  20. 46 CFR 159.007-5 - Production inspections and tests: Application for acceptance.

    Science.gov (United States)

    2010-10-01

    ... acceptance. 159.007-5 Section 159.007-5 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS: SPECIFICATIONS AND APPROVAL APPROVAL OF EQUIPMENT AND MATERIALS...) Is accepted by the Commandant for approval inspections and tests of the equipment or material under...

  1. GES [Ground Engineering System] test site preparation

    International Nuclear Information System (INIS)

    Cox, C.M.; Mahaffey, M.K.; Miller, W.C.; Schade, A.R.; Toyoda, K.G.

    1987-10-01

    Activities are under way at Hanford to convert the 309 containment building and its associated service wing to a nuclear test facility for the Ground Engineering System (GES) test. Conceptual design is about 80% complete, encompassing facility modifications, a secondary heat transport system, a large vacuum system, a test article cell and handing system, control and data handling systems, and safety andl auxiliary systems. The design makes extensive use of existing equipment to minimize technical risk and cost. Refurbishment of this equipment is 25% complete. Cleanout of some 1000 m 3 of equipment from the earlier reactor test in the facility is 85% complete. An Environmental Assessment was prepared and revised to incorporate Department of Energy (DOE) comments. It is now in the DOE approval chain, where a Finding of No Significant Impact is expected. During the next year, definite design will be well advanced, long-lead procurements will be initiated, construction planning will be completed, an operator training plan will be prepared, and the site (preliminary) safety analysis report will be drafted

  2. Acceptance Test Report for the high pressure water jet system canister cleaning fixture

    Energy Technology Data Exchange (ETDEWEB)

    Burdin, J.R.

    1995-10-25

    This Acceptance Test confirmed the test results and recommendations, documented in WHC-SD-SNF-DTR-001, Rev. 0 Development Test Report for the High Pressure Water Jet System Nozzles, for decontaminating empty fuel canisters in KE-Basin. Optimum water pressure, water flow rate, nozzle size and overall configuration were tested

  3. Acceptability of routine offer of HIV testing (opt-out approach) among ...

    African Journals Online (AJOL)

    Background: With the introduction of the opt out HIV testing policy in Ghana, the HIV test is offered routinely to all pregnant women unless they decline testing. Objective: To assess acceptability of the routine offer of HIV testing antenatal clinic (ANC) clients in the Wa municipality, Ghana. Design: Cross-sectional study of 270 ...

  4. 242-A MCS Logic Acceptance Test Report for Year 2000 Upgrade

    International Nuclear Information System (INIS)

    TEATS, M.C.

    1999-01-01

    242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. Testing was performed per test procedure HNF-3568. There were no unresolved exceptions. The system responded correctly to all testing and meets the requirements to operate the 242-A This report documents the acceptance test results for the Evaporator facility

  5. Acceptance Test Report for the high pressure water jet system canister cleaning fixture

    International Nuclear Information System (INIS)

    Burdin, J.R.

    1995-01-01

    This Acceptance Test confirmed the test results and recommendations, documented in WHC-SD-SNF-DTR-001, Rev. 0 Development Test Report for the High Pressure Water Jet System Nozzles, for decontaminating empty fuel canisters in KE-Basin. Optimum water pressure, water flow rate, nozzle size and overall configuration were tested

  6. 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

  7. Understanding patient acceptance and refusal of HIV testing in the emergency department

    Directory of Open Access Journals (Sweden)

    Christopoulos Katerina A

    2012-01-01

    Full Text Available ABSTRACT Background Despite high rates of patient satisfaction with emergency department (ED HIV testing, acceptance varies widely. It is thought that patients who decline may be at higher risk for HIV infection, thus we sought to better understand patient acceptance and refusal of ED HIV testing. Methods In-depth interviews with fifty ED patients (28 accepters and 22 decliners of HIV testing in three ED HIV testing programs that serve vulnerable urban populations in northern California. Results Many factors influenced the decision to accept ED HIV testing, including curiosity, reassurance of negative status, convenience, and opportunity. Similarly, a number of factors influenced the decision to decline HIV testing, including having been tested recently, the perception of being at low risk for HIV infection due to monogamy, abstinence or condom use, and wanting to focus on the medical reason for the ED visit. Both accepters and decliners viewed ED HIV testing favorably and nearly all participants felt comfortable with the testing experience, including the absence of counseling. While many participants who declined an ED HIV test had logical reasons, some participants also made clear that they would prefer not to know their HIV status rather than face psychosocial consequences such as loss of trust in a relationship or disclosure of status in hospital or public health records. Conclusions Testing for HIV in the ED as for any other health problem reduces barriers to testing for some but not all patients. Patients who decline ED HIV testing may have rational reasons, but there are some patients who avoid HIV testing because of psychosocial ramifications. While ED HIV testing is generally acceptable, more targeted approaches to testing are necessary for this subgroup.

  8. 26. willingness to accept hiv testing among caretakers with a child

    African Journals Online (AJOL)

    Esem

    women and 11% of men have ever been tested for HIV. With all these efforts in place the .... important strategy in determining the gap in knowledge and its relationship with ... salary, education, and religion to be associated with accepting VCT ...

  9. Acceptance/Operational Test Report for Tank 241-AN-104 camera and camera purge control system

    International Nuclear Information System (INIS)

    Castleberry, J.L.

    1995-11-01

    This Acceptance/Operational Test Procedure (ATP/OTP) will document the satisfactory operation of the camera purge panel, purge control panel, color camera system and associated control components destined for installation. The final acceptance of the complete system will be performed in the field. The purge panel and purge control panel will be tested for its safety interlock which shuts down the camera and pan-and-tilt inside the tank vapor space during loss of purge pressure and that the correct purge volume exchanges are performed as required by NFPA 496. This procedure is separated into seven sections. This Acceptance/Operational Test Report documents the successful acceptance and operability testing of the 241-AN-104 camera system and camera purge control system

  10. Void fraction instrument software, Version 1,2, Acceptance test report

    International Nuclear Information System (INIS)

    Gimera, M.

    1995-01-01

    This provides the report for the void fraction instrument acceptance test software Version 1.2. The void fraction will collect data that will be used to calculate the quantity of gas trapped in waste tanks

  11. Nevada Test Site Resource Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    The Nevada Test Site (NTS) Resource Management Plan (RMP) describes the NTS Stewardship Mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. The NTS Stewardship Mission is to manage the land and facilities at the NTS as a unique and valuable national resource. The RMP has defined goals for twelve resource areas based on the principles of ecosystem management. These goals were established using an interdisciplinary team of DOE/NV resource specialists with input from surrounding land managers, private parties, and representatives of Native American governments. The overall goal of the RMP is to facilitate improved NTS land use management decisions within the Great Basin and Mojave Desert ecoregions.

  12. Test report for the run-in acceptance testing of the hydrogen mitigation retrieval Pump-3

    International Nuclear Information System (INIS)

    Berglin, B.G.; Nash, Ch.R.

    1997-01-01

    This report will provide the findings of the demonstration test conducted on the Double-Shell Tank (DST) 241-SY-101 HMR Pump-3 in accordance with WHC-SDWM-TP-434 ''Test plan for run-in acceptance testing of hydrogen mitigation/retrieval pump-3'' at the 400 Area Maintenance and Storage Facility (MASF) building from 7 June 1996 through 30 July 1996 per work package 4A-96-92/W. The DST 241-SY-101 hydrogen mitigation retrieval Pump-3 is a 200-HP submersible electric driven pump that has been modified for use in the DST 241-SY-101 containing mixed waste located in the 200W area. The pump has a motor driven rotation mechanism that allows the pump column to rotate through 355 degree. Prior to operation, pre-operational checks were performed which included loop calibration grooming and alignment of instruments, learning how plumb HMR-3 assembly hung in a vertical position and bump test of the motor to determine rotation direction. The pump was tested in the MASF Large Diameter Cleaning Vessel (LDCV) with process water at controlled temperatures and levels. In addition, the water temperature of the cooling water to the motor oil heat exchanger was recorded during testing. A 480-volt source powered a Variable Frequency Drive (VFD). The VFD powered the pump at various frequencies and voltages to control speed and power output of the pump. A second VFD powered the oil cooling pump. A third VFD was not available to operate the rotational drive motor during the 72 hour test, so it was demonstrated as operational before and after the test. A Mini Acquisition and Control System (Mini-DACS) controls pump functions and monitoring of the pump parameters. The Mini-DACS consists of three computers, software and some Programmable Logic Controllers (PLC). Startup and shutdown of either the pump motor or the oil cooling pump can be accomplished by the Mini-DACS. When the pump was in operation, the Mini-DACS monitors automatically collects data electronically. However, some required data

  13. Establishment of a radiotherapy service with a linear accelerator (photons): acceptance tests, dosimetry and quality control

    International Nuclear Information System (INIS)

    Berdaky, Mafalda Feliciano

    2000-01-01

    This work presents the operational part of the final process of the establishment of a radiotherapy service with a linear accelerator (6 MeV photon beams), including the acceptance tests, commissioning tests and the implementation of a quality control program through routine mechanical and radiation tests. All acceptance tests were satisfactory, showing results below the allowed limits of the manufacturer, the commissioning tests presented results within those of the international recommendations. The quality control program was performed during 34 months and showed an excellent stability of this accelerator. (author)

  14. Risk analysis for new nuclear waste sites: Will it generate public acceptance?

    International Nuclear Information System (INIS)

    Inhaber, H.

    1993-01-01

    This report discusses public acceptance of radioactive waste facilities and what seems to be increasingly militant stances against such facilities. The role of risk assessment in possibly enhancing public acceptance is investigated

  15. Fueled viking generator S/N 106 acceptance vibration test report

    International Nuclear Information System (INIS)

    Anderson, C.; Brewer, C.O.; Abrahamson, S.G.

    1976-01-01

    The Viking Generator S/N 106 was vibrated to the Teledyne Isotope Flight Acceptance Schedule (Random Only) with no deviation from normal generator functional output. Radiographic analysis and power tests before and after the vibration test indicated no change in the condition of the generator. The work was conducted in the Alpha Fuels Environmental Test Facility at Mound Laboratory

  16. On the comparability of acceptance tests for concrete by operation characteristics

    International Nuclear Information System (INIS)

    Rackwitz, R.

    1978-01-01

    The purely statistical aspect of acceptance tests can be estimated by means of operation characteristics, the position and steepness of which determine the probability for acceptance or rejection of offered loads. For negative decisions in concrete checking there will be, as a rule, an after-check in normal quality control. The operation characteristics with after-check valid for DIN 1045, DIN 1084, and DIN 1048 are set up. Complete comparability of different acceptance tests by means of the operation characteristic can only be achieved if the different sampling rates and the number of decisions are also included in the consideration. Proposals for improving the acceptance tests for concrete are presented. (orig.) [de

  17. Cross-Site Transfer System at Hanford: long-term strategy for waste acceptance

    International Nuclear Information System (INIS)

    Shekarriz, A.; Onishi, Y.; Smith, P.A.; Sterner, M.; Rector, D.R.; Virden, J.

    1997-02-01

    This report summarizes results of a technical panel review of the current methodology for accepting waste for transport through the Hanford Replacement Cross-Site Transfer System (RCSTS), which was constructed to replace the existing pipelines that hydraulically connect the 200 West and 200 East areas. This report is a complement to an existing document (Hudson 1996); the methodology proposed in that document was refined based on panel recommendations. The refinements were focused around predicting and preventing the 3 main modes suspected of plugging the existing CSTS: precipitation, gelation, particle dropout/settling. The proposed analysis will require integration of computer modeling and laboratory experiments to build a defensible case for transportability of a proposed slurry composition for a given tank. This will be validated by recirculating actual tank waste, in-tank and in-farm, prior to transport. The panel's recommendation was that the probability of success of waste transfer would be greatly improved by integrating the predictive analysis with real-time control during RCSTS operation. The methodology will be optimized

  18. Testing the ecological site group concept

    Science.gov (United States)

    The 2016 “Ecological Sites for Landscape Management” special issue of Rangelands recommended an update to our thinking of Ecological Sites, suggesting that in our desire to make Ecological Sites more quantitative, we abandoned consideration of Ecological Sites’ spatial context. In response, Ecologic...

  19. Neutron absorber qualification and acceptance testing from the designer's perspective

    Energy Technology Data Exchange (ETDEWEB)

    Bracey, W. [Transnuclear, Inc, Hawthorne, NY (United States); Chiocca, R. [Cogema Logistics, St. Quentin en Yvelines (France)

    2004-07-01

    Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3{sigma}. The original and current bases for the reduced {sup 10}B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and

  20. An Exploration of Social Networking Sites (SNS) Adoption in Malaysia Using Technology Acceptance Model (TAM), Theory of Planned Behavior (TPB) And Intrinsic Motivation

    OpenAIRE

    Goh Say Leng; Suddin Lada; Mohd Zulkifli Muhammad; Ag Asri Hj Ag Ibrahim; Tamrin Amboala

    2011-01-01

    The objective of the paper is to explore the factors that encourage students to adopt social network sites (SNS) in Malaysia and to use the study’s findings to develop guidelines for SNS providers on how to maximize the rate of adoption. A conceptual model of Technology Acceptance Model (TAM), Theory of Planned Behaviour (TPB) and intrinsic motivation is proposed and empirically tested in the context of SNS usage. Structural Equation modelling was used on the survey data from 283 university s...

  1. Environmental assessment for double tracks test site, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    1996-04-01

    The U.S. Department of Energy, Nevada Operations Office (DOE/NV), with appropriate approvals from the U.S. Air Force (USAF), proposes to conduct environmental restoration operations at the Double Tracks test site located on the Nellis Air Force Range (NAFR) in Nye County, Nevada. This environmental assessment (EA) evaluates the potential environmental consequences of four alternative actions for conducting the restoration operation and of the no action alternative. The EA also identifies mitigation measures, where appropriate, designed to protect natural and cultural resources and reduce impacts to human health and safety. The environmental restoration operation at the Double Tracks test site would serve two primary objectives. First, the proposed work would evaluate the effectiveness of future restoration operations involving contamination over larger areas. The project would implement remediation technology options and evaluate how these technologies could be applied to the larger areas of contaminated soils on the Nevada Test Site (NTS), the Tonopah Test Range (TTR), and the NAFR. Second, the remediation would provide for the removal of plutonium contamination down to or below a predetermined level which would require cleanup of 1 hectare (ha) (2.5 acres), for the most likely case, or up to 3.0 ha (7.4 acres) of contaminated soil, for the upper bounding case

  2. Hydrogeologic testing strategy for the Basalt Waste Isolation Project site

    International Nuclear Information System (INIS)

    Logsdon, M.J.; Verma, T.R.

    1984-01-01

    At the time of licensing for a proposed deep geologic repository for high-level nuclear waste, the Department of Energy (DOE) has the responsibility to present and defend a complete licensing/performance assessment of the geologic repository system. As part of its responsibilities, the Nuclear Regulatory Commission (NRC) staff will be required to perform an independent assessment of the groundwater flow system with respect to the technical criteria of 10 Code of Federal Regulations (CFR) Part 60. Specifically, the staff expects to use mathematical models to predict pre-emplacement and post-emplacement groundwater flow paths and travel times. These predictive assessments will be used to reach findings on compliance with the proposed EPA Standards (10 CFR 60.112), which apply to post-emplacement groundwater travel time along the path of likely radionuclide travel (10 CFR 60.113(2)). Predictive modeling of groundwater flow will require defensible conceptual models of the flow system, defensible boundary conditions, and defensible values of hydraulic parameters. The purpose fo this technical position is to provide guidance to DOE on an approach that the NRC staff considers acceptable in determining what hydrogeologic testing (including types of tests, scale of tests, and number of tests) at the Hanford site will be required to produce the hydraulic data necessary and sufficient to perform rigorous, quantitative modeling to support predictions of repository performance. 2 figures

  3. Interpreting Results from the Standardized UXO Test Sites

    National Research Council Canada - National Science Library

    May, Michael; Tuley, Michael

    2007-01-01

    ...) and the Environmental Security Technology Certification Program (ESCTP) to complete a detailed analysis of the results of testing carried out at the Standardized Unexploded Ordnance (UXO) Test Sites...

  4. Standard-B auto grab sampler hydrogen monitoring system, Acceptance Test Report

    International Nuclear Information System (INIS)

    Lott, D.T.

    1995-01-01

    Project W-369, Watch List Tank Hydrogen Monitors, installed a Standard-C Hydrogen Monitoring System (SHMS) on the Flammable gas waste tank AN-104. General Support Projects (8K510) was support by Test Engineering (7CH30) in the performance of the Acceptance Test Procedures (ATP) to qualify the SHMS cabinets on the waste tank. The ATP's performance was controlled by Tank Farm work package. This completed ATP is transmitted by EDT-601748 as an Acceptance Test Report (ATR) in accordance with WHC-6-1, EP 4.2 and EP 1.12

  5. Radiation exposures from nuclear tests at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Dunning, G M

    1958-12-01

    A summary of the pertinent data on radiation exposures from nuclear tests in Nevada is presented. The data are presented in categories of external ..gamma.. radiation, activity concentrations in air, and activity concentrations in water. Methods used to estimate exposure and to evaluate data are described. The data are tabulated. The maximum external exposure was 7 to 8 r for 15 persons involved. In terms of relatively large populations, the average exposure for the 1,000,000 people living nearest the site was at the rate of 1/2 r/30 yr. The highest concentration of fallout activity in the air was about 1.3 ..mu..c/m/sup 3/ averaged over the 30 hr that the activity was present in significant quantities. The highest concentration of fallout activity in a potential drinking water supply was about 1.4 x 10/sup -/ ..mu..c/me extrapolated to D + 3 days. Evaluation of these data is given.

  6. Nevada Test Site Site Treatment Plan. Revision 2

    International Nuclear Information System (INIS)

    1996-03-01

    Treatment Plans (STPS) are required for facilities at which the US Department of Energy (DOE) or stores mixed waste, defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act and a radioactive material subject to the Atomic Energy Act. On April 6, 1993, DOE published a Federal Register notice (58 FR 17875) describing its proposed process for developing the STPs in three phases including a Conceptual, a Draft, and a Proposed Site Treatment Plan (PSTP). All of the DOE Nevada Operations Office STP iterations have been developed with the state of Nevada's input. The options and schedules reflect a ''bottoms-up'' approach and have been evaluated for impacts on other DOE sites, as well as impacts to the overall DOE program. Changes may have occurred in the preferred option and associated schedules between the PSTP, which was submitted to the state of Nevada and US Environmental Protection Agency April 1995, and the Final STP (hereafter referred to as the STP) as treatment evaluations progressed. The STP includes changes that have occurred since the submittal of the PSTP as a result of state-to-state and DOE-to-state discussions

  7. 241-AZ-101 Waste Tank Color Video Camera System Shop Acceptance Test Report

    International Nuclear Information System (INIS)

    WERRY, S.M.

    2000-01-01

    This report includes shop acceptance test results. The test was performed prior to installation at tank AZ-101. Both the camera system and camera purge system were originally sought and procured as a part of initial waste retrieval project W-151

  8. 241-AZ-101 Waste Tank Color Video Camera System Shop Acceptance Test Report

    Energy Technology Data Exchange (ETDEWEB)

    WERRY, S.M.

    2000-03-23

    This report includes shop acceptance test results. The test was performed prior to installation at tank AZ-101. Both the camera system and camera purge system were originally sought and procured as a part of initial waste retrieval project W-151.

  9. Acceptability of Sexually Transmitted Infection Testing Using Self-Collected Vaginal Swabs among College Women

    Science.gov (United States)

    Fielder, Robyn L.; Carey, Kate B.; Carey, Michael P.

    2013-01-01

    Objective: To assess the acceptability of sexually transmitted infection (STI) testing using self-collected vaginal swabs (SCVS) among college women. Participants: First-year female students ("N" = 483). Methods: Participants were offered free testing for 3 STIs using SCVS in April 2010 and later completed a survey regarding their…

  10. Enraf series 854 Advanced Technology Gauge (ATG) acceptance test procedure. Revision 3

    International Nuclear Information System (INIS)

    Barnes, G.A.

    1995-01-01

    This procedure provides acceptance testing for Enraf Series 854 level gauges used to monitor levels in Hanford Waste Storage Tanks. The test will verify that the gauge functions according to the manufacturer's instructions and specifications and is properly setup prior to being delivered to the tank farm area

  11. Understanding Student Teachers' Behavioural Intention to Use Technology: Technology Acceptance Model (TAM) Validation and Testing

    Science.gov (United States)

    Wong, Kung-Teck; Osman, Rosma bt; Goh, Pauline Swee Choo; Rahmat, Mohd Khairezan

    2013-01-01

    This study sets out to validate and test the Technology Acceptance Model (TAM) in the context of Malaysian student teachers' integration of their technology in teaching and learning. To establish factorial validity, data collected from 302 respondents were tested against the TAM using confirmatory factor analysis (CFA), and structural equation…

  12. Delinquency and Peer Acceptance in Adolescence: A Within-Person Test of Moffitt's Hypotheses

    Science.gov (United States)

    Rulison, Kelly L.; Kreager, Derek A.; Osgood, D. Wayne

    2014-01-01

    We tested 2 hypotheses derived from Moffitt's (1993) taxonomic theory of antisocial behavior, both of which are central to her explanation for the rise in delinquency during adolescence. We tested whether persistently delinquent individuals become more accepted by their peers during adolescence and whether individuals who abstain from delinquent…

  13. System acceptance and operability test report for the RMCS exhauster C on flammable gas tanks

    International Nuclear Information System (INIS)

    Waldo, E.J.

    1998-01-01

    This test report documents the completion of acceptance and operability testing of the rotary mode core sampling (RMCS) exhauster C, as modified for use as a major stack (as defined by the Washington State Department of Health) on flammable gas tanks

  14. Pill testing or drug checking in Australia: Acceptability of service design features.

    Science.gov (United States)

    Barratt, Monica J; Bruno, Raimondo; Ezard, Nadine; Ritter, Alison

    2018-02-01

    This study aimed to determine design features of a drug-checking service that would be feasible, attractive and likely to be used by Australian festival and nightlife attendees. Web survey of 851 Australians reporting use of psychostimulants and/or hallucinogens and attendance at licensed venues past midnight and/or festivals in the past year (70% male; median age 23 years). A drug-checking service located at festivals or clubs would be used by 94%; a fixed-site service external to such events by 85%. Most (80%) were willing to wait an hour for their result. Almost all (94%) would not use a service if there was a possibility of arrest, and a majority (64%) would not use a service that did not provide individual feedback of results. Drug-checking results were only slightly more attractive if they provided comprehensive quantitative results compared with qualitative results of key ingredients. Most (93%) were willing to pay up to $5, and 68% up to $10, per test. One-third (33%) reported willingness to donate a whole dose for testing: they were more likely to be male, younger, less experienced, use drugs more frequently and attend venues/festivals less frequently. In this sample, festival- or club-based drug-checking services with low wait times and low cost appear broadly attractive under conditions of legal amnesty and individualised feedback. Quantitative analysis of ecstasy pills requiring surrender of a whole pill may appeal to a minority in Australia where pills are more expensive than elsewhere. [Barratt MJ, Bruno R, Ezard N, Ritter A. Pill testing or drug checking in Australia: Acceptability of service design features. Drug Alcohol Rev 2017;00:000-000]. © 2017 Australasian Professional Society on Alcohol and other Drugs.

  15. Nevada Test Site, site treatment plan 1999 annual update

    International Nuclear Information System (INIS)

    1999-03-01

    A Site Treatment Plan (STP) is required for facilities at which the US Department of Energy Nevada Operations Office (DOE/NV) generates or stores mixed waste (MW), defined by the Federal Facility Compliance Act (FFC Act) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act (RCRA) and a radioactive material subject to the Atomic Energy Act. This STP was written to identify specific treatment facilities for treating DOE/NV generated MW and provides proposed implementation schedules. This STP was approved by the Nevada Division of Environmental Protection (NDEP) and provided the basis for the negotiation and issuance of the FFC Act Consent Order (CO) dated March 6, 1996, and revised June 15, 1998. The FFC Act CO sets forth stringent regulatory requirements to comply with the implementation of the STP

  16. Project W-320 acceptance test report for AY-farm electrical distribution

    International Nuclear Information System (INIS)

    Bevins, R.R.

    1998-01-01

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the AY-Farm Electrical Distribution System functions as required by the design criteria. This test is divided into three parts to support the planned construction schedule; Section 8 tests Mini-Power Pane AY102-PPI and the EES; Section 9 tests the SSS support systems; Section 10 tests the SSS and the Multi-Pak Group Control Panel. This test does not include the operation of end-use components (loads) supplied from the distribution system. Tests of the end-use components (loads) will be performed by other W-320 ATPs

  17. Local tolerance testing under REACH: Accepted non-animal methods are not on equal footing with animal tests.

    Science.gov (United States)

    Sauer, Ursula G; Hill, Erin H; Curren, Rodger D; Raabe, Hans A; Kolle, Susanne N; Teubner, Wera; Mehling, Annette; Landsiedel, Robert

    2016-07-01

    In general, no single non-animal method can cover the complexity of any given animal test. Therefore, fixed sets of in vitro (and in chemico) methods have been combined into testing strategies for skin and eye irritation and skin sensitisation testing, with pre-defined prediction models for substance classification. Many of these methods have been adopted as OECD test guidelines. Various testing strategies have been successfully validated in extensive in-house and inter-laboratory studies, but they have not yet received formal acceptance for substance classification. Therefore, under the European REACH Regulation, data from testing strategies can, in general, only be used in so-called weight-of-evidence approaches. While animal testing data generated under the specific REACH information requirements are per se sufficient, the sufficiency of weight-of-evidence approaches can be questioned under the REACH system, and further animal testing can be required. This constitutes an imbalance between the regulatory acceptance of data from approved non-animal methods and animal tests that is not justified on scientific grounds. To ensure that testing strategies for local tolerance testing truly serve to replace animal testing for the REACH registration 2018 deadline (when the majority of existing chemicals have to be registered), clarity on their regulatory acceptance as complete replacements is urgently required. 2016 FRAME.

  18. Cytogenetic Monitoring of Mammals of Semipalatinsk Test Site

    International Nuclear Information System (INIS)

    Zhapbasov, R.Zh.; Tusupbaev, V.I.; Karimbaeva, K.S.; Seisebaev, A.T.; Nurgalieva, K.G.; Chenal, C.

    1998-01-01

    The cytogenetic monitoring of the natural populations of mammals living under conditions of environment radioactive contamination is the simplest method to study the genetic consequences of nuclear tests. This work presents the preliminary results of the cytogenetic monitoring of the natural populations of rodents (Allactaga maior Kerr., Allactaga saltafor Eversm., Citellus erytrogenus Brandt) and domestic sheep (Ovis aries). The exposure of gonads is considered to be the most hazardous among the consequences of the chronic ionizing exposure since the exposure of gonads can cause not only somatic damages but also hereditary ones transferring to the farther generations, The genetic damage assessment of rodent reproductive cells was performed using the morphological test for abnormal form of the sperm head. It is generally accepted, that spermatogenesis disorders, which result in abnormal spermatozoa, are bound to the genetic disturbances during mitotic and meiotic division stages of male sex cells. The analysis of data obtained shows that the rodent males living on the radioactive contaminated sites (Balapan, Degelen) have the higher numbers of abnormal spermatozoa. So, the Allactaga maior taken from the sites with the gamma background of 250 μr/h showed the frequency of abnormal spermatozoa within 48.27 - 62.73 %. This value for the control animals from the gamma background of 11 - 16 μr/h did not exceed 5.8 %. The most objective and sensitive method for assessment of environmental contamination genetic consequences for the natural populations is to determine the damages of the cell genetic apparatus, e. g. the frequency of the visible changes in chromosome number and structure. The cytogenetic study of animals showed that the significant number of marrow cells of rodents and sheep living on the technical fields of the Test Site are the metaphase cells with polyploid (0.98 - 3.50 %) and aneuploidy (11.03 -19.72 %) chromosomal sets. There were also found the

  19. Structural geology report: Spent Fuel Test - Climax Nevada Test Site

    International Nuclear Information System (INIS)

    Wilder, D.G.; Yow, J.L. Jr.

    1984-10-01

    We performed underground mapping and core logging in the Climax Stock, a granitic intrusive at the Nevada Test Site, as part of a major field test to determine the feasibility of using granitic or crystalline rock for the underground storage of spent fuel from a nuclear reactor. This mapping and logging identified more than 2500 fractures, over 1500 of which were described in enough detail to allow statistical analyses and orientation studies to be performed. We identified eight joint sets, three major shear sets, and a fault zone within the Spent Fuel Test - Climax (SFT-C) portion of the Stock. Joint sets identified within the SFT-C and elsewhere in the Stock correlated well. The orientations of joint sets identified by other investigators were consistent with our findings, indicating that the joint sets are persistent and have a relatively uniform orientation throughout a major portion of the Stock. The one joint set not seen elsewhere in the Stock is healed and the wall rock is altered, implying that healed joints were not included in the mapping criteria used by other investigators. The shear sets were distinguished from the joint sets by virtue of crushed minerals, continuous clay infilling, and other evidences of shearing, and from faults by the lack of offsetting. Previous investigators working mainly in the Pile Driver Drifts identified two of the shear sets. The third set, being nearly parallel to these Drifts had not been identified previously. The fault zone identified at the far (Receiving Room) end of the project is oriented approximately N45 0 E-75 0 SE, similar to both the Boundary and Shaft Station Faults. We have, therefore, concluded that the Receiving Room Fault is one of a series of normal faults that occur within the Climax Stock and that are possibly related, in both age and genesis, to the Boundary Fault. 52 refs., 26 figs., 11 tabs

  20. Multiple Site Damage in Flat Panel Testing

    National Research Council Canada - National Science Library

    Shrage, Daniel

    2000-01-01

    This report aimed to experimentally verify analytical models that predict the residual strength of representative aircraft structures, such as wide panels, that are subjected to Multiple Site Damage (MSD...

  1. 105 K east ion exchange and cartridge filter restart instrumentation acceptance test report

    International Nuclear Information System (INIS)

    Whitehurst, R.

    1996-01-01

    Acceptance Test Report following the completion of ATP-012 for the 105KE CP-A and CP-A Computer and PLC Panels. The test was conducted from 11/13/95 to 12/11/95. Three test discrepancies were generated during the ATP and all were dispositioned and closed. All sections were completed except Section 5.9 which was deleted per ECN 190556

  2. KE basin recirculation/skimmer/IX systems restart acceptance test report

    International Nuclear Information System (INIS)

    Derosa, D.C.

    1996-01-01

    The 105 KE Basin Recirculation System and Skimmer Loop have been upgraded to provide the flexibility to run the Ion Exchange Modules on either system to support spent fuel removal for the Spent Nuclear Fuel Project. This Acceptance Test Report Provides the documentation of the leak Testing for the construction work associated with the IXM inlet and outlet piping, places the cartridge filters back in service and provides the functional testing of the IXM's on the recirculation and skimmer systems

  3. MAC Version 3.3, MBA Version 1.3 acceptance test summary report

    International Nuclear Information System (INIS)

    Russell, V.K.

    1994-01-01

    The K Basins Materials Accounting (MAC) and Materials Balance (MBA) programs had the Paradox Code Cleanup ATP run to check out the systems. This report describes the results of the test and provides the signoff sheets associated with the testing. The Acceptance Test results indicate that the MAC and MBA systems are ready for operation using the cleaned up code. The final codes were removed to the production space on the customer server on April 15th

  4. Acceptance sampling for attributes via hypothesis testing and the hypergeometric distribution

    Science.gov (United States)

    Samohyl, Robert Wayne

    2017-10-01

    This paper questions some aspects of attribute acceptance sampling in light of the original concepts of hypothesis testing from Neyman and Pearson (NP). Attribute acceptance sampling in industry, as developed by Dodge and Romig (DR), generally follows the international standards of ISO 2859, and similarly the Brazilian standards NBR 5425 to NBR 5427 and the United States Standards ANSI/ASQC Z1.4. The paper evaluates and extends the area of acceptance sampling in two directions. First, by suggesting the use of the hypergeometric distribution to calculate the parameters of sampling plans avoiding the unnecessary use of approximations such as the binomial or Poisson distributions. We show that, under usual conditions, discrepancies can be large. The conclusion is that the hypergeometric distribution, ubiquitously available in commonly used software, is more appropriate than other distributions for acceptance sampling. Second, and more importantly, we elaborate the theory of acceptance sampling in terms of hypothesis testing rigorously following the original concepts of NP. By offering a common theoretical structure, hypothesis testing from NP can produce a better understanding of applications even beyond the usual areas of industry and commerce such as public health and political polling. With the new procedures, both sample size and sample error can be reduced. What is unclear in traditional acceptance sampling is the necessity of linking the acceptable quality limit (AQL) exclusively to the producer and the lot quality percent defective (LTPD) exclusively to the consumer. In reality, the consumer should also be preoccupied with a value of AQL, as should the producer with LTPD. Furthermore, we can also question why type I error is always uniquely associated with the producer as producer risk, and likewise, the same question arises with consumer risk which is necessarily associated with type II error. The resolution of these questions is new to the literature. The

  5. Field testing a soil site field guide for Allegheny hardwoods

    Science.gov (United States)

    S.B. Jones

    1991-01-01

    A site quality evaluation decision model, developed for Allegheny hardwoods on the non-glaciated Allegheny Plateau of Pennsylvania and New York, was field tested by International Paper (IP) foresters and the author, on sites within the region of derivation and on glaciated sites north and west of the Wisconsin drift line. Results from the field testing are presented...

  6. Vacuum Acceptance Tests for the UHV Room Temperature Vacuum System of the LHC during LS1

    CERN Document Server

    Cattenoz, G; Bregliozzi, G; Calegari, D; Gallagher, J; Marraffa, A; Chiggiato, P

    2014-01-01

    During the CERN Large Hadron Collider (LHC) first long shut down (LS1), a large number of vacuum tests are carried out on consolidated or newly fabricated devices. In such a way, the vacuum compatibility is assessed before installation in the UHV system of the LHC. According to the equipment’s nature, the vacuum acceptance tests consist in functional checks, leak test, outgassing rate measurements, evaluation of contaminants by Residual Gas Analysis (RGA), pumping speed measurements and qualification of the H2 sticking probability of Non-Evaporable-Getter (NEG) coating. In this paper, the methods used for the tests and the acceptance criteria are described. A summary of the measured vacuum characteristics for the tested components is also given.

  7. Computer-facilitated rapid HIV testing in emergency care settings: provider and patient usability and acceptability.

    Science.gov (United States)

    Spielberg, Freya; Kurth, Ann E; Severynen, Anneleen; Hsieh, Yu-Hsiang; Moring-Parris, Daniel; Mackenzie, Sara; Rothman, Richard

    2011-06-01

    Providers in emergency care settings (ECSs) often face barriers to expanded HIV testing. We undertook formative research to understand the potential utility of a computer tool, "CARE," to facilitate rapid HIV testing in ECSs. Computer tool usability and acceptability were assessed among 35 adult patients, and provider focus groups were held, in two ECSs in Washington State and Maryland. The computer tool was usable by patients of varying computer literacy. Patients appreciated the tool's privacy and lack of judgment and their ability to reflect on HIV risks and create risk reduction plans. Staff voiced concerns regarding ECS-based HIV testing generally, including resources for follow-up of newly diagnosed people. Computer-delivered HIV testing support was acceptable and usable among low-literacy populations in two ECSs. Such tools may help circumvent some practical barriers associated with routine HIV testing in busy settings though linkages to care will still be needed.

  8. Acceptance test procedure for a portable, self-contained nitrogen supply

    International Nuclear Information System (INIS)

    Kostelnik, A.J.

    1994-01-01

    This Acceptance Test Procedure (ATP) will document compliance with the requirements of WHC-S-0249 Rev. 1 and ECN 606112. The equipment being tested is a Portable, Self-Contained Nitrogen Supply. The unit was purchased as a Design and Fabrication procurement activity. The Functional Test was written by the Seller and is contained in Appendix A. The Functional test will be performed by the Seller with representatives of the Westinghouse Hanford Company performing inspection and witnessing the functional test at the Seller's location

  9. Interim report on flash floods, Area 5 - Nevada Test Site

    International Nuclear Information System (INIS)

    French, R.H.

    1980-09-01

    Examination of the presently available data indicates that consideration must be given to the possibility of flash floods when siting waste management facilities in Area 5 of the Nevada Test Site. 6 figures, 7 tables

  10. Testing Pearl Model In Three European Sites

    Science.gov (United States)

    Bouraoui, F.; Bidoglio, G.

    The Plant Protection Product Directive (91/414/EEC) stresses the need of validated models to calculate predicted environmental concentrations. The use of models has become an unavoidable step before pesticide registration. In this context, European Commission, and in particular DGVI, set up a FOrum for the Co-ordination of pes- ticide fate models and their USe (FOCUS). In a complementary effort, DG research supported the APECOP project, with one of its objective being the validation and im- provement of existing pesticide fate models. The main topic of research presented here is the validation of the PEARL model for different sites in Europe. The PEARL model, actually used in the Dutch pesticide registration procedure, was validated in three well- instrumented sites: Vredepeel (the Netherlands), Brimstone (UK), and Lanna (Swe- den). A step-wise procedure was used for the validation of the PEARL model. First the water transport module was calibrated, and then the solute transport module, using tracer measurements keeping unchanged the water transport parameters. The Vrede- peel site is characterised by a sandy soil. Fourteen months of measurements were used for the calibration. Two pesticides were applied on the site: bentazone and etho- prophos. PEARL predictions were very satisfactory for both soil moisture content, and pesticide concentration in the soil profile. The Brimstone site is characterised by a cracking clay soil. The calibration was conducted on a time series measurement of 7 years. The validation consisted in comparing predictions and measurement of soil moisture at different soil depths, and in comparing the predicted and measured con- centration of isoproturon in the drainage water. The results, even if in good agreement with the measuremens, highlighted the limitation of the model when the preferential flow becomes a dominant process. PEARL did not reproduce well soil moisture pro- file during summer months, and also under-predicted the arrival of

  11. The acceptability, knowledge and perceptions of pregnant women toward HIV Testing in pregnancy at Ilembe District

    Directory of Open Access Journals (Sweden)

    FN Dube

    2008-09-01

    Full Text Available This research study aimed to investigate the acceptability, knowledge and perceptions of pregnant women toward HIV testing in pregnancy in Ilembe District. An exploratory research design guided the study. A systematic random sampling was used to select pregnant women who were attending the ante-natal clinic for the first time in their current pregnancy.

  12. Acceptability of self-collected vaginal samples for HPV testing in an ...

    African Journals Online (AJOL)

    Objective: To evaluate the acceptability of self-collected vaginal samples for HPV testing in women living in rural and urban areas of Madagascar. Materials and methods: Participants were recruited in a health care center (urban group) and smaller affiliated dispensaries (rural group). They were invited to perform ...

  13. Acceptance Test Report for the Modular Automation System (MAS) Manufactured by Honeywell Inc

    International Nuclear Information System (INIS)

    ANDERSON, D.L.

    2000-01-01

    This document details the performance of the acceptance test of the Honeywell MAS Control System for equipment to be installed in gloveboxes HA-20MB and HA-211 at a later date. Equipment that was anticipated included 6 stabilization furnaces, only three and their associated equipment were installed

  14. Integrating Telemedicine for Disaster Response: Testing the Emergency Telemedicine Technology Acceptance Model

    Science.gov (United States)

    Davis, Theresa M.

    2013-01-01

    Background: There is little evidence that technology acceptance is well understood in healthcare. The hospital environment is complex and dynamic creating a challenge when new technology is introduced because it impacts current processes and workflows which can significantly affect patient care delivery and outcomes. This study tested the effect…

  15. Measures of transparency for decommissioning of test site

    International Nuclear Information System (INIS)

    Andrusenko, B. A.; Smirnov, V. G.; Sherbina, A. N.

    1997-01-01

    This paper presents non-traditional directions of activity of the Institute specialists to solve complicated scientific and technical tasks within the framework of observance of international obligations on non-proliferation. In the latest time much attention is paid to the reaching of mutual confidence between sides during a control over the observance of agreements regarding disarmament. How can we demonstrate implementation of agreements to each of both sides, not having leakage of confidential or, so called, 'sensitive' information? That means to ensure 'transparency' of activity, not doing a damage to both sides. It is needed to note that the meaning of the above term can be substantially varied, depending on what field of activity it is used in. For instance, the meaning of the transparency measures adopted in joint program of RFNC and SNL for future control of disassembling of nuclear weapon is represented as ''...measures which can be taken for building of the confidence of both sides, assuring that these sides reach mutual understanding, and one side can inspect activity of another side as well as its outcomes which are a part of lifetime cycle of nuclear weapon. We consider this meaning to be acceptable for objectives and principles indicated in joint Russian-Kazakhstani activity on decommisioning of the test site. Hereafter in this paper we will use terminology on the transparency measures which is adopted for future control of the nuclear weapon disassembling. The transparency measures application distates a necessity of development of documentation drawing system of individual procedures and operations, which has 'sensitive' information and to which some transporancy measures, and be in accord with the existent legislation of Russia and Kazakhstan. There is an example of nuclear device (ND) destruction in a tunnel 108 located on the former Semipalatinsk test site, that represents experience gained by specialists of RFNC-RITP in the field of the

  16. Public perception and acceptance of the siting of nuclear waste facilities in seven countries

    International Nuclear Information System (INIS)

    Numark, N.J.; Paige, H.W.; Wonder, E.F.

    1989-09-01

    This report was prepared by ERC Environmental and Energy Services Co. (ERCE) on behalf of the Pacific Northwest Laboratory (PNL) and the US Department of Energy (DOE) between February and August 1989. It updates previous reports prepared by ERCE on public acceptance of waste management activities in foreign countries. The report is intended to serve as an aid in understanding experiences with public acceptance of waste activities in foreign countries, and thereby benefit US efforts with respect to public acceptance based on lessons learned abroad. Seven countries are addressed in the report: Belgium, the Federal Republic of Germany, France, Japan, Sweden, Switzerland, and the United Kingdom. The information provided in this report was obtained both from direct interviews of the responsible waste management officials in the seven countries surveyed and from source documents provided by these individuals

  17. Current use and acceptability of novel diagnostic tests for active tuberculosis: a worldwide survey

    Directory of Open Access Journals (Sweden)

    Massimo Amicosante

    Full Text Available ABSTRACT Objective: To determine the current use and potential acceptance (by tuberculosis experts worldwide of novel rapid tests for the diagnosis of tuberculosis that are in line with World Health Organization target product profiles. Methods: A multilingual survey was disseminated online between July and November of 2016. Results: A total of 723 individuals from 114 countries responded to the survey. Smear microscopy was the most commonly used rapid tuberculosis test (available to 90.9% of the respondents, followed by molecular assays (available to 70.7%. Only a small proportion of the respondents in middle- and low-income countries had access to interferon-gamma-release assays. Serological and lateral flow immunoassays were used by more than a quarter (25.4% of the respondents. Among the respondents who had access to molecular tests, 46.7% were using the Xpert assay overall, that proportion being higher in lower middle-income countries (55.6% and low-income countries (76.6%. The data also suggest that there was some alignment of pricing for molecular assays. Respondents stated they would accept novel rapid tuberculosis tests if available, including molecular assays (acceptable to 86.0% or biomarker-based serological assays (acceptable to 81.7%. Simple biomarker-based assays were more commonly deemed acceptable in middle- and low-income countries. Conclusions: Second-generation molecular assays have become more widely available in high- and low-resource settings. However, the development of novel rapid tuberculosis tests continues to be considered important by tuberculosis experts. Our data also underscore the need for additional training and education of end users.

  18. Nevada Test Site Resource Management Plan: Annual summary, January 2000

    International Nuclear Information System (INIS)

    2000-01-01

    The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan

  19. Nevada Test Site Resource Management Plan: Annual summary, January 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-01-01

    The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan.

  20. ASME N510 test results for Savannah River Site AACS filter compartments

    Energy Technology Data Exchange (ETDEWEB)

    Paul, J.D.; Punch, T.M. [Westinghouse Savannah River Company, Aiken, SC (United States)

    1995-02-01

    The K-Reactor at the Savannah River Site recently implemented design improvements for the Airborne Activity Confinement System (AACS) by procuring, installing, and testing new Air Cleaning Units, or filter compartments, to ASME AG-11, N509, and N510 requirements. Specifically, these new units provide documentable seismic resistance to a Design Basis Accident earthquake, provide 2 inch adsorber beds with 0.25 second residence time, and meet all AG-1, N509, and N510 requirements for testability and maintainability. This paper presents the results of the Site acceptance testing and discusses an issue associated with sample manifold qualification testing.

  1. Acceptance Sampling Plans Based on Truncated Life Tests for Sushila Distribution

    Directory of Open Access Journals (Sweden)

    Amer Ibrahim Al-Omari

    2018-03-01

    Full Text Available An acceptance sampling plan problem based on truncated life tests when the lifetime following a Sushila distribution is considered in this paper. For various acceptance numbers, confidence levels and values of the ratio between fixed experiment time and particular mean lifetime, the minimum sample sizes required to ascertain a specified mean life were found. The operating characteristic function values of the suggested sampling plans and the producer’s risk are presented. Some tables are provided and the results are illustrated by an example of a real data set.

  2. Acceptance test procedure for K basins dose reduction project clean and coat equipment

    International Nuclear Information System (INIS)

    Creed, R.F.

    1996-01-01

    This document is the Acceptance Test Procedure (ATP) for the clean and coat equipment designed by Oceaneering Hanford, Inc. under purchase order MDK-XVC-406988 for use in the 105 K East Basin. The ATP provides the guidelines and criteria to test the equipment's ability to clean and coat the concrete perimeter, divider walls, and dummy elevator pit above the existing water level. This equipment was designed and built in support of the Spent Nuclear Fuel, Dose Reduction Project. The ATP will be performed at the 305 test facility in the 300 Area at Hanford. The test results will be documented in WHC-SD-SNF-ATR-020

  3. Patients' Acceptance of Smartphone Health Technology for Chronic Disease Management: A Theoretical Model and Empirical Test.

    Science.gov (United States)

    Dou, Kaili; Yu, Ping; Deng, Ning; Liu, Fang; Guan, YingPing; Li, Zhenye; Ji, Yumeng; Du, Ningkai; Lu, Xudong; Duan, Huilong

    2017-12-06

    Chronic disease patients often face multiple challenges from difficult comorbidities. Smartphone health technology can be used to help them manage their conditions only if they accept and use the technology. The aim of this study was to develop and test a theoretical model to predict and explain the factors influencing patients' acceptance of smartphone health technology for chronic disease management. Multiple theories and factors that may influence patients' acceptance of smartphone health technology have been reviewed. A hybrid theoretical model was built based on the technology acceptance model, dual-factor model, health belief model, and the factors identified from interviews that might influence patients' acceptance of smartphone health technology for chronic disease management. Data were collected from patient questionnaire surveys and computer log records about 157 hypertensive patients' actual use of a smartphone health app. The partial least square method was used to test the theoretical model. The model accounted for .412 of the variance in patients' intention to adopt the smartphone health technology. Intention to use accounted for .111 of the variance in actual use and had a significant weak relationship with the latter. Perceived ease of use was affected by patients' smartphone usage experience, relationship with doctor, and self-efficacy. Although without a significant effect on intention to use, perceived ease of use had a significant positive influence on perceived usefulness. Relationship with doctor and perceived health threat had significant positive effects on perceived usefulness, countering the negative influence of resistance to change. Perceived usefulness, perceived health threat, and resistance to change significantly predicted patients' intentions to use the technology. Age and gender had no significant influence on patients' acceptance of smartphone technology. The study also confirmed the positive relationship between intention to use

  4. Patients’ Acceptance of Smartphone Health Technology for Chronic Disease Management: A Theoretical Model and Empirical Test

    Science.gov (United States)

    Dou, Kaili; Yu, Ping; Liu, Fang; Guan, YingPing; Li, Zhenye; Ji, Yumeng; Du, Ningkai; Lu, Xudong; Duan, Huilong

    2017-01-01

    Background Chronic disease patients often face multiple challenges from difficult comorbidities. Smartphone health technology can be used to help them manage their conditions only if they accept and use the technology. Objective The aim of this study was to develop and test a theoretical model to predict and explain the factors influencing patients’ acceptance of smartphone health technology for chronic disease management. Methods Multiple theories and factors that may influence patients’ acceptance of smartphone health technology have been reviewed. A hybrid theoretical model was built based on the technology acceptance model, dual-factor model, health belief model, and the factors identified from interviews that might influence patients’ acceptance of smartphone health technology for chronic disease management. Data were collected from patient questionnaire surveys and computer log records about 157 hypertensive patients’ actual use of a smartphone health app. The partial least square method was used to test the theoretical model. Results The model accounted for .412 of the variance in patients’ intention to adopt the smartphone health technology. Intention to use accounted for .111 of the variance in actual use and had a significant weak relationship with the latter. Perceived ease of use was affected by patients’ smartphone usage experience, relationship with doctor, and self-efficacy. Although without a significant effect on intention to use, perceived ease of use had a significant positive influence on perceived usefulness. Relationship with doctor and perceived health threat had significant positive effects on perceived usefulness, countering the negative influence of resistance to change. Perceived usefulness, perceived health threat, and resistance to change significantly predicted patients’ intentions to use the technology. Age and gender had no significant influence on patients’ acceptance of smartphone technology. The study also

  5. Rein tension acceptance in young horses in a voluntary test situation

    DEFF Research Database (Denmark)

    Christensen, Janne Winther; zharkikh, T.L.; Antoine, A.

    2011-01-01

    Reasons for performing the study: During riding, horses are frequently exposed to pressure from the rider, e.g. through the bit and reins, but few studies have investigated at which point rein tension becomes uncomfortable for the horse. Objectives: To investigate how much rein tension young...... inexperienced horses are willing to accept in order to obtain a food reward; whether the tension acceptance changes during 3 consecutive test days; and whether rein tension correlates with the expression of conflict behaviour and heart rate. Hypotheses: Pressure-naïve horses will apply only little rein tension...... in the first voluntary trial, but their acceptance will gradually increase. High levels of rein tension will lead to expression of conflict behaviour and increases in heart rate. Methods: Fifteen 2-year-old, bridle-naïve mares were encouraged to stretch their head forward (across a 0.95 m high metal bar...

  6. Key Variables of Merging Behaviour : Empirical Comparison between Two Sites and Assessment of Gap Acceptance Theory

    NARCIS (Netherlands)

    Marczak, F.; Daamen, W.; Buisson, C.

    2013-01-01

    This paper presents two empirical trajectory data sets focusing on the merging behaviour on a motorway, both in the Netherlands and in France. A careful review of the literature shows that the main theories explaining this behaviour rely on the hypothesis of gap acceptance, i.e. the fact that each

  7. Acceptance test procedure, 241-SY-101/241-C-106 shot loading system

    International Nuclear Information System (INIS)

    Ostrom, M.J.

    1994-01-01

    This Acceptance Test Procedure is for the 241-SY-101/241-C-106 Shot Loading System. The procedure will test the components of the Shot Loading System and its capability of adequately loading shot into the annular space of the Container. The loaded shot will provide shielding as required for transporting and storage of a contaminated pump after removal from the tank. This test serves as verification that the SLS is acceptable for use in the pump removal operations for Tanks 241-SY-101, 241-C-106 and 241-AY-102. The pump removal operation for these three tanks will be performed by two different organizations with different equipment, but the Shot Loading System will be compatible between the two operations

  8. The deformable secondary mirror of VLT: final electro-mechanical and optical acceptance test results

    Science.gov (United States)

    Briguglio, Runa; Biasi, Roberto; Xompero, Marco; Riccardi, Armando; Andrighettoni, Mario; Pescoller, Dietrich; Angerer, Gerald; Gallieni, Daniele; Vernet, Elise; Kolb, Johann; Arsenault, Robin; Madec, Pierre-Yves

    2014-07-01

    The Deformable Secondary Mirror (DSM) for the VLT ended the stand-alone electro-mechanical and optical acceptance process, entering the test phase as part of the Adaptive Optics Facility (AOF) at the ESO Headquarter (Garching). The VLT-DSM currently represents the most advanced already-built large-format deformable mirror with its 1170 voice-coil actuators and its internal metrology based on co-located capacitive sensors to control the shape of the 1.12m-diameter 2mm-thick convex shell. The present paper reports the final results of the electro-mechanical and optical characterization of the DSM executed in a collaborative effort by the DSM manufacturing companies (Microgate s.r.l. and A.D.S. International s.r.l.), INAF-Osservatorio Astrofisico di Arcetri and ESO. The electro-mechanical acceptance tests have been performed in the company premises and their main purpose was the dynamical characterization of the internal control loop response and the calibration of the system data that are needed for its optimization. The optical acceptance tests have been performed at ESO (Garching) using the ASSIST optical test facility. The main purpose of the tests are the characterization of the optical shell flattening residuals, the corresponding calibration of flattening commands, the optical calibration of the capacitive sensors and the optical calibration of the mirror influence functions.

  9. Modeling of a Parabolic Trough Solar Field for Acceptance Testing: A Case Study

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, M. J.; Mehos, M. S.; Kearney, D. W.; McMahan, A. C.

    2011-01-01

    As deployment of parabolic trough concentrating solar power (CSP) systems ramps up, the need for reliable and robust performance acceptance test guidelines for the solar field is also amplified. Project owners and/or EPC contractors often require extensive solar field performance testing as part of the plant commissioning process in order to ensure that actual solar field performance satisfies both technical specifications and performance guaranties between the involved parties. Performance test code work is currently underway at the National Renewable Energy Laboratory (NREL) in collaboration with the SolarPACES Task-I activity, and within the ASME PTC-52 committee. One important aspect of acceptance testing is the selection of a robust technology performance model. NREL1 has developed a detailed parabolic trough performance model within the SAM software tool. This model is capable of predicting solar field, sub-system, and component performance. It has further been modified for this work to support calculation at subhourly time steps. This paper presents the methodology and results of a case study comparing actual performance data for a parabolic trough solar field to the predicted results using the modified SAM trough model. Due to data limitations, the methodology is applied to a single collector loop, though it applies to larger subfields and entire solar fields. Special consideration is provided for the model formulation, improvements to the model formulation based on comparison with the collected data, and uncertainty associated with the measured data. Additionally, this paper identifies modeling considerations that are of particular importance in the solar field acceptance testing process and uses the model to provide preliminary recommendations regarding acceptable steady-state testing conditions at the single-loop level.

  10. Nevada test site low-level and mixed waste repository design in the unsaturated zone

    International Nuclear Information System (INIS)

    Kawamura, T.A.; Warren, D.M.

    1989-01-01

    The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs

  11. Hanford Site Emergency Alerting System siren testing report

    International Nuclear Information System (INIS)

    Weidner, L.B.

    1997-01-01

    The purpose of the test was to determine the effective coverage of the proposed upgrades to the existing Hanford Site Emergency Alerting System (HSEAS). The upgrades are to enhance the existing HSEAS along the Columbia River from the Vernita Bridge to the White Bluffs Boat Launch as well as install a new alerting system in the 400 Area on the Hanford Site. Five siren sites along the Columbia River and two sites in the 400 Area were tested to determine the site locations that will provide the desired coverage

  12. HIV/AIDS testing sites and locator services

    Data.gov (United States)

    U.S. Department of Health & Human Services — The HIV Testing Sites & Care Services Locator is a first-of-its-kind, location-based search tool that allows you to search for testing services, housing...

  13. Assessment of the Nevada Test Site as a Site for Distributed Resource Testing and Project Plan: March 2002

    Energy Technology Data Exchange (ETDEWEB)

    Horgan, S.; Iannucci, J.; Whitaker, C.; Cibulka, L.; Erdman, W.

    2002-05-01

    The objective of this project was to evaluate the Nevada Test Site (NTS) as a location for performing dedicated, in-depth testing of distributed resources (DR) integrated with the electric distribution system. In this large scale testing, it is desired to operate multiple DRs and loads in an actual operating environment, in a series of controlled tests to concentrate on issues of interest to the DR community. This report includes an inventory of existing facilities at NTS, an assessment of site attributes in relation to DR testing requirements, and an evaluation of the feasibility and cost of upgrades to the site that would make it a fully qualified DR testing facility.

  14. Test report for run-in acceptance testing of Project W-151 300 HP mixing pumps

    International Nuclear Information System (INIS)

    Berglin, B.G.

    1998-01-01

    This report documents the results of a performance demonstration and operational checkout of three 300 HP mixer pumps in accordance with WHC-SD-WI51-TS-001 ''Mixer Pump Test Specification for Project W-151'' and Statement of Work 8K520-EMN-95-004 ''Mixer Pump Performance Demonstration at MASF'' in the 400 Area Maintenance and Storage Facility (MASF) building. Testing of the pumps was performed by Fast Flux Test Facility (FFTF) Engineering and funded by the Tank Waste Remediation System (TWRS) Project W-151. Testing began with the first pump on 04-01-95 and ended with the third pump on 11-01-96. Prior to testing, the MASF was modified and prepared to meet the pump testing requirements set forth by the Test Specification and the Statement of Work

  15. Identification of items and activities important to waste form acceptance by Westinghouse GoCo sites

    International Nuclear Information System (INIS)

    Plodinec, M.J.; Marra, S.L.; Dempster, J.; Randklev, E.H.

    1993-01-01

    The Department of Energy has established specifications (Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms, or WAPS) for canistered waste forms produced at Hanford, Savannah River, and West Valley. Compliance with these specifications requires that each waste form producer identify the items and activities which must be controlled to ensure compliance. As part of quality assurance oversight activities, reviewers have tried to compare the methodologies used by the waste form producers to identify items and activities important to waste form acceptance. Due to the lack of a documented comparison of the methods used by each producer, confusion has resulted over whether the methods being used are consistent. This confusion has been exacerbated by different systems of nomenclature used by each producer, and the different stages of development of each project. The waste form producers have met three times in the last two years, most recently on June 28, 1993, to exchange information on each producer's program. These meetings have been sponsored by the Westinghouse GoCo HLW Vitrification Committee. This document is the result of this most recent exchange. It fills the need for a documented comparison of the methodologies used to identify items and activities important to waste form acceptance. In this document, the methodology being used by each waste form producer is summarized, and the degree of consistency among the waste form producers is determined

  16. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    International Nuclear Information System (INIS)

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static

  17. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static.

  18. Semipalatinsk nuclear test site: History of building and function

    International Nuclear Information System (INIS)

    Sergazina, G.M.; Balmukhanov, S.B.

    1999-01-01

    A vast materials on history of Semipalatinsk nuclear test site creation and it building and function are presented. Authors with big reliability report one page of Kazakhstan's history. In steppe on naked place thousands of soldiers and officers, construct and military specialists have built the nuclear site on which during 40 years were conducting nuclear tests . Prolonged chronic radiation on population living near by site results to tragedy which is confessed by General Assembly of United Nations. In the book aspects of test site conversion and rehabilitation of injured population are considered. The book consists of introduction, three chapters and conclusion. The book is intended to wide circle of readers. (author)

  19. On-site cell field test support program

    Science.gov (United States)

    Staniunas, J. W.; Merten, G. P.

    1982-09-01

    Utility sites for data monitoring were reviewed and selected. Each of these sites will be instrumented and its energy requirements monitored and analyzed for one year prior to the selection of 40 Kilowatt fuel cell field test sites. Analyses in support of the selection of sites for instrumentation shows that many building sectors offered considerable market potential. These sectors include nursing home, health club, restaurant, industrial, hotel/motel and apartment.

  20. Social problems on Semipalatinsk test site

    International Nuclear Information System (INIS)

    Cherepnin, Yu.S.; Zhdanov, N.A.; Tumenova, B.N.

    2000-01-01

    In the report main stages of National Nuclear Center of Republic of Kazakhstan activity in the field of scientific information obtain about consequences of conducted nuclear tests, radioecological and medical and biological researches, restoration of natural environment and people's health in Republic of Kazakhstan are reflected. Chronicle and results of joint works within frameworks of international programs in these field are given as well. Analysis of up-to-date social problems of population of the region is carried out

  1. The Road Side Unit for the A270 Test Site

    NARCIS (Netherlands)

    Passchier, I.; Driessen, B.J.F.; Heijligers, B.M.R.; Netten, B.D.; Schackmann, P.P.M.

    2011-01-01

    The design and implementation of the Road Side Unit for the A270 Test Site is presented. It consists of a sensor platform and V2I communication platform with full coverage of the test site. A service platform enables applications to make use of these facilities. The RSU will be used both for the

  2. Methods of Usability Testing in Libraries Web Sites

    Directory of Open Access Journals (Sweden)

    Eman Fawzy

    2006-03-01

    Full Text Available A Study about libraries' web sites evaluation, that is the Usability, the study talking about methods of usability testing and define it, and its important in web sites evaluation, then details the methods of usability: questionnaire, core groups, testing experimental model, cards arrangement, and composed evaluation.

  3. Application for Permit to Operate a Class II Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-03-31

    The Nevada Test Site (NTS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NTS and National Security Technologies LLC (NSTec) is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The site will be used for the disposal of refuse, rubbish, garbage, sewage sludge, pathological waste, Asbestos-Containing Material (ACM), industrial solid waste, hydrocarbon-burdened soil, hydrocarbon-burdened demolition and construction waste, and other inert waste (hereafter called permissible waste). Waste containing free liquids or regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA) will not be accepted for disposal at the site. Waste regulated under the Toxic Substance Control Act (TSCA), excluding Polychlorinated Biphenyl [PCB], Bulk Product Waste (see Section 6.2.5) and ACM (see Section 6.2.2.2) will not be accepted for disposal at the site. The disposal site will be used as the sole depository of permissible waste which is: (1) Generated by entities covered under the U.S. Environmental Protection Agency (EPA) Hazardous Waste Generator Identification Number for the NTS; (2) Generated at sites identified in the Federal Facilities Agreement and Consent Order (FFACO); (3) Sensitive records and media, including documents, vugraphs, computer disks, typewriter ribbons, magnetic tapes, etc., generated by NNSA/NSO or its contractors; (4) ACM generated by NNSA/NSO or its contractors according to Section 6.2.2.2, as necessary; (5) Hydrocarbon-burdened soil and solid waste from areas covered under the EPA Hazardous Waste Generator Identification Number for the NTS; (6) Other waste on a case-by-case concurrence by

  4. Optimized FFTF Acceptance Test Program covering Phases III, IV, and V

    International Nuclear Information System (INIS)

    Wykoff, W.R.; Jones, D.H.

    1977-03-01

    A detailed review of Phases III, IV, and V of the FFTF Acceptance Test Program has been completed. The purpose of this review was to formulate that test sequence which not only meets requirements for safe, reliable and useful operation of the plant, but also results in the earliest prudent demonstration of full-power performance. A test sequence based on the underlying assumption that sodium flows into the secondary sodium storage tank (T-44) no later than August 31, 1978, is described in detail. A time-scale which allows extra time to put systems and equipment into operation the first time, debugging, and learning how to operate most effectively has been superimposed on the test sequence. Time is not included for major equipment malfunctions. This test plan provides the basis for coordinating the many and varied activities and interfaces necessary for successful and timely execution of the FFTF Acceptance Test Program. In this report, the need dates have been identified for presently scheduled test articles and standard core components

  5. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

  6. Acceptance Test Procedure for New Pumping Instrumentation and Control Skid Q

    International Nuclear Information System (INIS)

    KOCH, M.R.

    2000-01-01

    This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

  7. Disintegration of sublingual tablets: proposal for a validated test method and acceptance criterion.

    Science.gov (United States)

    Weda, M; van Riet-Nales, D A; van Aalst, P; de Kaste, D; Lekkerkerker, J F F

    2006-12-01

    In the Netherlands the market share of isosorbide dinitrate 5 mg sublingual tablets is dominated by 2 products (A and B). In the last few years complaints have been received from health care professionals on product B. During patient use the disintegration of the tablet was reported to be slow and/or incomplete, and ineffectiveness was experienced. In the European Pharmacopoeia (Ph. Eur.) no requirement is present for the disintegration time of sublingual tablets. The purpose of this study was to compare the in vitro disintegration time of products A and B, and to establish a suitable test method and acceptance criterion. A and B were tested with the Ph. Eur. method described in the monograph on disintegration of tablets and capsules as well as with 3 modified tests using the same Ph. Eur. apparatus, but without movement of the basket-rack assembly. In modified test 1 and modified test 2 water was used as medium (900 ml and 50 ml respectively), whereas in modified test 3 artificial saliva was used (50 ml). In addition, disintegration was tested in Nessler tubes with 0.5 and 2 ml of water. Finally, the Ph. Eur. method was also applied to other sublingual tablets with other drug substances on the Dutch market. With modified test 3 no disintegration could be achieved within 20 min. With the Ph. Eur. method and modified tests 1 and 2 product A and B differed significantly (p disintegration times. These 3 methods were capable of discriminating between products and between batches. The time measured with the Ph. Eur. method was significantly lower compared to modified tests 1 and 2 (p tablets the disintegration time should be tested. The Ph. Eur. method is considered suitable for this test. In view of the products currently on the market and taking into consideration requirements in the United States Pharmacopeia and Japanese Pharmacopoeia, an acceptance criterion of not more than 2 min is proposed.

  8. Social trust, risk perceptions and public acceptance of recycled water: testing a social-psychological model.

    Science.gov (United States)

    Ross, Victoria L; Fielding, Kelly S; Louis, Winnifred R

    2014-05-01

    Faced with a severe drought, the residents of the regional city of Toowoomba, in South East Queensland, Australia were asked to consider a potable wastewater reuse scheme to supplement drinking water supplies. As public risk perceptions and trust have been shown to be key factors in acceptance of potable reuse projects, this research developed and tested a social-psychological model of trust, risk perceptions and acceptance. Participants (N = 380) were surveyed a few weeks before a referendum was held in which residents voted against the controversial scheme. Analysis using structural equation modelling showed that the more community members perceived that the water authority used fair procedures (e.g., consulting with the community and providing accurate information), the greater their sense of shared identity with the water authority. Shared social identity in turn influenced trust via increased source credibility, that is, perceptions that the water authority is competent and has the community's interest at heart. The findings also support past research showing that higher levels of trust in the water authority were associated with lower perceptions of risk, which in turn were associated with higher levels of acceptance, and vice versa. The findings have a practical application for improving public acceptance of potable recycled water schemes. Copyright © 2014 Elsevier Ltd. All rights reserved.

  9. Tritium activities in selected wells on the Nevada Test Site

    International Nuclear Information System (INIS)

    Lyles, B.F.

    1993-05-01

    Literature and data were reviewed related to radionuclides in groundwater on and near the Nevada Test Site. No elevated tritium activities have been reported outside of the major testing regions of the Nevada Test Site. Three wells were identified as having water with above-background (>50 pCi/l) tritium activities: UE-15d Water Well; USGS Water Well A; and USGS Test Well B Ex. Although none of these wells have tritium activities greater than the Nevada State Drinking Water standard (20,000 pCi/l), their time-series tritium trends may be indicative to potential on-site radionuclide migration

  10. Penetration Testing Model for Web sites Hosted in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Mohd Dzul Aiman Aslan; Mohamad Safuan Sulaiman; Siti Nurbahyah Hamdan; Saaidi Ismail; Mohd Fauzi Haris; Norzalina Nasiruddin; Raja Murzaferi Mokhtar

    2012-01-01

    Nuclear Malaysia web sites has been very crucial in providing important and useful information and services to the clients as well as the users worldwide. Furthermore, a web site is important as it reflects the organisation image. To ensure the integrity of the content of web site, a study has been made and a penetration testing model has been implemented to test the security of several web sites hosted at Nuclear Malaysia for malicious attempts. This study will explain how the security was tested in the detailed condition and measured. The result determined the security level and the vulnerability of several web sites. This result is important for improving and hardening the security of web sites in Nuclear Malaysia. (author)

  11. Analysis of the cool down related cavity performance of the European XFEL vertical acceptance tests

    Energy Technology Data Exchange (ETDEWEB)

    Wenskat, Marc; Schaffran, J.

    2017-09-15

    For the European X-Ray Free Electron Laser (XFEL) cavity production, the cold radio-frequency (RF) test of the cavities at 2 K after delivery from the two vendors was the mandatory acceptance test. It has been previously reported, that the cool down dynamics of a cavity across T{sub c} has a significant influence on the observed intrinsic quality factor Q{sub 0}, which is a measure of the losses on the inner cavity surface. A total number of 367 cool downs is used to analyze this correlation and we show that such a correlation is not observed during the European XFEL cavity production.

  12. Tools for DIY site-testing

    Science.gov (United States)

    Flores, Federico; Rondanelli, Roberto; Abarca, Accel; Diaz, Marcos; Querel, Richard

    2012-09-01

    Our group has designed, sourced and constructed a radiosonde/ground-station pair using inexpensive opensource hardware. Based on the Arduino platform, the easy to build radiosonde allows the atmospheric science community to test and deploy instrumentation packages that can be fully customized to their individual sensing requirements. This sensing/transmitter package has been successfully deployed on a tethered-balloon, a weather balloon, a UAV airplane, and is currently being integrated into a UAV quadcopter and a student-built rocket. In this paper, the system, field measurements and potential applications will be described. As will the science drivers of having full control and open access to a measurement system in an age when commercial solutions have become popular but are restrictive in terms of proprietary sensor specifications, "black-box" calibration operations or data handling routines, etc. The ability to modify and experiment with both the hardware and software tools is an essential part of the scientific process. Without an understanding of the intrinsic biases or limitations in your instruments and system, it becomes difficult to improve them or advance the knowledge in any given field.

  13. Malignant tumors and Semipalatinsk test site

    International Nuclear Information System (INIS)

    Balmukhanov, S.B.; Gusev, B.I.; Abdrakhmanov, Zh.N.

    1998-01-01

    Mutational biological effect of ionizing irradiation initiates and promotes neoplastic process (cancer or leukemia) as well as genetic defects in further generations. It is well-known that the far-off irradiation effects, caused by deoxyribonucleic acid mutation, take place for adulterers when irradiation dose is within 20 c Sv and for foetus when it is 1.0 c Sv. According to information obtained by a number of researches, irradiation dose of within 0.5-0.9 c Sv, and even 0.1 c Sv, cannot be considered to be safe in regards to their capabilities to cause formation of malignant tumors. Number of people, being effected by the ionizing irradiation during 40 years of nuclear weapon testiness conduction (more than 600), comes to about 3 mill., half of which are Kazakstan people. In addition, more than 500 different areas in Semipalatinsk region, which have different level of radiation contamination. The excess malignant tumor sick rate, caused by irradiation effect, was studied for two groups of population that were being continuously examined since 1960. The exposure external irradiation dose was from 80 to 274 c Sv for the main population group (10 thousands). The testing group of population (11 thousands) was effected by the irradiation dose of 7-10 c Sv

  14. Cassini RTG acceptance test results and RTG performance on Galileo and Ulysses

    International Nuclear Information System (INIS)

    Kelly, C.E.; Klee, P.M.

    1997-01-01

    Flight acceptance testing has been completed for the RTGs to be used on the Cassini spacecraft which is scheduled for an October 6, 1997 launch to Saturn. The acceptance test program includes vibration tests, magnetic field measurements, mass properties (weight and c.g.) and thermal vacuum test. This paper presents the thermal vacuum test results. Three RTGs are to be used, F-2, F-6, and F-7. F-5 is the backup RTG, as it was for the Galileo and Ulysses missions launched in 1989 and 1990, respectively. RTG performance measured during the thermal vacuum tests carried out at the Mound Laboratory facility met all specification requirements. Beginning of mission (BOM) and end of mission (EOM) power predictions have been made based on these tests results. BOM power is predicted to be 888 watts compared to the minimum requirement of 826 watts. Degradation models predict the EOM power after 16 years is to be 640 watts compared to a minimum requirement of 596 watts. Results of small scale module tests are also shown. The modules contain couples from the qualification and flight production runs. The tests have exceeded 28,000 hours (3.2 years) and are continuing to provide increased confidence in the predicted long term performance of the Cassini RTGs. All test results indicate that the power requirements of the Cassini spacecraft will be met. BOM and EOM power margins of over 5% are predicted. Power output from telemetry for the two Galileo RTGs are shown from the 1989 launch to the recent Jupiter encounter. Comparisons of predicted, measured and required performance are shown. Telemetry data are also shown for the RTG on the Ulysses spacecraft which completed its planned mission in 1995 and is now in the extended mission

  15. Cassini RTG acceptance test results and RTG performance on Galileo and Ulysses

    International Nuclear Information System (INIS)

    Kelly, C.E.; Klee, P.M.

    1997-01-01

    Flight acceptance testing has been completed for the RTGs to be used on the Cassini spacecraft which is scheduled for an October 6, 1997 launch to Saturn. The acceptance test program includes vibration tests, magnetic field measurements, properties (weight and c.g.) and thermal vacuum test. This paper presents The thermal vacuum test results. Three RTGs are to be used, F-2, F-6, and F-7. F-5 is tile back-up RTG, as it was for the Galileo and Ulysses missions launched in 1989 and 1990, respectively. RTG performance measured during the thermal vacuum tests carried out at die Mound Laboratory facility met all specification requirements. Beginning of mission (BOM) and end of mission (EOM) power predictions have been made based on than tests results. BOM power is predicted to be 888 watts compared to the minimum requirement of 826 watts. Degradation models predict the EOM power after 16 years is to be 640 watts compared to a minimum requirement of 596 watts. Results of small scale module tests are also showing. The modules contain couples from the qualification and flight production runs. The tests have exceeded 28,000 hours (3.2 years) and are continuing to provide increased confidence in the predicted long term performance of the Cassini RTGs. All test results indicate that the power requirements of the Cassini spacecraft will be met. BOM and EOM power margins of over five percent are predicted. Power output from telemetry for the two Galileo RTGs are shown from the 1989 launch to the recent Jupiter encounter. Comparisons of predicted, measured and required performance are shown. Telemetry data are also shown for the RTG on the Ulysses spacecraft which completed its planned mission in 1995 and is now in the extended mission

  16. W-026 acceptance test report system integration equipment (SIE)(submittal {number_sign} 018.6.A)

    Energy Technology Data Exchange (ETDEWEB)

    Watson, T.L.

    1997-01-27

    Acceptance testing of the System Integration Equipment (SIE) at Hanford was performed in two stages. The first was inconclusive, and resulted in a number of findings. These finding. are summarized as part of this report. The second stage of testing addressed these findings, and performed full system testing per the approved test procedure. This report includes summaries of all testing, results and finding.. Although the SIE did not in some cases perform as required for plant operations, it did perform per the system specification. (These discrepancies were noted and are addressed elsewhere.) Following testing, the system was formaLLy accepted. Documentation of this acceptance is incLuded in this report.

  17. Hanford Immobilized LAW Product Acceptance: Tanks Focus Area Testing Data Package II

    International Nuclear Information System (INIS)

    Schulz, Rebecca L.; Lorier, Troy H.; Peeler, David K.; Brown, Kevin G.; Reamer, Irene A.; Vienna, John D.; Jiricka, Antonin; Jorgensen, Benaiah M.; Smith, Donald E.

    2001-01-01

    This report is a continuation of the Hanford Immobilized Low Activity Waste (LAW) Product Acceptance (HLP): Initial Tanks Focus Area Testing Data Package (Vienna (and others) 2000). In addition to new 5000-h product consistency test (PCT), vapor hydration test (VHT), and alteration products data, some previously reported data together with relevant background information are included for an easily accessible source of reference when comparing the response of the various glasses to different test conditions. A matrix of 55 glasses was developed and tested to identify the impact of glass composition on long-term corrosion behavior and to develop an acceptable composition region for Hanford LAW glasses. Of the 55 glasses, 45 were designed to systematically vary the glass composition, and 10 were selected because large and growing databases on their corrosion characteristics had accumulated. The targeted and measured compositions of these glasses are found in the Appendix A. All glasses were fabricated according to standard procedures and heat treated to simulate the slow cooling that will occur in a portion of the waste glass after vitrification in the planned treatment facility at Hanford

  18. Quality assurance in diagnostic radiology in Hungary - first experiences in acceptance testing

    International Nuclear Information System (INIS)

    Porubszky, T.; Pellet, S.; Ballay, L.; Talian, L.; Giczi, F.

    2003-01-01

    It is a general experience that optimum imaging with minimum patient doses, moreover, the safe operation and long life of X-ray equipment can be assured by regular measurement of technical parameters and checking of their constancy (routine performance testing) only. These tests are generally known as quality control, while together with the so-called corrective actions and its management it is called (physical-technical) quality assurance (QA). In the European Union, Directive 97/43/EURATOM about radiation protection of patients requires - among others - the good practice of (physical-technical) quality assurance. In Hungary, Decree No. 31/2001. (X.3.) of the Minister of Health harmonizes all of its requirements. Acceptance testing of new diagnostic X-ray equipment is assigned to NPHC-NRIRR. QA has been a daily practice in radiation therapy and nuclear medicine for a long time. A National Patient Dose Assessment Programme has also successfully run since 1989. We had, however, only few preliminaries in QA in diagnostic radiology in the second half of the eighties. Nowadays there are running QA programmes in some hospitals and mammography centres. he testing activity of our institute is independent from manufacturers, it is run within the frame of an accredited testing laboratory, using calibrated measuring instruments and based on valid international standards. So the started way of implementing QA in diagnostic radiology needs a lot of further efforts, adapting experiences of other countries, and also some financial help to reach an acceptable level in the EU. (authors)

  19. Consumer acceptance, market test and market development of irradiated rice, dehydrated vegetables and spices

    International Nuclear Information System (INIS)

    Shi Peixin; Lin Yin

    2001-01-01

    Establishment of irradiation processing parameters, a quality assurance system, consumer acceptance, market test and market development of irradiated rice, dehydrated vegetables and spices were the activities carried out in this project by the Chinese Agricultural Irradiation Center. The results of the studies showed that the process dose for rice was 0.2-0.5 kGy when the non-uniformity was lower than 2.5, dose range for dehydrated vegetables was 5-7 kGy, dose for spices was 7-8 kGy. The system for quality assurance was established. The processing standards for several irradiated food items were set up. Market test showed that more than 70-80% of consumers accepted irradiated food. Industrial companies also accepted irradiated dehydrated vegetables and spices. The latter were successfully introduced to the markets and successful commercialization of irradiated garlic was followed. The economic benefit of operating the Chinese Agricultural Irradiation Center was analyzed and found attractive, especially for low dose irradiation of foods in sufficient supply. (author)

  20. Consumer acceptance, market test and market development of irradiated rice, dehydrated vegetables and spices

    Energy Technology Data Exchange (ETDEWEB)

    Peixin, Shi; Yin, Lin [Chinese Agricultural Irradiation Center, Institute for Application of Atomic Energy, Chinese Academy of Agricultural Sciences, Beijing (China)

    2001-05-01

    Establishment of irradiation processing parameters, a quality assurance system, consumer acceptance, market test and market development of irradiated rice, dehydrated vegetables and spices were the activities carried out in this project by the Chinese Agricultural Irradiation Center. The results of the studies showed that the process dose for rice was 0.2-0.5 kGy when the non-uniformity was lower than 2.5, dose range for dehydrated vegetables was 5-7 kGy, dose for spices was 7-8 kGy. The system for quality assurance was established. The processing standards for several irradiated food items were set up. Market test showed that more than 70-80% of consumers accepted irradiated food. Industrial companies also accepted irradiated dehydrated vegetables and spices. The latter were successfully introduced to the markets and successful commercialization of irradiated garlic was followed. The economic benefit of operating the Chinese Agricultural Irradiation Center was analyzed and found attractive, especially for low dose irradiation of foods in sufficient supply. (author)

  1. Acceptance criteria for reprocessed AcuNav catheters: comparison between functionality testing and clinical image assessment.

    Science.gov (United States)

    Bank, Alan J; Berry, James M; Wilson, Robert F; Lester, Bruce R

    2009-03-01

    The AcuNav-catheter is a vector-phased array ultrasound catheter that has shown great utility for both diagnosis and electrophysiological interventions. To test the feasibility of limited catheter reuse and to ensure that reprocessed catheters would produce acceptable clinical images, the present study compared the 2-D and Doppler image quality, as determined by clinical assessment, with the catheter's functional status as determined by the FirstCall 2000 transducer tester. Reprocessed catheters from four functional categories, two acceptable and two unacceptable, were used to collect images, 2-D and Doppler, from a porcine heart. The images were blinded and then rated by clinical evaluation. The study found that catheter images from all functional categories were found to be clinically acceptable except for those from the lowest unacceptable category. In addition, examination of tip deflection characteristics showed no significant difference between new and reprocessed catheters. We conclude that reprocessed AcuNav catheters that pass functional tests are able to produce clinical images, 2-D and Doppler, which are equivalent to their new counterparts.

  2. Home-based voluntary HIV counselling and testing found highly acceptable and to reduce inequalities

    Directory of Open Access Journals (Sweden)

    Michelo Charles

    2010-06-01

    Full Text Available Abstract Background Low uptake of voluntary HIV counselling and testing (VCT in sub-Saharan Africa is raising acceptability concerns which might be associated with ways by which it is offered. We investigated the acceptability of home-based delivery of counselling and HIV testing in urban and rural populations in Zambia where VCT has been offered mostly from local clinics. Methods A population-based HIV survey was conducted in selected communities in 2003 (n = 5035. All participants stating willingness to be HIV tested were offered VCT at home and all counselling was conducted in the participants' homes. In the urban area post-test counselling and giving of results were done the following day whereas in rural areas this could take 1-3 weeks. Results Of those who indicated willingness to be HIV tested, 76.1% (95%CI 74.9-77.2 were counselled and received the test result. Overall, there was an increase in the proportion ever HIV tested from 18% before provision of home-based VCT to 38% after. The highest increase was in rural areas; among young rural men aged 15-24 years up from 14% to 42% vs. for urban men from 17% to 37%. Test rates by educational attainment changed from being positively associated to be evenly distributed after home-based VCT. Conclusions A high uptake was achieved by delivering HIV counselling and testing at home. The highest uptakes were seen in rural areas, in young people and groups with low educational attainment, resulting in substantial reductions in existing inequalities in accessing VCT services.

  3. Testing Usability and Acceptability of a Web Application to Promote Physical Activity (iCanFit) Among Older Adults

    Science.gov (United States)

    Goldberg, Daniel; Dahlke, Deborah Vollmer; Ory, Marcia G; Cargill, Jessica S; Coughlin, Rachel; Hernandez, Edgar; Kellstedt, Debra K; Peres, S Camille

    2014-01-01

    Background Most older Americans do not exercise regularly and many have chronic conditions. Among an increasing number of fitness mobile and Web apps, few are designed for older adults with chronic conditions despite high ownership rates of mobile tools and Internet access in this population. We designed a mobile-enabled Web app, iCanFit, to promote physical activity in this population. Objective This study aimed to test the usability and acceptability of iCanFit among older adults in a community setting. Methods A total of 33 older adults (aged 60 to 82 years) were recruited from communities to test iCanFit. Of these 33, 10 participants completed the usability testing in a computer room of a senior community center. A research assistant timed each Web application task and observed user navigation behavior using usability metrics. The other 23 participants used the website on their own devices at home and provided feedback after 2-3 weeks by completing a user-experience survey assessing ease of use, helpfulness, and satisfaction with iCanFit. Results Participants completed all 15 tasks on the iCanFit site in an average of 31 (SD 6.9) minutes; some tasks required more time or needed assistance. Participants’ comments were addressed to improve the site’s senior friendliness and ease of use. In the user-experience survey, participants reported high levels of usefulness and satisfaction. More than 56% (13/23) of participants indicated they would continue using the program and recommend it to their families or friends. Conclusions Testing usability and acceptability is a very important step in developing age-appropriate and user-friendly Web apps, especially for older adults. Testing usability and acceptability in a community setting can help reveal users’ experiences and feedback in a real-life setting. Our study suggested that older adults had a high degree of acceptance of iCanFit and could use it easily. The efficacy trial of iCanFit is currently underway

  4. The Rapid Integration and Test Environment - A Process for Achieving Software Test Acceptance

    OpenAIRE

    Jack, Rick

    2010-01-01

    Proceedings Paper (for Acquisition Research Program) Approved for public release; distribution unlimited. The Rapid Integration and Test Environment (RITE) initiative, implemented by the Program Executive Office, Command, Control, Communications, Computers and Intelligence, Command and Control Program Office (PMW-150), was born of necessity. Existing processes for requirements definition and management, as well as those for software development, did not consistently deliver high-qualit...

  5. The Changing Adventures of Mixed Low-Level Waste Disposal at the Nevada Test Site

    International Nuclear Information System (INIS)

    2007-01-01

    After a 15-year hiatus, the United States Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO) began accepting DOE off-site generated mixed low-level radioactive waste (MLLW) for disposal at the Nevada Test Site (NTS) in December 2005. This action was predicated on the acceptance by the Nevada Division of Environmental Protection (NDEP) of a waste analysis plan (WAP). The NNSA/NSO agreed to limit mixed waste disposal to 20,000 cubic meters (approximately 706,000 cubic feet) and close the facility by December 2010 or sooner, if the volume limit is reached. The WAP and implementing procedures were developed based on Hanford?s system of verification to the extent possible so the two regional disposal sites could have similar processes. Since the NNSA/NSO does not have a breaching facility to allow the opening of boxes at the site, verification of the waste occurs by visual inspection at the generator/treatment facility or by Real-Time-Radiography (RTR) at the NTS. This system allows the NTS to effectively, efficiently, and compliantly accept MLLW for disposal. The WAP, NTS Waste Acceptance Criteria, and procedures have been revised based on learning experiences. These changes include: RTR expectations; visual inspection techniques; tamper-indicating device selection; void space requirements; and chemical screening concerns. The NNSA/NSO, NDEP, and the generators have been working together throughout the debugging of the verification processes. Additionally, the NNSA/NSO will continue to refine the MLLW acceptance processes and strive for continual improvement of the program

  6. Rein tension acceptance in young horses in a voluntary test situation.

    Science.gov (United States)

    Christensen, J W; Zharkikh, T L; Antoine, A; Malmkvist, J

    2011-03-01

    During riding, horses are frequently exposed to pressure from the rider, e.g. through the bit and reins, but few studies have investigated at which point rein tension becomes uncomfortable for the horse. To investigate how much rein tension young inexperienced horses are willing to accept in order to obtain a food reward; whether the tension acceptance changes during 3 consecutive test days; and whether rein tension correlates with the expression of conflict behaviour and heart rate. Pressure-naïve horses will apply only little rein tension in the first voluntary trial, but their acceptance will gradually increase. High levels of rein tension will lead to expression of conflict behaviour and increases in heart rate. Fifteen 2-year-old, bridle-naïve mares were encouraged to stretch their head forward (across a 0.95 m high metal bar) to obtain a food reward in a voluntary test situation. On each test day, each horse was exposed to 2 control sessions (loose reins), an intermediate and a short rein session (1 min/session). Rein tension, heart rate and behaviour were recorded. The horses applied significantly more tension on the first day (mean rein tension: 10.2 N), compared to the second and third test day (Day 2: 6.0 and Day 3: 5.7 N). The horses showed significantly more conflict behaviour in the short rein treatment. There was no treatment effect on heart rate. The horses applied the highest rein tension on the first day, and apparently learned to avoid the tension, rather than habituate to it. Rein tension correlated with expression of conflict behaviour, indicating that the horses found the tension aversive. Further studies should focus on the correlation between rein tension and conflict behaviour in ridden horses. © 2010 EVJ Ltd.

  7. Low acceptance of HSV-2 testing among high-risk women.

    Science.gov (United States)

    Roth, A M; Dodge, B M; Van Der Pol, B; Reece, M; Zimet, G D

    2011-06-01

    We evaluated the acceptability of a community-based herpes simplex virus type 2 (HSV-2) screening programme for at-risk women and assessed factors related to uptake of point of care HSV-2 testing. One hundred recently arrested women (median age 34 years) were recruited from a community court handling lower-level misdemeanour cases in Indianapolis, Indiana. Individuals completed a survey assessing factors related to HSV-2 screening intentions and were offered point of care HSV-2 testing. Rates of HSV-2 infection in this population are high; 61.1% of women tested were positive. The majority (81%) accepted a prescription for suppressive therapy. Women in this sample indicated that HSV-2 screening is an important component of health care but were unwilling to pay the US$10 it cost to be tested. To encourage this and other high-risk populations to be screened for HSV-2, public health resources will be needed to help individuals overcome cost-related barriers to care.

  8. Closure Plan for the Area 3 Radioactive Waste Management Site at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2007-09-01

    The Area 3 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec) for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the interim closure plan for the Area 3 RWMS, which was presented in the Integrated Closure and Monitoring Plan (ICMP) (DOE, 2005). The format and content of this plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). The major updates to the plan include a new closure date, updated closure inventory, the new institutional control policy, and the Title II engineering cover design. The plan identifies the assumptions and regulatory requirements, describes the disposal sites and the physical environment in which they are located, presents the design of the closure cover, and defines the approach and schedule for both closing and monitoring the site. The Area 3 RWMS accepts low-level waste (LLW) from across the DOE Complex in compliance with the NTS Waste Acceptance Criteria (NNSA/NSO, 2006). The Area 3 RWMS accepts both packaged and unpackaged unclassified bulk LLW for disposal in subsidence craters that resulted from deep underground tests of nuclear devices in the early 1960s. The Area 3 RWMS covers 48 hectares (119 acres) and comprises seven subsidence craters--U-3ax, U-3bl, U-3ah, U-3at, U-3bh, U-3az, and U-3bg. The area between craters U-3ax and U-3bl was excavated to form one large disposal unit (U-3ax/bl); the area between craters U-3ah and U-3at was also excavated to form another large disposal unit (U-3ah/at). Waste unit U-3ax/bl is closed; waste units U-3ah/at and U-3bh are active; and the remaining craters, although currently undeveloped, are available for disposal of waste if required. This plan specifically addresses the closure of the U-3ah/at and the U-3bh LLW units. A final closure

  9. Closure Plan for the Area 3 Radioactive Waste Management Site at the Nevada Test Site

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2007-01-01

    The Area 3 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec) for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the interim closure plan for the Area 3 RWMS, which was presented in the Integrated Closure and Monitoring Plan (ICMP) (DOE, 2005). The format and content of this plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). The major updates to the plan include a new closure date, updated closure inventory, the new institutional control policy, and the Title II engineering cover design. The plan identifies the assumptions and regulatory requirements, describes the disposal sites and the physical environment in which they are located, presents the design of the closure cover, and defines the approach and schedule for both closing and monitoring the site. The Area 3 RWMS accepts low-level waste (LLW) from across the DOE Complex in compliance with the NTS Waste Acceptance Criteria (NNSA/NSO, 2006). The Area 3 RWMS accepts both packaged and unpackaged unclassified bulk LLW for disposal in subsidence craters that resulted from deep underground tests of nuclear devices in the early 1960s. The Area 3 RWMS covers 48 hectares (119 acres) and comprises seven subsidence craters--U-3ax, U-3bl, U-3ah, U-3at, U-3bh, U-3az, and U-3bg. The area between craters U-3ax and U-3bl was excavated to form one large disposal unit (U-3ax/bl); the area between craters U-3ah and U-3at was also excavated to form another large disposal unit (U-3ah/at). Waste unit U-3ax/bl is closed; waste units U-3ah/at and U-3bh are active; and the remaining craters, although currently undeveloped, are available for disposal of waste if required. This plan specifically addresses the closure of the U-3ah/at and the U-3bh LLW units. A final closure

  10. Hanford tank initiative test facility site selection study

    International Nuclear Information System (INIS)

    Staehr, T.W.

    1997-01-01

    The Hanford Tanks Initiative (HTI) project is developing equipment for the removal of hard heel waste from the Hanford Site underground single-shell waste storage tanks. The HTI equipment will initially be installed in the 241-C-106 tank where its operation will be demonstrated. This study evaluates existing Hanford Site facilities and other sites for functional testing of the HTI equipment before it is installed into the 241-C-106 tank

  11. ENRAF Series 854 Advanced Technology Gauge (ATG) with SPU II card for Leak Detector Use Acceptance Test Procedure

    International Nuclear Information System (INIS)

    SMITH, S.G.

    1999-01-01

    The following Acceptance Test Procedure was written to test the ENRAF series 854 ATG with SPU II card prior to installation in the Tank Farms. The procedure sets various parameters and verifies the gauge and alarms functionality

  12. ENRAF Series 854 Advanced Technology Gauge (ATG) with SPU ll Card for Leak Detector Use Acceptance Test Procedure

    International Nuclear Information System (INIS)

    SMITH, S.G.

    1999-01-01

    The following Acceptance Test Procedure was written to test the Enraf Series 854 ATG with SPU-II card prior to installation in the Tank Farms. The procedure sets various parameters and verifies the gauge and the alarms functionality

  13. Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    V. Yucel

    2001-09-01

    This report summarizes the results of a Composite Analysis (CA) for the Area 5 Radioactive Waste Management Site (RWMS). The Area 5 RWMS is a US Department of Energy (DOE)-operated low-level radioactive waste (LLW) management site located in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS has disposed of low-level radioactive waste in shallow unlined pits and trenches since 1960. Transuranic waste (TRU) and high-specific activity waste was disposed in Greater Confinement Disposal (GCD) boreholes from 1983 to 1989. The purpose of this CA is to determine if continuing operation of the Area 5 RWMS poses an acceptable or unacceptable risk to the public considering the total waste inventory and all other interacting sources of radioactive material in the vicinity. Continuing operation of the Area 5 RWMS will be considered acceptable if the total effective dose equivalent (TEDE) is less than 100 mrem in a year. If the TEDE exceeds 30 mrem in a year, a cost-benefit options analysis must be performed to determine if cost-effective management options exist to reduce the dose further. If the TEDE is found to be less than 30 mrem in a year, an analysis may be performed if warranted to determine if doses are as low as reasonably achievable (ALARA).

  14. Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    V. Yucel

    2001-01-01

    This report summarizes the results of a Composite Analysis (CA) for the Area 5 Radioactive Waste Management Site (RWMS). The Area 5 RWMS is a US Department of Energy (DOE)-operated low-level radioactive waste (LLW) management site located in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS has disposed of low-level radioactive waste in shallow unlined pits and trenches since 1960. Transuranic waste (TRU) and high-specific activity waste was disposed in Greater Confinement Disposal (GCD) boreholes from 1983 to 1989. The purpose of this CA is to determine if continuing operation of the Area 5 RWMS poses an acceptable or unacceptable risk to the public considering the total waste inventory and all other interacting sources of radioactive material in the vicinity. Continuing operation of the Area 5 RWMS will be considered acceptable if the total effective dose equivalent (TEDE) is less than 100 mrem in a year. If the TEDE exceeds 30 mrem in a year, a cost-benefit options analysis must be performed to determine if cost-effective management options exist to reduce the dose further. If the TEDE is found to be less than 30 mrem in a year, an analysis may be performed if warranted to determine if doses are as low as reasonably achievable (ALARA)

  15. Database on radioecological situation in Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Turkebaev, T.Eh.; Kislitsin, S.B.; Lopuga, A.D.; Kuketaev, A.T.; Kikkarin, S.M.

    1999-01-01

    One of the main objectives of the National Nuclear Center of the Republic of Kazakstan is to define radioecological situation in details, conduct a continuous monitoring and eliminate consequences of nuclear explosions at Semipalatinsk nuclear test site. Investigations of Semipalatinsk nuclear test site area contamination by radioactive substances and vindication activity are the reasons for development of computer database on radioecological situation of the test site area, which will allow arranging and processing the available and entering information about the radioecological situation, assessing the effect of different testing factors on the environment and health of the Semipalatinsk nuclear test site area population.The described conception of database on radioecological situation of the Semipalatinsk nuclear test site area cannot be considered as the final one. As new information arrives, structure and content of the database is updated and optimized. New capabilities and structural elements may be provided if new aspects in Semipalatinsk nuclear test site area contamination study (air environment study, radionuclides migration) arise

  16. Semipalatinsk test site: 10 years after shutting down

    International Nuclear Information System (INIS)

    Tukhvatulin, Sh.T.

    2001-01-01

    The paper consists the historical materials and chronology of events on the Semipalatinsk test site before and after it shutdown. The main part of the paper is focused on the activity on the former nuclear site after it shutdown. The first of all activity is related with coming into being and development of the National Nuclear Center of the Republic of Kazakhstan

  17. Usability Testing in a Library Web Site Redesign Project.

    Science.gov (United States)

    McMullen, Susan

    2001-01-01

    Discusses the need for an intuitive library information gateway to meet users' information needs and describes the process involved in redesigning a library Web site based on experiences at Roger Williams University. Explains usability testing methods that were used to discover how users were interacting with the Web site interface. (Author/LRW)

  18. Preliminary access routes and cost study analyses for seven potentially acceptable salt sites: Final report, October 1984

    International Nuclear Information System (INIS)

    1987-02-01

    This report analyzes highway and railroad access to seven potentially acceptable salt repository sites: Richton Dome and Cypress Creek Dome in Mississippi, Vacherie Dome in Louisiana, Swisher County and Deaf Smith County in Texas, and Davis Canyon and Lavender Canyon in utah. The objectives of the study were to investigate the routing of reasonable access corridors to the sites, describe major characteristics of each route, and estimate the costs for constructing or upgrading highways and railroads. The routes used in the analysis are not necessarily recommended or preferred over other routes, nor do they represent an implied final selection. Detailed engineering studies must be performed for the Davis Canyon and Lavender Canyon highway access before the analyzed routes can be considered to be viable. 20 refs., 7 figs., 3 tabs

  19. Assessment of national systems for obtaining local siting acceptance of nuclear-waste-management facilities (1981). Final report

    International Nuclear Information System (INIS)

    1981-01-01

    There is a rich mixture of formal and informal approaches being used in our sister nuclear democracies in their attempts to deal with the difficulties in obtaining local siting acceptance of national waste management facilities. Some of these are meeting with a degree of success not yet achieved in the US. Although this survey documents and assesses many of these approaches, the scope of the study did not include an assessment of their relevance to common problems in the US. It would appear that in addition to a periodic updating of the approaches and progress of other countries in dealing with the siting of nuclear waste facilities, an assessment of the applicability of the more successful of these approaches to the US political system could make good use of the information developed in the preparation of this report

  20. Review of the acceptance tests of the W7-X superconducting magnets

    International Nuclear Information System (INIS)

    Ehmler, H.; Baldzuhn, J.; Genini, L.; Heyn, K.; Sborchia, C.; Schild, T.

    2007-01-01

    The W7-X magnet system consists of 50 non-planar coils of five different types and 20 planar coils of two different types. Factory tests of the non-planar coils are carried out at the manufacturer site of Babcock-Noell, Germany, and for the planar coils at Tesla Engineering, UK. They consist of electrical insulation checks, mass flow measurements, leak tests and sensor checks. In the test facility of CEA Saclay, France, each coil is cooled down to ∼5 K and operated at nominal current. At least one coil of each type is quenched by increasing the inlet temperature. Results of the mass flow measurements and the quench tests are presented. The manufacturing and testing progress is reviewed and the impact of technical failures is discussed. In conclusion, the scope of the tests allows a very strict quality control. This experience is highly beneficial for the construction and testing of similar components for future superconducting fusion experiments

  1. Grid site testing for ATLAS with HammerCloud

    International Nuclear Information System (INIS)

    Elmsheuser, J; Hönig, F; Legger, F; LLamas, R Medrano; Sciacca, F G; Ster, D van der

    2014-01-01

    With the exponential growth of LHC (Large Hadron Collider) data in 2012, distributed computing has become the established way to analyze collider data. The ATLAS grid infrastructure includes more than 130 sites worldwide, ranging from large national computing centers to smaller university clusters. HammerCloud was previously introduced with the goals of enabling virtual organisations (VO) and site-administrators to run validation tests of the site and software infrastructure in an automated or on-demand manner. The HammerCloud infrastructure has been constantly improved to support the addition of new test workflows. These new workflows comprise e.g. tests of the ATLAS nightly build system, ATLAS Monte Carlo production system, XRootD federation (FAX) and new site stress test workflows. We report on the development, optimization and results of the various components in the HammerCloud framework.

  2. Tonopah Test Range Environmental Restoration Corrective Action Sites

    International Nuclear Information System (INIS)

    Ronald B. Jackson

    2007-01-01

    Corrective Action Sites (CASs) and Corrective Action Units (CAUs) at the Tonopah Test Range (TTR) may be placed into three categories: Clean Closure/No Further Action, Closure in Place, or Closure in Progress

  3. Grid Site Testing for ATLAS with HammerCloud

    CERN Document Server

    Elmsheuser, J; The ATLAS collaboration; Legger, F; Medrano LLamas, R; Sciacca, G; van der Ster, D

    2014-01-01

    With the exponential growth of LHC (Large Hadron Collider) data in 2012, distributed computing has become the established way to analyze collider data. The ATLAS grid infrastructure includes more than 130 sites worldwide, ranging from large national computing centers to smaller university clusters. HammerCloud was previously introduced with the goals of enabling VO- and site-administrators to run validation tests of the site and software infrastructure in an automated or on-demand manner. The HammerCloud infrastructure has been constantly improved to support the addition of new test work-flows. These new work-flows comprise e.g. tests of the ATLAS nightly build system, ATLAS MC production system, XRootD federation FAX and new site stress test work-flows. We report on the development, optimization and results of the various components in the HammerCloud framework.

  4. Grid Site Testing for ATLAS with HammerCloud

    CERN Document Server

    Elmsheuser, J; The ATLAS collaboration; Legger, F; Medrano LLamas, R; Sciacca, G; van der Ster, D

    2013-01-01

    With the exponential growth of LHC (Large Hadron Collider) data in 2012, distributed computing has become the established way to analyze collider data. The ATLAS grid infrastructure includes more than 130 sites worldwide, ranging from large national computing centers to smaller university clusters. HammerCloud was previously introduced with the goals of enabling VO- and site-administrators to run validation tests of the site and software infrastructure in an automated or on-demand manner. The HammerCloud infrastructure has been constantly improved to support the addition of new test work-flows. These new work-flows comprise e.g. tests of the ATLAS nightly build system, ATLAS MC production system, XRootD federation FAX and new site stress test work-flows. We report on the development, optimization and results of the various components in the HammerCloud framework.

  5. New data on the Paleozoic of the Semipalatinsk test site

    International Nuclear Information System (INIS)

    Ergaliev, G.Kh.; Myasnikov, A.K.; Nikitin, I.F.; Polyanskij, N.V.; Sergeeva, L.V.; Sergieva, M.N.; Sal'menova, L.T.; Utegulov, M.T.; Tsaj, D.T.; Shuzhanov, V.M.

    1998-01-01

    The latest data on Paleozoic of the Semipalatinsk test site acquired as result of the stratigraphic and pale ontological investigation which have been conducted for the first time after 46-year interval in geological studies are presented. (author)

  6. Closure Report for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2009-01-01

    Corrective Action Unit (CAU) 107 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Low Impact Soil Sites' and consists of the following 15 Corrective Action Sites (CASs), located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site: CAS 01-23-02, Atmospheric Test Site - High Alt; CAS 02-23-02, Contaminated Areas (2); CAS 02-23-03, Contaminated Berm; CAS 02-23-10, Gourd-Amber Contamination Area; CAS 02-23-11, Sappho Contamination Area; CAS 02-23-12, Scuttle Contamination Area; CAS 03-23-24, Seaweed B Contamination Area; CAS 03-23-27, Adze Contamination Area; CAS 03-23-28, Manzanas Contamination Area; CAS 03-23-29, Truchas-Chamisal Contamination Area; CAS 04-23-02, Atmospheric Test Site T4-a; CAS 05-23-06, Atmospheric Test Site; CAS 09-23-06, Mound of Contaminated Soil; CAS 10-23-04, Atmospheric Test Site M-10; and CAS 18-23-02, U-18d Crater (Sulky). Closure activities were conducted from February through April 2009 according to the FFACO (1996; as amended February 2008) and Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 107 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2009). The corrective action alternatives included No Further Action and Closure in Place with Administrative Controls. Closure activities are summarized.

  7. Basic considerations for the preparation of performance testing materials as related to performance evaluation acceptance criteria

    International Nuclear Information System (INIS)

    McCurdy, D.E.; Morton, J.S.

    2001-01-01

    The preparation of performance testing (PT) materials for environmental and radiobioassay applications involves the use of natural matrix materials containing the analyte of interest, the addition (spiking) of the analyte to a desired matrix (followed by blending for certain matrices) or a combination of the two. The distribution of the sample analyte concentration in a batch of PT samples will reflect the degree of heterogeneity of the analyte in the PT material and/or the reproducibility of the sample preparation process. Commercial and government implemented radioanalytical performance evaluation programs have a variety of acceptable performance criteria. The performance criteria should take into consideration many parameters related to the preparation of the PT materials including the within and between sample analyte heterogeneity, the accuracy of the quantification of an analyte in the PT material and to what 'known' value will a laboratory's result be compared. How sample preparation parameters affect the successful participation in performance evaluation (PE) programs having an acceptance criteria established as a percent difference from a 'known' value or in PE programs using other acceptance criteria, such as the guidance provided in ANSI N42.22 and N13.30 is discussed. (author)

  8. SU-F-T-313: Clinical Results of a New Customer Acceptance Test for Elekta VMAT

    Energy Technology Data Exchange (ETDEWEB)

    Rusk, B; Fontenot, J [Mary Bird Perkins Cancer Center, Baton Rouge, LA (United States)

    2016-06-15

    Purpose: To report the results of a customer acceptance test (CAT) for VMAT treatments for two matched Elekta linear accelerators. Methods: The CAT tests were performed on two clinically matched Elekta linear accelerators equipped with a 160-leaf MLC. Functional tests included performance checks of the control system during dynamic movements of the diaphragms, MLC, and gantry. Dosimetric tests included MLC picket fence tests at static and variable dose rates and a diaphragm alignment test, all performed using the on-board EPID. Additionally, beam symmetry during arc delivery was measured at the four cardinal angles for high and low dose rate modes using a 2D detector array. Results of the dosimetric tests were analyzed using the VMAT CAT analysis tool. Results: Linear accelerator 1 (LN1) met all stated CAT tolerances. Linear accelerator 2 (LN2) passed the geometric, beam symmetry, and MLC position error tests but failed the relative dose average test for the diaphragm abutment and all three picket fence fields. Though peak doses in the abutment regions were consistent, the average dose was below the stated tolerance corresponding to a leaf junction that was too narrow. Despite this, no significant differences in patient specific VMAT quality assurance measured were observed between the accelerators and both passed monthly MLC quality assurance performed with the Hancock test. Conclusion: Results from the CAT showed LN2 with relative dose averages in the abutment regions of the diaphragm and MLC tests outside the tolerances resulting from differences in leaf gap distances. Tolerances of the dose average tests from the CAT may be small enough to detect MLC errors which do not significantly affect patient QA or the routine MLC tests.

  9. SU-F-T-313: Clinical Results of a New Customer Acceptance Test for Elekta VMAT

    International Nuclear Information System (INIS)

    Rusk, B; Fontenot, J

    2016-01-01

    Purpose: To report the results of a customer acceptance test (CAT) for VMAT treatments for two matched Elekta linear accelerators. Methods: The CAT tests were performed on two clinically matched Elekta linear accelerators equipped with a 160-leaf MLC. Functional tests included performance checks of the control system during dynamic movements of the diaphragms, MLC, and gantry. Dosimetric tests included MLC picket fence tests at static and variable dose rates and a diaphragm alignment test, all performed using the on-board EPID. Additionally, beam symmetry during arc delivery was measured at the four cardinal angles for high and low dose rate modes using a 2D detector array. Results of the dosimetric tests were analyzed using the VMAT CAT analysis tool. Results: Linear accelerator 1 (LN1) met all stated CAT tolerances. Linear accelerator 2 (LN2) passed the geometric, beam symmetry, and MLC position error tests but failed the relative dose average test for the diaphragm abutment and all three picket fence fields. Though peak doses in the abutment regions were consistent, the average dose was below the stated tolerance corresponding to a leaf junction that was too narrow. Despite this, no significant differences in patient specific VMAT quality assurance measured were observed between the accelerators and both passed monthly MLC quality assurance performed with the Hancock test. Conclusion: Results from the CAT showed LN2 with relative dose averages in the abutment regions of the diaphragm and MLC tests outside the tolerances resulting from differences in leaf gap distances. Tolerances of the dose average tests from the CAT may be small enough to detect MLC errors which do not significantly affect patient QA or the routine MLC tests.

  10. Multi-Canister Overpack (MCO) Combustible Gas Management Leak Test Acceptance Criteria (OCRWM)

    International Nuclear Information System (INIS)

    SHERRELL, D.L.

    2000-01-01

    The purpose of this document is to support the Spent Nuclear Fuel Project's combustible gas management strategy while avoiding the need to impose any requirements for oxygen free atmospheres within storage tubes that contain multi-canister overpacks (MCO). In order to avoid inerting requirements it is necessary to establish and confirm leak test acceptance criteria for mechanically sealed and weld sealed MCOs that are adequte to ensure that, in the unlikely event the leak test results for any MCO were to approach either of those criteria, it could still be handled and stored in stagnant air without compromising the SNF Project's overall strategy to prevent accumulation of combustible gas mixtures within MCOs or within their surroundings. To support that strategy, this document: (1) establishes combustible gas management functions and minimum functional requirements for the MCO's mechanical seals and closure weld(s); (2) establishes a maximum practical value for the minimum required initial MCO inert backfill gas pressure; and (3) based on items 1 and 2, establishes and confirms leak test acceptance criteria for the MCO's mechanical seal and final closure weld(s)

  11. Testing the validity and acceptability of the diagnostic criteria for Hoarding Disorder: a DSM-5 survey.

    Science.gov (United States)

    Mataix-Cols, D; Fernández de la Cruz, L; Nakao, T; Pertusa, A

    2011-12-01

    The DSM-5 Obsessive-Compulsive Spectrum Sub-Workgroup is recommending the creation of a new diagnostic category named Hoarding Disorder (HD). The validity and acceptability of the proposed diagnostic criteria have yet to be formally tested. Obsessive-compulsive disorder/hoarding experts and random members of the American Psychiatric Association (APA) were shown eight brief clinical vignettes (four cases meeting criteria for HD, three with hoarding behaviour secondary to other mental disorders, and one with subclinical hoarding behaviour) and asked to decide the most appropriate diagnosis in each case. Participants were also asked about the perceived acceptability of the criteria and whether they supported the inclusion of HD in the main manual. Altogether, 211 experts and 48 APA members completed the survey (30% and 10% response rates, respectively). The sensitivity and specificity of the HD diagnosis and the individual criteria were high (80-90%) across various types of professionals, irrespective of their experience with hoarding cases. About 90% of participants in both samples thought the criteria would be very/somewhat acceptable for professionals and sufferers. Most experts (70%) supported the inclusion of HD in the main manual, whereas only 50% of the APA members did. The proposed criteria for HD have high sensitivity and specificity. The criteria are also deemed acceptable for professionals and sufferers alike. Training of professionals and the development and validation of semi-structured diagnostic instruments should improve diagnostic accuracy even further. A field trial is now needed to confirm these encouraging findings with real patients in real clinical settings.

  12. Formulation of a candidate glass for use as an acceptance test standard material

    International Nuclear Information System (INIS)

    Ebert, W.L.; Strachan, D.M.; Wolf, S.F.

    1998-04-01

    In this report, the authors discuss the formulation of a glass that will be used in a laboratory testing program designed to measure the precision of test methods identified in the privatization contracts for the immobilization of Hanford low-activity wastes. Tests will be conducted with that glass to measure the reproducibility of tests and analyses that must be performed by glass producers as a part of the product acceptance procedure. Test results will be used to determine if the contractually required tests and analyses are adequate for evaluating the acceptability of likely immobilized low-activity waste (ILAW) products. They will also be used to evaluate if the glass designed for use in these tests can be used as an analytical standard test material for verifying results reported by vendors for tests withg ILAW products. The results of those tests and analyses will be presented in a separate report. The purpose of this report is to document the strategy used to formulate the glass to be used in the testing program. The low-activity waste reference glass LRM that will be used in the testing program was formulated to be compositionally similar to ILAW products to be made with wastes from Hanford. Since the ILAW product compositions have not been disclosed by the vendors participating in the Hanford privatization project, the composition of LRM was formulated based on simulated Hanford waste stream and amounts of added glass forming chemicals typical for vitrified waste forms. The major components are 54 mass % SiO 2 , 20 mass % Na 2 O, 10 mass % Al 2 O 3 , 8 mass % B 2 O 3 , and 1.5 mass % K 2 O. Small amounts of other chemicals not present in Hanford wastes were also included in the glass, since they may be included as chemical additives in ILAW products. This was done so that the use of LRM as a composition standard could be evaluated. Radionuclides were not included in LRM because a nonradioactive material was desired

  13. Commissioning and Acceptance Testing of the existing linear accelerator upgraded to volumetric modulated arc therapy

    Science.gov (United States)

    Varadharajan, Ekambaram; Ramasubramanian, Velayudham

    2013-01-01

    Aim The RapidArc commissioning and Acceptance Testing program will test and ensure accuracy in DMLC position, precise dose-rate control during gantry rotation and accurate control of gantry speed. Background Recently, we have upgraded our linear accelerator capable of performing IMRT which was functional from 2007 with image guided RapidArc facility. The installation of VMAT in the existing linear accelerator is a tedious process which requires many quality assurance procedures before the proper commissioning of the facility and these procedures are discussed in this study. Materials and methods Output of the machine at different dose rates was measured to verify its consistency at different dose rates. Monitor and chamber linearity at different dose rates were checked. DMLC QA comprising of MLC transmission factor measurement and dosimetric leaf gap measurements were performed using 0.13 cm3 and 0.65 cm3 Farmer type ionization chamber, dose 1 dosimeter, and IAEA 30 cm × 30 cm × 30 cm water phantom. Picket fence test, garden fence test, tests to check leaf positioning accuracy due to carriage movement, calibration of the leaves, leaf speed stability effects due to the acceleration and deceleration of leaves, accuracy and calibration of leaves in producing complex fields, effects of interleaf friction, etc. were verified using EDR2 therapy films, Vidar scanner, Omnipro accept software, amorphous silicon based electronic portal imaging device and EPIQA software.1–8 Results All the DMLC related quality assurance tests were performed and evaluated by film dosimetry, portal dosimetry and EPIQA.7 Conclusion Results confirmed that the linear accelerator is capable of performing accurate VMAT. PMID:24416566

  14. Commissioning and Acceptance Testing of the existing linear accelerator upgraded to volumetric modulated arc therapy.

    Science.gov (United States)

    Varadharajan, Ekambaram; Ramasubramanian, Velayudham

    2013-01-01

    The RapidArc commissioning and Acceptance Testing program will test and ensure accuracy in DMLC position, precise dose-rate control during gantry rotation and accurate control of gantry speed. Recently, we have upgraded our linear accelerator capable of performing IMRT which was functional from 2007 with image guided RapidArc facility. The installation of VMAT in the existing linear accelerator is a tedious process which requires many quality assurance procedures before the proper commissioning of the facility and these procedures are discussed in this study. Output of the machine at different dose rates was measured to verify its consistency at different dose rates. Monitor and chamber linearity at different dose rates were checked. DMLC QA comprising of MLC transmission factor measurement and dosimetric leaf gap measurements were performed using 0.13 cm(3) and 0.65 cm(3) Farmer type ionization chamber, dose 1 dosimeter, and IAEA 30 cm × 30 cm × 30 cm water phantom. Picket fence test, garden fence test, tests to check leaf positioning accuracy due to carriage movement, calibration of the leaves, leaf speed stability effects due to the acceleration and deceleration of leaves, accuracy and calibration of leaves in producing complex fields, effects of interleaf friction, etc. were verified using EDR2 therapy films, Vidar scanner, Omnipro accept software, amorphous silicon based electronic portal imaging device and EPIQA software.(1-8.) All the DMLC related quality assurance tests were performed and evaluated by film dosimetry, portal dosimetry and EPIQA.(7.) Results confirmed that the linear accelerator is capable of performing accurate VMAT.

  15. Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills

    2007-10-01

    The Nevada Test Site Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders.

  16. Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

    International Nuclear Information System (INIS)

    Cathy Wills

    2007-01-01

    The Nevada Test Site Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders

  17. Accuracy and user-acceptability of HIV self-testing using an oral fluid-based HIV rapid test.

    Directory of Open Access Journals (Sweden)

    Oon Tek Ng

    Full Text Available BACKGROUND: The United States FDA approved an over-the-counter HIV self-test, to facilitate increased HIV testing and earlier linkage to care. We assessed the accuracy of self-testing by untrained participants compared to healthcare worker (HCW testing, participants' ability to interpret sample results and user-acceptability of self-tests in Singapore. METHODOLOGY/PRINCIPAL FINDINGS: A cross-sectional study, involving 200 known HIV-positive patients and 794 unknown HIV status at-risk participants was conducted. Participants (all without prior self-test experience performed self-testing guided solely by visual instructions, followed by HCW testing, both using the OraQuick ADVANCE Rapid HIV 1/2 Antibody Test, with both results interpreted by the HCW. To assess ability to interpret results, participants were provided 3 sample results (positive, negative, and invalid to interpret. Of 192 participants who tested positive on HCW testing, self-testing was positive in 186 (96.9%, negative in 5 (2.6%, and invalid in 1 (0.5%. Of 794 participants who tested negative on HCW testing, self-testing was negative in 791 (99.6%, positive in 1 (0.1%, and invalid in 2 (0.3%. Excluding invalid tests, self-testing had sensitivity of 97.4% (95% CI 95.1% to 99.7% and specificity of 99.9% (95% CI: 99.6% to 100%. When interpreting results, 96%, 93.1% and 95.2% correctly read the positive, negative and invalid respectively. There were no significant demographic predictors for false negative self-testing or wrongly interpreting positive or invalid sample results as negative. Eighty-seven percent would purchase the kit over-the-counter; 89% preferred to take HIV tests in private. 72.5% and 74.9% felt the need for pre- and post-test counseling respectively. Only 28% would pay at least USD15 for the test. CONCLUSIONS/SIGNIFICANCE: Self-testing was associated with high specificity, and a small but significant number of false negatives. Incorrectly identifying model results as

  18. RFI to CMS: An Approach to Regulatory Acceptance of Site Remediation Technologies

    Science.gov (United States)

    Rowland, Martin A.

    2001-01-01

    Lockheed Martin made a smooth transition from RCRA Facility Investigation (RFI) at the National Aeronautics and Space Administrations'(NASA) Michoud Assembly Facility (MA-F) to its Corrective Measures Study (CMS) phase within the RCRA Corrective Action Process. We located trichloroethylene (TCE) contamination that resulted from the manufacture of the Apollo Program Saturn V rocket and the Space Shuttle External Tank, began the cleanup, and identified appropriate technologies for final remedies. This was accomplished by establishing a close working relationship with the state environmental regulatory agency through each step of the process, and resulted in receiving approvals for each of those steps. The agency has designated Lockheed Martin's management of the TCE-contamination at the MAF site as a model for other manufacturing sites in a similar situation. In February 1984, the Louisiana Department of Environmental Quality (LDEQ) issued a compliance order to begin the clean up of groundwater contaminated with TCE. In April 1984 Lockheed Martin began operating a groundwater recovery well to capture the TCE plume. The well not only removes contaminants, but also sustains an inward groundwater hydraulic gradient so that the potential offsite migration of the TCE plume is greatly diminished. This effort was successful, and for the agency to give orders and for a regulated industry to follow them is standard procedure, but this is a passive approach to solving environmental problems. The goal of the company thereafter was to take a leadership, proactive role and guide the MAF contamination clean up to its best conclusion at minimum time and lowest cost to NASA. To accomplish this goal, we have established a positive working relationship with LDEQ, involving them interactively in the implementation of advanced remedial activities at MAF as outlined in the following paragraphs.

  19. The Development of a Competency Testing Systems: Adopting TAM to Explore User’s Acceptance

    Directory of Open Access Journals (Sweden)

    Ibrahim Wahyu Saputra

    2017-12-01

    Full Text Available The main problems of learning evaluation using paper based-test are inefficient time and cost. Technology can be used as a system to evaluate the learning process. Using technology can save time and cost of implementing learning evaluations. The aims of this study are to create a software product that can be used to evaluate the learning process. This software product is designed to be used by the test organizer or test committee, the teachers and the students (test takers. This software product was developed using Waterfall Model with five stages of development; communication, planning, modeling, construction, and deployment. The testing was conducted by using Blackbox Method and TAM Theory by considering the aspect of usefulness and the aspect ease of use. The analysis was based on the flow of the current test system. The web-based platform enables ease of access for conducting work in various places. According to the result, the Developed Skills Competency Test System is accepted and can be used by the user as an evaluation system.

  20. Acceptance/operational test procedure 241-AN-107 Video Camera System

    International Nuclear Information System (INIS)

    Pedersen, L.T.

    1994-01-01

    This procedure will document the satisfactory operation of the 241-AN-107 Video Camera System. The camera assembly, including camera mast, pan-and-tilt unit, camera, and lights, will be installed in Tank 241-AN-107 to monitor activities during the Caustic Addition Project. The camera focus, zoom, and iris remote controls will be functionally tested. The resolution and color rendition of the camera will be verified using standard reference charts. The pan-and-tilt unit will be tested for required ranges of motion, and the camera lights will be functionally tested. The master control station equipment, including the monitor, VCRs, printer, character generator, and video micrometer will be set up and performance tested in accordance with original equipment manufacturer's specifications. The accuracy of the video micrometer to measure objects in the range of 0.25 inches to 67 inches will be verified. The gas drying distribution system will be tested to ensure that a drying gas can be flowed over the camera and lens in the event that condensation forms on these components. This test will be performed by attaching the gas input connector, located in the upper junction box, to a pressurized gas supply and verifying that the check valve, located in the camera housing, opens to exhaust the compressed gas. The 241-AN-107 camera system will also be tested to assure acceptable resolution of the camera imaging components utilizing the camera system lights

  1. Nuclear Materials Management for the Nevada Test Site (NTS)

    International Nuclear Information System (INIS)

    Jesse C. Schreiber

    2007-01-01

    The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

  2. Community acceptability of use of rapid diagnostic tests for malaria by community health workers in Uganda

    Directory of Open Access Journals (Sweden)

    Waiswa Peter

    2010-07-01

    Full Text Available Abstract Background Many malarious countries plan to introduce artemisinin combination therapy (ACT at community level using community health workers (CHWs for treatment of uncomplicated malaria. Use of ACT with reliance on presumptive diagnosis may lead to excessive use, increased costs and rise of drug resistance. Use of rapid diagnostic tests (RDTs could address these challenges but only if the communities will accept their use by CHWs. This study assessed community acceptability of the use of RDTs by Ugandan CHWs, locally referred to as community medicine distributors (CMDs. Methods The study was conducted in Iganga district using 10 focus group discussions (FGDs with CMDs and caregivers of children under five years, and 10 key informant interviews (KIIs with health workers and community leaders. Pre-designed FGD and KII guides were used to collect data. Manifest content analysis was used to explore issues of trust and confidence in CMDs, stigma associated with drawing blood from children, community willingness for CMDs to use RDTs, and challenges anticipated to be faced by the CMDs. Results CMDs are trusted by their communities because of their commitment to voluntary service, access, and the perceived effectiveness of anti-malarial drugs they provide. Some community members expressed fear that the blood collected could be used for HIV testing, the procedure could infect children with HIV, and the blood samples could be used for witchcraft. Education level of CMDs is important in their acceptability by the community, who welcome the use of RDTs given that the CMDs are trained and supported. Anticipated challenges for CMDs included transport for patient follow-up and picking supplies, adults demanding to be tested, and caregivers insisting their children be treated instead of being referred. Conclusion Use of RDTs by CMDs is likely to be acceptable by community members given that CMDs are properly trained, and receive regular technical

  3. Intra-site Secure Transport Vehicle test and evaluation

    International Nuclear Information System (INIS)

    Scott, S.

    1995-01-01

    In the past many DOE and DoD facilities involved in handling nuclear material realized a need to enhance the safely and security for movement of sensitive materials within their facility, or ''intra-site''. There have been prior efforts to improve on-site transportation; however, there remains a requirement for enhanced on-site transportation at a number of facilities. The requirements for on-site transportation are driven by security, safety, and operational concerns. The Intra-site Secure Transport Vehicle (ISTV) was designed to address these concerns specifically for DOE site applications with a standardized vehicle design. This paper briefly reviews the ISTV design features providing significant enhancement of onsite transportation safety and security, and also describes the test and evaluation activities either complete of underway to validate the vehicle design and operation

  4. Fruit and vegetable radioactivity survey, Nevada Test Site environs

    International Nuclear Information System (INIS)

    Andrews, V.E.; Vandervort, J.C.

    1978-04-01

    During the 1974 growing season, the Environmental Monitoring and Support Laboratory-Las Vegas, of the U.S. Environmental Protection Agency, collected samples of fruits and vegetables grown in the off-site area surrounding the Nevada Test Site. The objective was to estimate the potential radiological dose to off-site residents from consumption of locally grown foodstuffs. Irrigation water and soil were collected from the gardens and orchards sampled. Soil concentrations of cesium-137 and plutonium-239 reflected the effects of close-in fallout from nuclear testing at the Nevada Test Site. The only radionuclide measured in fruit and vegetable samples which might be related to such fallout was strontium-90, for which the first year estimated dose to bone marrow of an adult with an assumed rate of consumption of the food would be 0.14 millirad

  5. Evaluation Of ARG-1 Samples Prepared By Cesium Carbonate Dissolution During The Isolok SME Acceptability Testing

    International Nuclear Information System (INIS)

    Edwards, T.; Hera, K.; Coleman, C.

    2011-01-01

    Evaluation of Defense Waste Processing Facility (DWPF) Chemical Process Cell (CPC) cycle time identified several opportunities to improve the CPC processing time. The Mechanical Systems and Custom Equipment Development (MS and CED) Section of the Savannah River National Laboratory (SRNL) recently completed the evaluation of one of these opportunities - the possibility of using an Isolok sampling valve as an alternative to the Hydragard valve for taking DWPF process samples at the Slurry Mix Evaporator (SME). The use of an Isolok for SME sampling has the potential to improve operability, reduce maintenance time, and decrease CPC cycle time. The SME acceptability testing for the Isolok was requested in Task Technical Request (TTR) HLW-DWPF-TTR-2010-0036 and was conducted as outlined in Task Technical and Quality Assurance Plan (TTQAP) SRNLRP-2011-00145. RW-0333P QA requirements applied to the task, and the results from the investigation were documented in SRNL-STI-2011-00693. Measurement of the chemical composition of study samples was a critical component of the SME acceptability testing of the Isolok. A sampling and analytical plan supported the investigation with the analytical plan directing that the study samples be prepared by a cesium carbonate (Cs 2 CO 3 ) fusion dissolution method and analyzed by Inductively Coupled Plasma - Optical Emission Spectroscopy (ICP-OES). The use of the cesium carbonate preparation method for the Isolok testing provided an opportunity for an additional assessment of this dissolution method, which is being investigated as a potential replacement for the two methods (i.e., sodium peroxide fusion and mixed acid dissolution) that have been used at the DWPF for the analysis of SME samples. Earlier testing of the Cs 2 CO 3 method yielded promising results which led to a TTR from Savannah River Remediation, LLC (SRR) to SRNL for additional support and an associated TTQAP to direct the SRNL efforts. A technical report resulting from this

  6. Performance of the JT-60SA cryogenic system under pulsed heat loads during acceptance tests

    Science.gov (United States)

    Hoa, C.; Bonne, F.; Roussel, P.; Lamaison, V.; Girard, S.; Fejoz, P.; Goncalves, R.; Vallet, J. C.; Legrand, J.; Fabre, Y.; Pudys, V.; Wanner, M.; Cardella, A.; Di Pietro, E.; Kamiya, K.; Natsume, K.; Ohtsu, K.; Oishi, M.; Honda, A.; Kashiwa, Y.; Kizu, K.

    2017-12-01

    The JT-60SA cryogenic system a superconducting tokamak currently under assembly at Naka, Japan. After one year of commissioning, the acceptance tests were successfully completed in October 2016 in close collaboration with Air Liquide Advanced Technologies (ALaT), the French atomic and alternative energies commission (CEA), Fusion for Energy (F4E) and the Quantum Radiological Science and Technology (QST). The cryogenic system has several cryogenic users at various temperatures: the superconducting magnets at 4.4 K, the current leads at 50 K, the thermal shields at 80 K and the divertor cryo-pumps at 3.7 K. The cryogenic system has an equivalent refrigeration power of about 9.5 kW at 4.5 K, with peak loads caused by the nuclear heating, the eddy currents in the structures and the AC losses in the magnets during cyclic plasma operation. The main results of the acceptance tests will be reported, with emphasis on the management of the challenging pulsed load operation using a liquid helium volume of 7 m3 as a thermal damper.

  7. The Worlds First Ever Cooling Tower Acceptance Test Using Process Data Reconciliation

    International Nuclear Information System (INIS)

    Magnus Langenstein; Jan Hansen-Schmidt

    2006-01-01

    The cooling capacity of cooling towers is influenced by multiple constructive and atmospheric parameters in a very complex way. This leads to strong variations of the measured cold-water temperature and causes unacceptable unreliability of conventional acceptance tests, which are based on single point measurements. In order to overcome this lack of accuracy a new approach to acceptance test based on process data reconciliation has been developed by BTB Jansky and applied at a nuclear power plant. This approach uses process data reconciliation according to VDI 2048 to evaluate datasets over a long period covering different operating conditions of the cooling tower. Data reconciliation is a statistical method to determine the true process parameters with a statistical probability of 95% by considering closed material-, mass-and energy balances. Datasets which are not suitable for the evaluation due to strong transient gradients are excluded beforehand, according to well-defined criteria. The reconciled cold-water temperature is then compared, within a wet bulb temperature range of 5 deg. C to 20 deg. C to the manufacturer's guaranteed temperature. Finally, if the average deviation between reconciled and guaranteed value over the evaluated period is below zero, the cooling tower guarantee is fulfilled. (authors)

  8. The Careful Puppet Master: Reducing risk and fortifying acceptance testing with Jenkins CI

    Science.gov (United States)

    Smith, Jason A.; Richman, Gabriel; DeStefano, John; Pryor, James; Rao, Tejas; Strecker-Kellogg, William; Wong, Tony

    2015-12-01

    Centralized configuration management, including the use of automation tools such as Puppet, can greatly increase provisioning speed and efficiency when configuring new systems or making changes to existing systems, reduce duplication of work, and improve automated processes. However, centralized management also brings with it a level of inherent risk: a single change in just one file can quickly be pushed out to thousands of computers and, if that change is not properly and thoroughly tested and contains an error, could result in catastrophic damage to many services, potentially bringing an entire computer facility offline. Change management procedures can—and should—be formalized in order to prevent such accidents. However, like the configuration management process itself, if such procedures are not automated, they can be difficult to enforce strictly. Therefore, to reduce the risk of merging potentially harmful changes into our production Puppet environment, we have created an automated testing system, which includes the Jenkins CI tool, to manage our Puppet testing process. This system includes the proposed changes and runs Puppet on a pool of dozens of RedHat Enterprise Virtualization (RHEV) virtual machines (VMs) that replicate most of our important production services for the purpose of testing. This paper describes our automated test system and how it hooks into our production approval process for automatic acceptance testing. All pending changes that have been pushed to production must pass this validation process before they can be approved and merged into production.

  9. Webinar Training: an acceptable, feasible and effective approach for multi-site medical record abstraction: the BOWII experience

    Directory of Open Access Journals (Sweden)

    St Charles Meaghan

    2011-10-01

    95% agreement across sites. Conclusions Conducting training via web-based technology was an acceptable and effective approach to standardizing medical record review across multiple sites for this group of experienced abstractors. Given the substantial time and cost savings achieved with the webinar, coupled with participants' positive evaluation of the training session, researchers should consider this instructional method as part of training efforts to ensure high quality data collection in multi-site studies.

  10. Tank Monitor and Control System sensor acceptance test procedure. Revision 6

    International Nuclear Information System (INIS)

    Scaief, C.C. III.

    1994-01-01

    The purpose of this Acceptance Test Procedure (ATP) is to verify the correct reading of sensor elements connected to the Tank Monitor and Control System (TMACS). The system functional requirements are contained in WHC-SD-WM-RD-013, Rev. 1 (WHC 1992a). This ATP is intended to be used for testing of the connection of existing temperature sensors, new temperature sensors, pressure sensing equipment, new Enraf level gauges, sensors that generate a current output, and discrete (on/off) inputs. The TMACS operation was verified by the original ATP (WHC 1991 c). It is intended that this ATP will be used each time sensors are added to the system. As a result, the data sheets have been designed to be generic

  11. Tank Monitor and Control System sensor acceptance test procedure. Revision 5

    International Nuclear Information System (INIS)

    Scaief, C.C. III.

    1994-01-01

    The purpose of this acceptance test procedure (ATP) is to verify the correct reading of sensor elements connected to the Tank Monitor and Control System (TMACS). This ATP is intended to be used for testing of the connection of existing temperature sensors, new temperature sensors, pressure sensing equipment, new Engraf level gauges, sensors that generate a current output, and discrete (on/off) inputs. It is intended that this ATP will be used each time sensors are added to the system. As a result, the data sheets have been designed to be generic. The TMACS has been designed in response to recommendations from the Defense Nuclear Facilities Safety Board primarily for improved monitoring of waste tank temperatures. The system has been designed with the capability to monitor other types of sensor input as well

  12. BIOMETRICAL CHARACTERIZATION OF TEST SITES FOR MAIZE BREEDING

    Directory of Open Access Journals (Sweden)

    Domagoj Šimić

    2003-12-01

    Full Text Available Yield stability of genotypes and analysis of genotype×environment interaction (GEI as important objects in analyses of multienvironment trials are well documented in Croatia. However, little is known about suitability and biometrical characters of the sites where genotypes should be tested. Objectives of this study were in combined analysis of balanced maize trials i to compare test sites in joint linear regression analysis and ii to compare several stability models by clustering test sites in order to assess biometrical suitability of particular test sites. Partitioning of GEI sum of squares according to the symmetrical joint linear regression analysis revealed highly significant Tukey's test, heterogeneity of environmental regressions and residual deviations. Mean grain yields, within-macroenvironment error mean squares, and stability parameters varied considerably among 16 macroenvironments. The highest grain yields were recorded in Osijek in both years and in Varaždin in 1996, with more than 11 t ha-1 . It seems that Feričanci would be optimum test site with relatively high and consistent yield and high values of entry mean squares indicating satisfactory differentiation among cultivars. However, four clustering methods generally did not correspond. According to three out of four clustering methods, two macroenvironments of Feričanci provide similar results. Employing other methods such as shifted multiplicative models, which effectively eliminate significant rank-change interaction, appears to be more reasonable.

  13. Acceptance testing and commissioning of Kodak Directview CR-850 digital radiography system.

    Science.gov (United States)

    Bezak, E; Nelligan, R A

    2006-03-01

    This Technical Paper describes Acceptance Testing and Commissioning of the Kodak DirectView CR-850 digital radiography system installed at the Royal Adelaide Hospital. The first of its type installed in Australia, the system is a "dry" image processor, for which no chemicals are required to develop images. Rather, latent radiographic images are stored on photostimulable phosphor screens, which are scanned and displayed by a reader unit. The image can be digitally processed and enhanced before it is forwarded to a storage device, printer or workstation display, thereby alleviating the need to re-expose patients to achieve satisfactory quality images. The phosphor screens are automatically erased, ready for re-use. Results are reported of tests carried out using the optional "Total Quality Tool" quality assurance package installed with the system. This package includes analysis and reporting software which provides for simple testing and reporting of many important characteristics of the system, such as field uniformity, aspect ratio, line and pixel positions, image and system noise, exposure response, scan linearity, modulation transfer function (MTF) and image artefacts. Acceptance Tests were performed for kV and MV exposures. Resolution for MV exposures was at least 0.8 l/mm, and measured phantom dimensions were within 1.05% of expected magnification. Reproducibility between cassettes was within 1.6%. The mean pixel values on the central axis were close to linear for MV exposures from 3 to 10 MU and reached saturation level at around 20 MU for 6 MV and around 30 MV for 23 MV beams. Noise levels were below 0.2 %.

  14. Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations

    International Nuclear Information System (INIS)

    Carilli, J.T.; Krenzien, S.K.; Geisinger, R.G.; Gordon, S.J.; Quinn, B.

    2009-01-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams

  15. 241-AZ-101 Mixer Pump Demonstration Test Gamma Cart Acceptance Test Procedure and Quality Test Plan (ATP and QTP)

    International Nuclear Information System (INIS)

    WHITE, D.A.

    2000-01-01

    Shop test of the sludge mobilization cart system to be used in the AZ-101 Mixer Pump Demonstration Test Tests hardware and software. This procedure involves testing the Instrumentation involved with the Gamma Cart System, local and remote, including depth indicators, speed controls, interface to data acquisition software and the raising and lowering functions. This Procedure will be performed twice, once for each Gamma Cart System. This procedure does not test the accuracy of the data acquisition software

  16. 241-AZ-101 Mixer Pump Demonstration Test Gamma Cart Acceptance Test Procedure and Quality Test Plan (ATP and QTP)

    International Nuclear Information System (INIS)

    WHITE, D.A.

    2000-01-01

    Shop Test of the Gamma Cart System to be used in the AZ-101 Mixer Pump Demonstration Test. Tests hardware and software. This procedure involves testing the Instrumentation involved with the Gamma Cart System, local and remote, including: depth indicators, speed controls, interface to data acquisition software and the raising and lowering functions. This Procedure will be performed twice, once for each Gamma Cart System. This procedure does not test the accuracy of the data acquisition software

  17. Defense waste management operations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Williams, R.E.; Kendall, E.W.

    1988-01-01

    Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types

  18. Defense waste management operations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Williams, R.E.; Kendall, E.W.

    1988-01-01

    Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class-C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types. The paper discusses site selection; establishment of the Radioactive Waste Management Project; operations with respect to low-level radioactive wastes, transuranic waste storage, greater confinement disposal test, and mixed waste management facility; and related research activities such as tritium migration studies, revegetation studies, and in-situ monitoring of organics

  19. Closure report for CAU No. 450: Historical UST release sites, Nevada Test Site. Volume 1

    International Nuclear Information System (INIS)

    1997-09-01

    This report addresses the closure of 11 historical underground storage tank (UST) release sites within various areas of the Nevada Test Site (NTS). The closure of each hydrocarbon release has not been documented, therefore, this report addresses the remedial activities completed for each release site. The hydrocarbon release associated with each tank site within CAU 450 was remediated by excavating the impacted soil. Clean closure of the release was verified through soil sample analysis by an off-site laboratory. All release closure activities were completed following standard environmental and regulatory guidelines. Based upon site observations during the remedial activities and the soil sample analytical results, which indicated that soil concentrations were below the Nevada Administrative code (NAC) Action Level of 100 mg/kg, it is anticipated that each of the release CASs be closed without further action

  20. Is it acceptable to approach colorectal cancer patients at diagnosis to discuss genetic testing? A pilot study

    OpenAIRE

    Porteous, M; Dunckley, M; Appleton, S; Catt, S; Dunlop, M; Campbell, H; Cull, A

    2003-01-01

    In this pilot study, the acceptability of approaching 111 newly diagnosed colorectal cancer patients with the offer of genetic testing for hereditary nonpolyposis colorectal cancer (HNPCC) was assessed. A total of 78% of participants found it highly acceptable to have the information about HNPCC brought to their attention at that time.

  1. Acceptance testing of Siemens e.cam SPECT system at the Korle-Bu Teaching Hospital

    International Nuclear Information System (INIS)

    Sosu, K. E.

    2006-01-01

    Acceptance testing has been performed on the Siemens e.cam Signature Series (Single Head) Single Photon Emission Computed Tomography (SPECT) system; the first of its kind, at the Nuclear Medicine Department, Korle-Bu Teaching Hospital, Accra. The various tests were performed according to NEMA NU 1 (2001) specifications as far as possible. The most important parameters that characterized the performance of the camera, gantry system, patient bed, collimators, computer system and fundamental software were evaluated based on visual inspection techniques. Various measuring instruments, different kinds of phantoms, point and flood sources containing 99m-Tc were also used for quantitative studies. Tests performed were divided into Physical inspection, intrinsic measurements (without collimator), extrinsic measurements (with collimator) and Single Photon Emission Computed Tomography (SPECT) system measurement. Some results obtained were better than factory specifications, others were within specifications. Other results obtained from this study which did not have factory specifications for comparison can serve as baseline for future measurements and quality control. Although not all the tests originally planned for could be done due to the non-availability of certain phantoms and radionuclide, it had been possible to perform sufficient and relevant tests to ensure that the system had no serious problems and that it can be used for clinical nuclear medicine imaging. (au)

  2. A review of acceptance testing of the Los Alamos, Canberra Alpha Sentry Continuous Air Monitor (CAM)

    International Nuclear Information System (INIS)

    Rodgers, J.C.

    1998-01-01

    Los Alamos National Laboratory (LANL) undertook the design and development of a new generation of alpha continuous air monitor (CAM) instrumentation that would incorporate advanced technologies in the design of the sampling inlet, multi-channel analyzer (MCA) electronics, solid state alpha detectors, radon background interference suppression, background interference compensation and based on spectral analysis, and microcomputer based data communication, processing, storage, and retrieval. The ANSI air monitoring instrument standards (Performance Specifications for Health Physics Instrumentation -- Occupational Airborne Radioactivity Monitoring Instrumentation, N42.17B) specify performance criteria and testing procedures for instruments and instrument systems designed to continuously sample and quantify airborne radioactivity in the workplace. Although the intent of the standard is to provide performance testing criteria for type testing, it is appropriate to evaluate the performance of a new instrument such as the Alpha Sentry against certain of these criteria for purposes of an acceptance test based on stated specifications and the Los Alamos CAM Requirements document. This report provides an overview of the results of these tests, as they pertain to instruments designed to detect alpha-emitting radionuclides in particulate form

  3. On the population dose around the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Hill, P.; Dederichs, H.; Ostapczuk, P.; Hille, R.; Artemev, O.; Ptitskaya, L.; Akhmetov, M.; Pivovarov, S.

    2002-01-01

    Since 1949 the Semipalatinsk Nuclear Test Site (NTS) was extensively used by the former Soviet government as a testing range for atomic weapons. Atmospheric and underground tests were finally stopped in 1962 and 1989, respectively. The Ministry of the Russian Federation of Atomic Energy officially counts a total of 456 tests, including 116 atmospheric tests. The total yield of the nuclear explosions carried out was 6.3 Megatons equivalent with 6.7 PetaBq of 1 37C s and 3.7 PetaBq of 9 0S r being released into the athmosphere. Some of the athmospheric radioactive tests shielded plumes, which extended far beyond the outer borders of the NTS. Already the first Soviet atomic bomb test on August 29, 1949 due to unfavourable meteorological conditions affected the villages of Dolon and Moistik. Since 1995 joint investigations performed by the Research Centre Julich in cooperation with the Kazakh National Nuclear Centre in the region of the former nuclear test site near Semipalatinsk besides environmental measurents also involve the assessment of the current dose of the population at and around the test site in addition to the important retrospective determination of the dose of persons affected by the atmospheric tests

  4. Measured data from the Avery Island Site C heater test

    International Nuclear Information System (INIS)

    Waldman, H.; Stickney, R.G.

    1984-11-01

    Over the past six years, a comprehensive field testing program was conducted in the Avery Island salt mine. Three single canister heater tests were included in the testing program. Specifically, electric heaters, which simulate canisters of heat-generating nuclear waste, were placed in the floor of the Avery Island salt mine, and measurements were made of the response of the salt to heating. These tests were in operation by June 1978. One of the three heater tests, Site C, operated for a period of 1858 days and was decommissioned during July and August 1983. This data report presents the temperature and displacement data gathered during the operation and decommissioning of the Site C heater test. The purpose of this data report is to transmit the data to the scientific community. Rigorous analysis and interpretation of the data are considered beyond the scope of a data report. 6 references, 21 figures, 1 table

  5. SU-E-P-46: Clinical Acceptance Testing and Implementation of a Portable CT Unit

    International Nuclear Information System (INIS)

    LaFrance, M; Marsh, S; Hicks, R; O’Donnell-Moran, G

    2015-01-01

    Purpose: Planning for the first installation in New England of a new portable CT unit to be used in the Operating Room required the integration of many departments including Surgery, Neurosurgery, Information Services, Clinical Engineering, Radiology and Medical Physics/Radiation Safety. Acceptance testing and the quality assurance procedures were designed to optimize image quality and patient and personnel radiation exposure. Methods: The vendor’s protocols were tested using the CT Dosimetry phantoms. The system displayed the CTDIw instead of the CTDIvol while testing the unit. Radiation exposure was compared to existing CT scanners from installed CT units throughout the facility. Brainlab measures all 4 periphery slots on the CT Dosimetry phantom. The ACR measures only the superior slot for the periphery measurement. A comprehensive radiation survey was also performed for several locations. Results: The CTDIvol measurements were comparable for the following studies: brain, C-Spine, and sinuses. However, the mobile CT measurements were slightly higher than other CT units but within acceptable tolerance if measured using the ACR method.Based on scatter measurements, it was determined if any personnel were to stay in the OR Suite during image acquisition that the appropriate lead apron and thyroid shields had to be worn.In addition, to reduce unnecessary scatter, there were two mobile 6 foot wide shields (1/16″ lead equivalent) available to protect personnel in the room and adjacent areas. Conclusion: Intraoperative CT provides the physician new opportunities for evaluation of the progression of surgical resections and device placement at the cost of increasing the amount of trained personnel required to perform this procedure. It also brings with it challenges to keep the radiation exposure to the patients and staff within reasonable limits

  6. SU-E-P-46: Clinical Acceptance Testing and Implementation of a Portable CT Unit

    Energy Technology Data Exchange (ETDEWEB)

    LaFrance, M; Marsh, S; Hicks, R; O’Donnell-Moran, G [Baystate Health Systems, Inc., Springfield, MA (United States)

    2015-06-15

    Purpose: Planning for the first installation in New England of a new portable CT unit to be used in the Operating Room required the integration of many departments including Surgery, Neurosurgery, Information Services, Clinical Engineering, Radiology and Medical Physics/Radiation Safety. Acceptance testing and the quality assurance procedures were designed to optimize image quality and patient and personnel radiation exposure. Methods: The vendor’s protocols were tested using the CT Dosimetry phantoms. The system displayed the CTDIw instead of the CTDIvol while testing the unit. Radiation exposure was compared to existing CT scanners from installed CT units throughout the facility. Brainlab measures all 4 periphery slots on the CT Dosimetry phantom. The ACR measures only the superior slot for the periphery measurement. A comprehensive radiation survey was also performed for several locations. Results: The CTDIvol measurements were comparable for the following studies: brain, C-Spine, and sinuses. However, the mobile CT measurements were slightly higher than other CT units but within acceptable tolerance if measured using the ACR method.Based on scatter measurements, it was determined if any personnel were to stay in the OR Suite during image acquisition that the appropriate lead apron and thyroid shields had to be worn.In addition, to reduce unnecessary scatter, there were two mobile 6 foot wide shields (1/16″ lead equivalent) available to protect personnel in the room and adjacent areas. Conclusion: Intraoperative CT provides the physician new opportunities for evaluation of the progression of surgical resections and device placement at the cost of increasing the amount of trained personnel required to perform this procedure. It also brings with it challenges to keep the radiation exposure to the patients and staff within reasonable limits.

  7. Design verification and acceptance tests of the ASST-A helium refrigeration system

    International Nuclear Information System (INIS)

    Ganni, V.; Apparao, T.V.V.R.

    1993-07-01

    Three similar helium refrigerator systems have been installed at the Superconducting Super Collider Laboratory (SSCL) N15 site; the ASST-A system, which will be used for the accelerator system's full cell string test; the N15-B system, which will be used for string testing in the tunnel; and a third plant, dedicated to magnet testing at the Magnet Testing Laboratory. The ASST-A and N15-B systems will ultimately be a part of the collider's N15 sector station equipment. Each of these three systems has many subsystems, but the design basis for the main refrigerator is the same. Each system has a guaranteed capacity of 2000 W of refrigeration and 20 g/s liquefaction at 4.5K. The testing and design verification of the ASST-A refrigeration system consisted of parametric tests on the compressors and the total system. A summary of the initial performance test data is given in this paper. The tests were conducted for two cases: in the first, all four compressors were operating; in the second, only one compressor in each stage was operating. In each case, tests were conducted in three modes of operation described later on. The process design basis supplied by the manufacturers and used in the design of the main components -- the compressor, and expanders and heat exchangers for the coldbox -- were used to reduce the actual test data using process simulation methodology. In addition, the test results and the process design submitted by the manufacturer were analyzed using exergy analysis. This paper presents both the process and the exergy analyses of the manufacturer's design and the actual test data for Case 1. The process analyses are presented in the form of T-S diagrams. The results of the exergy analyses comparing the exergy losses of each component and the total system for the manufacturer's design and the test data are presented in the tables

  8. Hanford Site physical separations CERCLA treatability test plan

    International Nuclear Information System (INIS)

    1992-03-01

    This test plan describes specifications, responsibilities, and general procedures to be followed to conduct a physical separations soil treatability test in the North Process Pond of the 300-FF-1 Operable Unit at the Hanford Site, Washington. The objective of this test is to evaluate the use of physical separation systems as a means of concentrating chemical and radioactive contaminants into fine soil fractions and thereby minimizing waste volumes. If successful the technology could be applied to clean up millions of cubic meters of contaminated soils in waste sites at Hanford and other sites. It is not the intent of this test to remove contaminated materials from the fine soils. Physical separation is a simple and comparatively low cost technology to potentially achieve a significant reduction in the volume of contaminated soils. Organic contaminants are expected to be insignificant for the 300-FF-I Operable Unit test, and further removal of metals and radioactive contaminants from the fine fraction of soils will require secondary treatment such as chemical extraction, electromagnetic separation, or other technologies. Additional investigations/testing are recommended to assess the economic and technical feasibility of applying secondary treatment technologies, but are not within the scope of this test. This plan provides guidance and specifications for the treatability test to be conducted as a service contract. More detailed instructions and procedures will be provided as part of the vendors (sellers) proposal. The procedures will be approved by Westinghouse Hanford Company (Westinghouse Hanford) and finalized by the seller prior to initiating the test

  9. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Wickline, Alfred

    2005-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

  10. Overview of software development at the parabolic dish test site

    Science.gov (United States)

    Miyazono, C. K.

    1985-01-01

    The development history of the data acquisition and data analysis software is discussed. The software development occurred between 1978 and 1984 in support of solar energy module testing at the Jet Propulsion Laboratory's Parabolic Dish Test Site, located within Edwards Test Station. The development went through incremental stages, starting with a simple single-user BASIC set of programs, and progressing to the relative complex multi-user FORTRAN system that was used until the termination of the project. Additional software in support of testing is discussed including software in support of a meteorological subsystem and the Test Bed Concentrator Control Console interface. Conclusions and recommendations for further development are discussed.

  11. Understanding Student Teachers’ Behavioural Intention to Use Technology: Technology Acceptance Model (TAM Validation and Testing

    Directory of Open Access Journals (Sweden)

    Kung-Teck, Wong

    2013-01-01

    Full Text Available This study sets out to validate and test the Technology Acceptance Model (TAM in the context of Malaysian student teachers’ integration of their technology in teaching and learning. To establish factorial validity, data collected from 302 respondents were tested against the TAM using confirmatory factor analysis (CFA, and structural equation modelling (SEM was used for model comparison and hypotheses testing. The goodness-of-fit test of the analysis shows partial support of the applicability of the TAM in a Malaysian context. Overall, the TAM accounted for 37.3% of the variance in intention to use technology among student teachers and of the five hypotheses formulated, four are supported. Perceived usefulness is a significant influence on attitude towards computer use and behavioural intention. Perceived ease of use significantly influences perceived usefulness, and finally, behavioural intention is found to be influenced by attitude towards computer use. The findings of this research contribute to the literature by validating the TAM in the Malaysian context and provide several prominent implications for the research and practice of technology integration development.

  12. Evaluation of CCTF Core-II second acceptance Test C2-AC2 (Run 052)

    International Nuclear Information System (INIS)

    Okubo, Tsutomu; Murao, Yoshio

    1984-03-01

    In order to investigate the thermo-hydrodynamic behavior in a PWR during the reflood phase of the LOCA, large scale reflooding tests have been conducted at JAERI using the CCTF Core-I and Core-II facilities. This report presents the investigation on the difference in the thermo-hydrodynamic behavior observed between in the CCTF Core-I and Core-II facilities. For this purpose the test data of the second CCTF Core-II acceptance test C2-AC2 (Run 052) were evaluated by using the data of the Test CL-21 (Run 040) in the Core-I test series. The experimental conditions for these two tests were almost identical. Comparing the data of those two tests, the following is obtained. 1. The system behavior observed in the Core-II facility was nearly identical to that observed in the Core-I facility. 2. The core behavior observed in the Core-II facility was also nearly identical to that observed in the Core-I facility except for the top quenching behavior. 3. The differences in the top quenching behavior between the two facilities were as follows: (1) The selective occurrence of top quenching below the open holes of the upper core support plate observed in the Core-I facility was not observed in the Core-II facility. (2) Top quenching tended to occur less in the Core-II facility in the region where the initial average linear power density was over 1.69 kW/m. (author)

  13. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    International Nuclear Information System (INIS)

    2010-01-01

    the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325, Nevada Test Site Waste Acceptance Criteria (NTSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NTS Class III Permit and the NTSWAC.

  14. Preliminary site design for the SP-100 ground engineering test

    International Nuclear Information System (INIS)

    Cox, C.M.; Miller, W.C.; Mahaffey, M.K.

    1986-04-01

    In November, 1985, Hanford was selected by the Department of Energy (DOE) as the preferred site for a full-scale test of the integrated nuclear subsystem for SP-100. The Hanford Engineering Development Laboratory, operated by Westinghouse Hanford Company, was assigned as the lead contractor for the Test Site. The nuclear subsystem, which includes the reactor and its primary heat transport system, will be provided by the System Developer, another contractor to be selected by DOE in late FY-1986. In addition to reactor operations, test site responsibilities include preparation of the facility plus design, procurement and installation of a vacuum chamber to house the reactor, a secondary heat transport system to dispose of the reactor heat, a facility control system, and postirradiation examination. At the conclusion of the test program, waste disposal and facility decommissioning are required. The test site must also prepare appropriate environmental and safety evaluations. This paper summarizes the preliminary design requirements, the status of design, and plans to achieve full power operation of the test reactor in September, 1990

  15. Factors predicting the acceptance of herpes simplex virus type 2 antibody testing among adolescents and young adults.

    Science.gov (United States)

    Zimet, Gregory D; Rosenthal, Susan L; Fortenberry, J Dennis; Brady, Rebecca C; Tu, Wanzhu; Wu, Jingwei; Bernstein, David I; Stanberry, Lawrence R; Stone, Katherine M; Leichliter, Jami S; Fife, Kenneth H

    2004-11-01

    The rates and determinants of acceptance of herpes simplex virus type 2 (HSV-2) testing have not been adequately studied. The objective of this study was to identify factors associated with acceptance of HSV-2 antibody testing in individuals with no history of genital herpes. We conducted a cross-sectional survey study followed by the offer of free HSV-2 serologic testing at an urban sexually transmitted disease (STD) clinic, 2 general adult medical clinics, an urban university campus, and an urban adolescent medicine clinic. A total of 1199 individuals aged 14 to 30 years completed the survey and were offered testing. A total of 68.4% accepted HSV-2 testing. Factors independently associated with acceptance were female sex, older age, having an STD history, having 1 or more sexual partners in the last 6 months, perceived vulnerability to HSV-2 infection, and perceived benefits of HSV-2 testing. Fear of needles predicted rejection of testing, as did attending a general medical clinic versus an STD clinic and nonwhite race. There is a substantial interest in HSV-2 antibody testing across a variety of settings. Those at greatest behavioral and historic risk for HSV-2 infection, women, and persons whose health beliefs are consistent with testing are more likely to accept serologic testing when it is offered.

  16. Full-Scale Cask Testing and Public Acceptance of Spent Nuclear Fuel Shipments - 12254

    Energy Technology Data Exchange (ETDEWEB)

    Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge Northridge, CA 91330 (United States)

    2012-07-01

    Full-scale physical testing of spent fuel shipping casks has been proposed by the National Academy of Sciences (NAS) 2006 report on spent nuclear fuel transportation, and by the Presidential Blue Ribbon Commission (BRC) on America's Nuclear Future 2011 draft report. The U.S. Nuclear Regulatory Commission (NRC) in 2005 proposed full-scale testing of a rail cask, and considered 'regulatory limits' testing of both rail and truck casks (SRM SECY-05-0051). The recent U.S. Department of Energy (DOE) cancellation of the Yucca Mountain project, NRC evaluation of extended spent fuel storage (possibly beyond 60-120 years) before transportation, nuclear industry adoption of very large dual-purpose canisters for spent fuel storage and transport, and the deliberations of the BRC, will fundamentally change assumptions about the future spent fuel transportation system, and reopen the debate over shipping cask performance in severe accidents and acts of sabotage. This paper examines possible approaches to full-scale testing for enhancing public confidence in risk analyses, perception of risk, and acceptance of spent fuel shipments. The paper reviews the literature on public perception of spent nuclear fuel and nuclear waste transportation risks. We review and summarize opinion surveys sponsored by the State of Nevada over the past two decades, which show consistent patterns of concern among Nevada residents about health and safety impacts, and socioeconomic impacts such as reduced property values along likely transportation routes. We also review and summarize the large body of public opinion survey research on transportation concerns at regional and national levels. The paper reviews three past cask testing programs, the way in which these cask testing program results were portrayed in films and videos, and examines public and official responses to these three programs: the 1970's impact and fire testing of spent fuel truck casks at Sandia National

  17. Political aspects of nuclear test effects at Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Sydykov, E.B.; Panin, M.S.

    2003-01-01

    The paper describes tense struggle of Kazakhstan people for closure of the Semipalatinsk Nuclear Test Site. It reveals major foreign policy aspects and nuclear test effects for both Kazakhstan and the world community. (author)

  18. History of creation of Semipalatinsk test nuclear site. Chapter 1

    International Nuclear Information System (INIS)

    1999-01-01

    In 1949 August USSR's Government adopted decision about creation of nuclear site with conditional name Uchebnyj polygon 2. For its building was chosen territory in 140 km from Semipalatinsk city. Semipalatinsk test site consists of the land of three regions: Semipalatinsk, Pavlodar, Karaganda and it occupies 18,500 km 2 of fertile land, rich with minerals. Now this territory was alienated from national using. Polygon was complex object and it incorporated three main zones: Opytnoe Pole, zone of radiation safety, site Sh. Opytnoe Pole was equipped by special constructions ensuring nuclear test conducting, its observing and registration of physical measurements and occupied 2,300 km 2 . Around of the Opytnoe Pole is situated zone of radiation safety with area 45 thousand ha. Site Sh was situated in 14 km from center of Opytnoe Pole and it was intended for distribution of individual protection devices, dosimeters and for conducting of dis-activation and sanitary works. History of the site creation is connected with building of Kurchatov city. In dozen and hundred of kilometers from Kurchatov city there were top secret objects: site Balapan with total area 100,000 ha intended for conducting of nuclear tests in wells with threshold capacity 100-200 kt. Here simultaneously with main problems on the site the military-applied works were conducted on mechanics, physics of combustion, simulation of Earthquakes and determination of seismic stability of buildings and constructions. Research site Degelen with total area 33,100 ha which has been used for underground testing of nuclear charges with small capacity. Site 10 one of large research technical complex on which two reactor units were installed. Main tasks of the complex were as follows: high-temperature fuel materials testing, conducting of fundamental researches in field of physics of fissile products, thermal physics and gas hydrodynamics. On site M a laboratory base for radiochemical, radiological and chemical

  19. Closure report for CAU No. 450: Historical UST release sites, Nevada Test Site. Volume 2

    International Nuclear Information System (INIS)

    1997-09-01

    This report addresses the closure of 11 historical underground storage tank release sites within various areas of the Nevada Test Site. This report contains remedial verification of the soil sample analytical results for the following: Area 11 Tweezer facility; Area 12 boiler house; Area 12 service station; Area 23 bypass yard; Area 23 service station; Area 25 power house; Area 25 tech. services building; Area 25 tech. operations building; Area 26 power house; and Area 27 boiler house

  20. Resource Conservation and Recovery Act Industrial Sites quality assurance project plan: Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1994-06-01

    This quality assurance project plan (QAPjP) describes the measures that shall be taken to ensure that the environmental data collected during characterization and closure activities of Resource Conservation and Recovery Act (RCRA) Industrial Sites at the Nevada Test Site (NTS) are meaningful, valid, defensible, and can be used to achieve project objectives. These activities are conducted by the US Department of Energy Nevada Operations Office (DOE/NV) under the Nevada Environmental Restoration (ER) Project. The Nevada ER Project consists of environmental restoration activities on the NTS, Tonopah Test Range, Nellis Air Force Range, and eight sites in five other states. The RCRA Industrial Sites subproject constitutes a component of the Nevada ER Project. Currently, this QAPjP is limited to the seven RCRA Industrial Sites identified within this document that are to be closed under an interim status and pertains to all field- investigation, analytical-laboratory, and data-review activities in support of these closures. The information presented here supplements the RCRA Industrial Sites Project Management Plan and is to be used in conjunction with the site-specific subproject sampling and analysis plans

  1. Radioactive contamination of former Semipalatinsk test site area

    International Nuclear Information System (INIS)

    Artem'ev, O.I.; Akhmetov, M.A.; Ptitskaya, L.D.

    2001-01-01

    The nuclear weapon infrastructure elimination activities and related surveys of radioactive contamination are virtually accomplished at the Semipalatinsk test site (STS). The radioecological surveys accompanied closure of tunnels which were used for underground nuclear testing at Degelen technical field and elimination of intercontinental ballistic missile silo launchers at Balapan technical field. At the same time a ground-based route survey was carried out at the Experimental Field where aboveground tests were conducted and a ground-based area survey was performed in the south of the test site where there are permanent and temporary inhabited settlements. People dwelling these settlements are mainly farmers. The paper presents basic results of radiological work conducted in the course of elimination activities. (author)

  2. Who accepts a rapid HIV antibody test? The role of race/ethnicity and HIV risk behavior among community adolescents.

    Science.gov (United States)

    Swenson, Rebecca R; Hadley, Wendy S; Houck, Christopher D; Dance, S Kwame; Brown, Larry K

    2011-05-01

    Centers for Disease Control and Prevention guidelines recommend routine human immunodeficiency virus (HIV) screening in health care settings for all individuals aged 13-64 years; however, overall testing rates among adolescents still continue to remain low. This study examined factors related to the acceptance of HIV testing among an at-risk sample of ethnically/racially diverse community adolescents. Adolescents aged 15-21 (N = 81) years were recruited from community-based youth organizations to complete HIV risk assessment surveys. After the completion of the survey, participants were offered a free OraQuick rapid HIV antibody test. More than half (53.1%) of the participants accepted the test, with the black population being more likely to accept testing as compared to Latinos (75% vs. 39%). After controlling for race/ethnicity, significant predictors of test acceptance included history of sexual intercourse (OR = 5.43), having only one sexual partner in the past 3 months (OR = 4.88), not always using a condom with a serious partner (OR = 3.94), and not using a condom during last sexual encounter (OR = 4.75). Given that many adolescents are willing to know their HIV status, policies that support free or low-cost routine testing may lead to higher rates of case identification among youth. However, approaches must be developed to increase test acceptance among Latino adolescents and teenagers with multiple sexual partners. Copyright © 2011 Society for Adolescent Health and Medicine. Published by Elsevier Inc. All rights reserved.

  3. Geomechanics of the Climax mine-by, Nevada Test Site

    International Nuclear Information System (INIS)

    Heuze, F.E.

    1981-03-01

    A generic test of retrievable geologic storage of spent fuel assemblies in an underground chamber is being conducted at the Nevada Test Site. The horizontal shrinkage of the pillars is not explainable, but the vertical pillar stresses are easily understood. A two-phase project was initiated to estimate the in-situ deformability of the Climax granite and to refine the in-situ stress field data, and to model the mine-by

  4. Factors associated with willingness to accept oral fluid HIV rapid testing among most-at-risk populations in China.

    Directory of Open Access Journals (Sweden)

    Huanmiao Xun

    Full Text Available The availability of oral fluid HIV rapid testing provides an approach that may have the potential to expand HIV testing in China, especially among most-a-risk populations. There are few investigations about the acceptability of oral fluid HIV testing among most-at-risk populations in China.A cross-sectional study with men who have sex with men (MSM, female sex workers (FSW and voluntary counseling and testing (VCT clients was conducted in three cities of Shandong province, China from 2011 to 2012. Data were collected by face-to-face questionnaire.About 71% of participants were willing to accept the oral fluid HIV rapid testing, and home HIV testing was independently associated with acceptability of the new testing method among MSM, FSW and VCT clients (AOR of 4.46, 3.19 and 5.74, respectively. Independent predictors of oral fluid HIV rapid testing acceptability among MSM were having ever taken an oral fluid HIV rapid test (AOR= 15.25, having ever taken an HIV test (AOR= 2.07, and education level (AOR= 1.74. Engagement in HIV-related risk behaviors (AOR= 1.68 was an independent predictor of acceptability for FSW. Having taken an HIV test (AOR= 2.85 was an independent predictor of acceptability for VCT clients. The primary concern about the oral fluid HIV testing was accuracy. The median price they would pay for the testing ranged from 4.8 to 8.1 U.S. dollars.High acceptability of oral fluid HIV rapid testing was shown among most-at-risk populations. Findings provide support for oral rapid HIV testing as another HIV prevention tool, and provide a backdrop for the implementation of HIV home testing in the near future. Appropriate pricing and increased public education through awareness campaigns that address concerns about the accuracy and safety of the oral fluid HIV rapid testing may help increase acceptability and use among most-at-risk populations in China.

  5. Operational radioactive waste management plan for the Nevada Test Site

    International Nuclear Information System (INIS)

    1980-11-01

    The Operational Radioactive Waste Management Plan for the Nevada Test Site establishes procedures and methods for the safe shipping, receiving, processing, disposal, and storage of radioactive waste. Included are NTS radioactive waste disposition program guidelines, procedures for radioactive waste management, a description of storage and disposal areas and facilities, and a glossary of specifications and requirements

  6. Tonopah Test Range Environmental Restoration Corrective Action Sites

    International Nuclear Information System (INIS)

    2010-01-01

    This report describes the status (closed, closed in place, or closure in progress) of the Corrective Action Sites (CASs) and Corrective Action Units (CAUs) at the Tonopah Test Range. CASs and CAUs where contaminants were either not detected or were cleaned up to within regulatory action levels are summarized

  7. Nevada test site radionuclide inventory and distribution: project operations plan

    International Nuclear Information System (INIS)

    Kordas, J.F.; Anspaugh, L.R.

    1982-01-01

    This document is the operational plan for conducting the Radionuclide Inventory and Distribution Program (RIDP) at the Nevada Test Site (NTS). The basic objective of this program is to inventory the significant radionuclides of NTS origin in NTS surface soil. The expected duration of the program is five years. This plan includes the program objectives, methods, organization, and schedules

  8. Ore levels in Paleozoic of Semipalatinsk test site

    International Nuclear Information System (INIS)

    Ergaliev, G.Kh.; Myasnikov, A.K.; Fomichev, V.I.

    1999-01-01

    The regularity of the deposition of main mineralization of industrial types within Semipalatinsk test site proves and here and there defines more exactly location of the ore levels in Eastern Kazakhstan. Two mega levels, namely: Cambrian-Ordovician (siliceous-basalt, island-arc) and Carboniferous (especially carbonaceous-tarragons) ones are the most perspective for localizing the leading gold mineralization in the region

  9. Soil monitoring in Pavlodar region adjoining to Semipalatinsk test site

    International Nuclear Information System (INIS)

    Tuleubaev, B.A.; Ramazanov, Zh.R.; Askarov, E.V.

    2004-01-01

    A problem of territory study and rehabilitation contaminated with man-caused radionuclides is an important task and it has economic, social, and ecology aspects. The problem is crucial for Pavlodar region due to real proximity and to partial location of Semipalatinsk Test Site on its territory. (author)

  10. Integrated radiobioecological monitoring of Semipalatinsk test site: general approach

    International Nuclear Information System (INIS)

    Sejsebaev, A.T.; Shenal', K.; Bakhtin, M.M.; Kadyrova, N.Zh.

    2001-01-01

    This paper presents major research directions and general methodology for establishment of an integrated radio-bio-ecological monitoring system at the territory of the former Semipalatinsk nuclear test site. Also, it briefly provides the first results of monitoring the natural plant and animal populations at STS. (author)

  11. Environmental survey of southern part of former Semipalatinsk test site

    International Nuclear Information System (INIS)

    Zharikov, S.K.

    2000-01-01

    The present paper discusses results of the environmental survey performed in selected areas of Semipalatinsk test site southern part and gives calculations of possible annual radionuclide (Cs-37, Sr-90 and Pu-239/240) intake due to local husbandry products. (author)

  12. Nevada Test Site Radiological Control Manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  13. Options for clean-up of the Maralinga test site

    International Nuclear Information System (INIS)

    1985-06-01

    This report examines the limit of contamination of the soil and ground cover by 239 Pu, 235 U and 241 Am which may be considered as permitting the unrestricted land use of the former nuclear weapon test sites at Emu and Maralinga by Aboriginal groups. It reports on the options available to achieve this objective and their cost

  14. 78 FR 12259 - Unmanned Aircraft System Test Site Program

    Science.gov (United States)

    2013-02-22

    ... addressing potential UAS privacy concerns, as set out herein, contact Gregory C. Carter, Office of the Chief... address privacy concerns relating to the operation of the test site program, the FAA intends to include in... among policymakers, privacy advocates, and the industry regarding broader questions concerning the use...

  15. Wireless fetal heart rate monitoring in inpatient full-term pregnant women: testing functionality and acceptability.

    Science.gov (United States)

    Boatin, Adeline A; Wylie, Blair; Goldfarb, Ilona; Azevedo, Robin; Pittel, Elena; Ng, Courtney; Haberer, Jessica

    2015-01-01

    We tested functionality and acceptability of a wireless fetal monitoring prototype technology in pregnant women in an inpatient labor unit in the United States. Women with full-term singleton pregnancies and no evidence of active labor were asked to wear the prototype technology for 30 minutes. We assessed functionality by evaluating the ability to successfully monitor the fetal heartbeat for 30 minutes, transmit this data to Cloud storage and view the data on a web portal. Three obstetricians also rated fetal cardiotocographs on ease of readability. We assessed acceptability by administering closed and open-ended questions on perceived utility and likeability to pregnant women and clinicians interacting with the prototype technology. Thirty-two women were enrolled, 28 of whom (87.5%) successfully completed 30 minutes of fetal monitoring including transmission of cardiotocographs to the web portal. Four sessions though completed, were not successfully uploaded to the Cloud storage. Six non-study clinicians interacted with the prototype technology. The primary technical problem observed was a delay in data transmission between the prototype and the web portal, which ranged from 2 to 209 minutes. Delays were ascribed to Wi-Fi connectivity problems. Recorded cardiotocographs received a mean score of 4.2/5 (± 1.0) on ease of readability with an interclass correlation of 0.81(95%CI 0.45, 0.96). Both pregnant women and clinicians found the prototype technology likable (81.3% and 66.7% respectively), useful (96.9% and 66.7% respectively), and would either use it again or recommend its use to another pregnant woman (77.4% and 66.7% respectively). In this pilot study we found that this wireless fetal monitoring prototype technology has potential for use in a United States inpatient setting but would benefit from some technology changes. We found it to be acceptable to both pregnant women and clinicians. Further research is needed to assess feasibility of using this

  16. Wireless fetal heart rate monitoring in inpatient full-term pregnant women: testing functionality and acceptability.

    Directory of Open Access Journals (Sweden)

    Adeline A Boatin

    Full Text Available We tested functionality and acceptability of a wireless fetal monitoring prototype technology in pregnant women in an inpatient labor unit in the United States. Women with full-term singleton pregnancies and no evidence of active labor were asked to wear the prototype technology for 30 minutes. We assessed functionality by evaluating the ability to successfully monitor the fetal heartbeat for 30 minutes, transmit this data to Cloud storage and view the data on a web portal. Three obstetricians also rated fetal cardiotocographs on ease of readability. We assessed acceptability by administering closed and open-ended questions on perceived utility and likeability to pregnant women and clinicians interacting with the prototype technology. Thirty-two women were enrolled, 28 of whom (87.5% successfully completed 30 minutes of fetal monitoring including transmission of cardiotocographs to the web portal. Four sessions though completed, were not successfully uploaded to the Cloud storage. Six non-study clinicians interacted with the prototype technology. The primary technical problem observed was a delay in data transmission between the prototype and the web portal, which ranged from 2 to 209 minutes. Delays were ascribed to Wi-Fi connectivity problems. Recorded cardiotocographs received a mean score of 4.2/5 (± 1.0 on ease of readability with an interclass correlation of 0.81(95%CI 0.45, 0.96. Both pregnant women and clinicians found the prototype technology likable (81.3% and 66.7% respectively, useful (96.9% and 66.7% respectively, and would either use it again or recommend its use to another pregnant woman (77.4% and 66.7% respectively. In this pilot study we found that this wireless fetal monitoring prototype technology has potential for use in a United States inpatient setting but would benefit from some technology changes. We found it to be acceptable to both pregnant women and clinicians. Further research is needed to assess feasibility of

  17. Scaling of Lift Degradation Due to Anti-Icing Fluids Based Upon the Aerodynamic Acceptance Test

    Science.gov (United States)

    Broeren, Andy P.; Riley, James T.

    2012-01-01

    In recent years, the FAA has worked with Transport Canada, National Research Council Canada (NRC) and APS Aviation, Inc. to develop allowance times for aircraft operations in ice-pellet precipitation. These allowance times are critical to ensure safety and efficient operation of commercial and cargo flights. Wind-tunnel testing with uncontaminated anti-icing fluids and fluids contaminated with simulated ice pellets had been carried out at the NRC Propulsion and Icing Wind Tunnel (PIWT) to better understand the flowoff characteristics and resulting aerodynamic effects. The percent lift loss on the thin, high-performance wing model tested in the PIWT was determined at 8 angle of attack and used as one of the evaluation criteria in determining the allowance times. Because it was unclear as to how performance degradations measured on this model were relevant to an actual airplane configuration, some means of interpreting the wing model lift loss was deemed necessary. This paper describes how the lift loss was related to the loss in maximum lift of a Boeing 737-200ADV airplane through the Aerodynamic Acceptance Test (AAT) performed for fluids qualification. A loss in maximum lift coefficient of 5.24 percent on the B737-200ADV airplane (which was adopted as the threshold in the AAT) corresponds to a lift loss of 7.3 percent on the PIWT model at 8 angle of attack. There is significant scatter in the data used to develop the correlation related to varying effects of the anti-icing fluids that were tested and other factors. A statistical analysis indicated the upper limit of lift loss on the PIWT model was 9.2 percent. Therefore, for cases resulting in PIWT model lift loss from 7.3 to 9.2 percent, extra scrutiny of the visual observations is required in evaluating fluid performance with contamination.

  18. Fun During Knee Rehabilitation: Feasibility and Acceptability Testing of a New Android-Based Training Device.

    Science.gov (United States)

    Weber-Spickschen, Thomas Sanjay; Colcuc, Christian; Hanke, Alexander; Clausen, Jan-Dierk; James, Paul Abraham; Horstmann, Hauke

    2017-01-01

    The initial goals of rehabilitation after knee injuries and operations are to achieve full knee extension and to activate quadriceps muscle. In addition to regular physiotherapy, an android-based knee training device is designed to help patients achieve these goals and improve compliance in the early rehabilitation period. This knee training device combines fun in a computer game with muscular training or rehabilitation. Our aim was to test the feasibility and acceptability of this new device. 50 volunteered subjects enrolled to test out the computer game aided device. The first game was the high-striker game, which recorded maximum knee extension power. The second game involved controlling quadriceps muscular power to simulate flying an aeroplane in order to record accuracy of muscle activation. The subjects evaluated this game by completing a simple questionnaire. No technical problem was encountered during the usage of this device. No subjects complained of any discomfort after using this device. Measurements including maximum knee extension power, knee muscle activation and control were recorded successfully. Subjects rated their experience with the device as either excellent or very good and agreed that the device can motivate and monitor the progress of knee rehabilitation training. To the best of our knowledge, this is the first android-based tool available to fast track knee rehabilitation training. All subjects gave very positive feedback to this computer game aided knee device.

  19. Environmental assessment of SP-100 ground engineering system test site: Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    The US Department of Energy (DOE) proposes to modify an existing reactor containment building (decommissioned Plutonium Recycle Test Reactor (PRTR) 309 Building) to provide ground test capability for the prototype SP-100 reactor. The 309 Building (Figure 1.1) is located in the 300 Area on the Hanford Site in Washington State. The National Environmental Policy Act (NEPA) requires that Federal agencies assess the potential impacts that their actions may have on the environment. This Environmental Assessment describes the consideration given to environmental impacts during reactor concept and test site selection, examines the environmental effects of the DOE proposal to ground test the nuclear subsystem, describes alternatives to the proposed action, and examines radiological risks of potential SP-100 use in space. 73 refs., 19 figs., 7 tabs.

  20. Probabilistic Description of a Clay Site using CPTU tests

    DEFF Research Database (Denmark)

    Andersen, Sarah; Lauridsen, Kristoffer; Nielsen, Benjaminn Nordahl

    2012-01-01

    A clay site at the harbour of Aarhus, where numerous cone penetration tests have been conducted, is assessed. The upper part of the soil deposit is disregarded, and only the clay sections are investigated. The thickness of the clay deposit varies from 5 to 6 meters, and is sliced into sections of...... a geotechnical assessment of a site, using both the method for classifying soil behaviour types and applying statistics, yield a new level of information, and certainty about the estimates of the strength parameters which are the important outcome of such a site description.......A clay site at the harbour of Aarhus, where numerous cone penetration tests have been conducted, is assessed. The upper part of the soil deposit is disregarded, and only the clay sections are investigated. The thickness of the clay deposit varies from 5 to 6 meters, and is sliced into sections of 1...... meter in thickness. For each slice, a map of the variation of the undrained shear strength is created through Kriging and the probability of finding weak zones in the deposit is calculated. This results in a description of the spatial variation of the undrained shear strength at the site. Making...

  1. Acceptability of rapid oral fluid HIV testing among male injection drug users in Taiwan, 1997 and 2007.

    Science.gov (United States)

    Lyu, Shu-Yu; Morisky, Donald E; Yeh, Ching-Ying; Twu, Shiing-Jer; Peng, Eugene Yu-Chang; Malow, Robert M

    2011-04-01

    Rapid oral fluid HIV testing (rapid oral testing) is in the process of being adapted in Taiwan and elsewhere given its advantages over prior HIV testing methods. To guide this process, we examined the acceptability of rapid oral testing at two time points (i.e., 1997 and 2007) among one of the highest risk populations, male injection drug users (IDUs). For this purpose, an anonymous self-administered survey was completed by HIV-negative IDUs involved in the criminal justice system in 1997 (N (1)=137 parolees) and 2007 (N (2)=106 prisoners). A social marketing model helped guide the design of our questionnaire to assess the acceptability of rapid oral testing. This included assessing a new product, across four marketing dimensions: product, price, promotion, and place. Results revealed that in both 1997 and 2007, over 90% indicated that rapid oral testing would be highly acceptable, particularly if the cost was under US$6, and that a pharmacy would be the most appropriate and accessible venue for selling the rapid oral testing kits. The vast majority of survey respondents believed that the cost of rapid oral testing should be federally subsidized and that television and newspaper advertisements would be the most effective media to advertise for rapid oral testing. Both the 1997 and 2007 surveys suggested that rapid oral HIV testing would be particularly accepted in Taiwan by IDUs after release from the criminal justice system.

  2. Plutonium Particle Migration in the Shallow Vadose Zone: The Nevada Test Site as an Analog Site

    Science.gov (United States)

    Hunt, J. R.; Smith, D. K.

    2004-12-01

    The upper meter of the vadose zone in desert environments is the horizon where wastes have been released and human exposure is determined through dermal, inhalation, and food uptake pathways. This region is also characterized by numerous coupled processes that determine contaminant transport, including precipitation infiltration, evapotranspiration, daily and annual temperature cycling, dust resuspension, animal burrowing, and geochemical weathering reactions. While there is considerable interest in colloidal transport of minerals, pathogenic organisms, and contaminants in the vadose zone, there are limited field sites where the actual occurrence of contaminant migration can be quantified over the appropriate spatial and temporal scales of interest. At the US Department of Energy Nevada Test Site, there have been numerous releases of radionuclides since the 1950's that have become field-scale tracer tests. One series of tests was the four safety shots conducted in an alluvial valley of Area 11 in the 1950's. These experiments tested the ability of nuclear materials to survive chemical explosions without initiating fission reactions. Four above-ground tests were conducted and they released plutonium and uranium on the desert valley floor with only one of the tests undergoing some fission. Shortly after the tests, the sites were surveyed for radionuclide distribution on the land surface using aerial surveys and with depth. Additional studies were conducted in the 1970's to better understand the fate of plutonium in the desert that included studies of depth distribution and dust resuspension. More recently, plutonium particle distribution in the soil profile was detected using autoradiography. The results to date demonstrate the vertical migration of plutonium particles to depths in excess of 30 cm in this arid vadose zone. While plutonium migration at the Nevada Test Site has been and continues to be a concern, these field experiments have become analog sites for the

  3. Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Potable Water System Operations Plan

    Energy Technology Data Exchange (ETDEWEB)

    Ocampo, Ruben P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bellah, Wendy [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-03-04

    The existing Lawrence Livermore National Laboratory (LLNL) Site 300 drinking water system operation schematic is shown in Figures 1 and 2 below. The sources of water are from two Site 300 wells (Well #18 and Well #20) and San Francisco Public Utilities Commission (SFPUC) Hetch-Hetchy water through the Thomas shaft pumping station. Currently, Well #20 with 300 gallons per minute (gpm) pump capacity is the primary source of well water used during the months of September through July, while Well #18 with 225 gpm pump capacity is the source of well water for the month of August. The well water is chlorinated using sodium hypochlorite to provide required residual chlorine throughout Site 300. Well water chlorination is covered in the Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Chlorination Plan (“the Chlorination Plan”; LLNL-TR-642903; current version dated August 2013). The third source of water is the SFPUC Hetch-Hetchy Water System through the Thomas shaft facility with a 150 gpm pump capacity. At the Thomas shaft station the pumped water is treated through SFPUC-owned and operated ultraviolet (UV) reactor disinfection units on its way to Site 300. The Thomas Shaft Hetch- Hetchy water line is connected to the Site 300 water system through the line common to Well pumps #18 and #20 at valve box #1.

  4. LLNL Experimental Test Site (Site 300) Potable Water System Operations Plan

    Energy Technology Data Exchange (ETDEWEB)

    Ocampo, R. P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bellah, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-14

    The existing Lawrence Livermore National Laboratory (LLNL) Site 300 drinking water system operation schematic is shown in Figures 1 and 2 below. The sources of water are from two Site 300 wells (Well #18 and Well #20) and San Francisco Public Utilities Commission (SFPUC) Hetch-Hetchy water through the Thomas shaft pumping station. Currently, Well #20 with 300 gallons per minute (gpm) pump capacity is the primary source of well water used during the months of September through July, while Well #18 with 225 gpm pump capacity is the source of well water for the month of August. The well water is chlorinated using sodium hypochlorite to provide required residual chlorine throughout Site 300. Well water chlorination is covered in the Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Chlorination Plan (“the Chlorination Plan”; LLNL-TR-642903; current version dated August 2013). The third source of water is the SFPUC Hetch-Hetchy Water System through the Thomas shaft facility with a 150 gpm pump capacity. At the Thomas shaft station the pumped water is treated through SFPUC-owned and operated ultraviolet (UV) reactor disinfection units on its way to Site 300. The Thomas Shaft Hetch- Hetchy water line is connected to the Site 300 water system through the line common to Well pumps #18 and #20 at valve box #1.

  5. Off-site monitoring for the Mighty Oak nuclear test

    International Nuclear Information System (INIS)

    Black, S.C.; Smith, A.E.; Costa, C.F.

    1986-07-01

    After a nuclear explosives test, code name Mighty Oak, the tunnel leading to the test point became contaminated with radioactive debris. To re-enter and recover valuable equipment and data, the DOE purged the tunnel air using particulate and charcoal filters to minimize discharge of radioactivity to the atmosphere. During this purging, the EPA established special air samples supplementing their routine air monitoring networks. Analysis of the collected samples for radioactive noble gases and for gamma-emitting radionuclides indicated that only low levels of xenon-133 were released in amounts detectable in populated areas near the Nevada Test Site. The maximum dose to an individual was calculated to be 0.36 microrem, assuming that person remained in the open field at the measurement site during the whole period of the purging

  6. CTBTO tests its on-site inspection regime in Kazakhstan

    International Nuclear Information System (INIS)

    2003-07-01

    The former Soviet Union's nuclear test site at Semipalatinsk in the east of today's Kazakhstan was closed down after Kazakhstan became an independent State in 1991. This region in the Kazakh steppe is deserted and pockmarked by countless craters, remnants of over 450 nuclear explosions that were detonated there. In September 2008, the area will start brimming with activity. Scientists, diplomats and journalists will arrive from all over the world to witness an endeavour in the Kazakh steppe that is of great significance for the safety of our planet. The organization that monitors the comprehensive ban on nuclear testing will conduct a large scale exercise to test one of the key elements of its global alarm system - on-site inspections.

  7. Environmental site assessments should include radon gas testing

    International Nuclear Information System (INIS)

    Nardi, M.A.

    1991-01-01

    There are two emerging influences that will require radon gas testing as part of many property transfers and most site assessments. These requirements come from lending regulators and state legislatures. Fannie Mae and others have developed environmental investigation guidelines for the purchase of environmentally contaminated real estate. These guidelines include radon gas testing for many properties. Several states have enacted laws that require environmental disclosure forms be prepared to ensure that the parties involved in certain real estate transactions are aware of the environmental liabilities that may come with the transfer of property. Indiana has recently enacted legislation that would require the disclosure of the presence of radon gas on many commercial real estate transactions. With more lenders and state governments likely to follow this trend, radon gas testing should be performed during all property transfers and site assessment to protect the parties involved from any legal liabilities

  8. On-site tests on the nuclear power plants

    International Nuclear Information System (INIS)

    Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

    1996-01-01

    On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

  9. Rehabilitation of the former nuclear test sites at Maralinga

    International Nuclear Information System (INIS)

    Costello, J.M.; Davoren, P.J.

    1994-01-01

    The Department of Primary Industries and Energy, Canberra, has commenced tendering procedures for appointment of a Project Management Organisation for the Rehabilitation of the former British atomic weapon test sites at Maralinga and Emu in South Australia. This paper gives a historical background to the atomic tests, and reports scientific and engineering studies conducted by the Technical Assessment Group (TAG) to define practical and economic options for rehabilitation of the former test sites. The rehabilitation option preferred by the Australian Government will focus on removal and burial of soil and fragments highly contaminated with plutonium oxide, and erection of warning fences around areas where permanent residence will not be permitted. The application of in-situ vitrification is under investigation for stabilisation of twenty one disposal pits containing up to twenty kilograms of plutonium at Taranaki. 3 refs., 2 tabs., 3 figs

  10. Nevada Test Site Radiation Protection Program - Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Radiological Control Managers' Council

    2008-06-01

    Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material.

  11. Nevada Test Site Radiation Protection Program - Revision 1

    International Nuclear Information System (INIS)

    Nevada Test Site Radiological Control Managers' Council

    2008-01-01

    Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material

  12. Land reclamation on the Nevada Test Site: A field tour

    International Nuclear Information System (INIS)

    Winkel, V.K.; Ostler, W.K.

    1993-01-01

    An all-day tour to observe and land reclamation on the Nevada Test Site was conducted in conjunction with the 8th Wildland Shrub and Arid Land Restoration Symposium. Tour participants were introduced to the US Department of Energy reclamation programs for Yucca Mountain Site Characterization Project and Treatability Studies for Soil Media (TSSM) Project. The tour consisted of several stops that covered a variety of topics and studies including revegetation by seeding, topsoil stockpile stabilization, erosion control, shrub transplanting, shrub herbivory, irrigation, mulching, water harvesting, and weather monitoring

  13. Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith

    International Nuclear Information System (INIS)

    Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo; Lindberg, Michael J.; Parker, Kent E.

    2011-01-01

    To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions has initiated secondary-waste-form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target for cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that

  14. Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith

    Energy Technology Data Exchange (ETDEWEB)

    Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo; Lindberg, Michael J.; Parker, Kent E.

    2011-08-12

    To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions has initiated secondary-waste-form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target for cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that

  15. Acceptance testing in digital systens of mammography. Protocols applicability; Pruebas de aceptacion en equipos digitales de mamografia. Aplicabilidad de protocolos

    Energy Technology Data Exchange (ETDEWEB)

    Bermudez, R.; Espana, M.L.; Garcia Castanon, P.; Gomez Barrado, A.; Rodriguez Martin, G.; Fernandez Bedoya, B.

    2011-07-01

    Acceptance testing of mammographic imaging systems technical is the first approach in order to guarantee that mammograms will be achieved with the minimun radiation dose compatible with an image quality sutiable for diagnose purposes. The aim of this study is to assess the practical applicability of different protocols in acceptance test of digital mammographyc systems. This study has been carried out on the results of ltyhe acceptance tests of five flat panel digital mammographic systems. Parameters established in the systems technical specifications and those evaluated in the consulted protocols were tested. Due to the fact that the legislation oin our country does not demand to consider a specific protocol, the results obtained were also compared considering different existing protocols. Results show discrepancies between manufacturers limiting values and those established in the protocols. Some parameters, such as the authomatic exposure control compensation and the detector noise, were found out to meet or not the limiting value, depending on the selected protocol. From our results we could suggest, that protocols from manufacturers should be adapted to acknowledged documents on acceptance testing in digital mammography. They buyer representative could even specify the protocol to be followed during the acceptance tests. (Author). 25 refs.

  16. Acceptance testing in digital systems of mammography. Protocols applicability; Pruebas de aceptacion en equipos digitales de mamografia. Aplicabilidad de protocolos

    Energy Technology Data Exchange (ETDEWEB)

    Bermudez, R.; Espana, M.L.; Garcia Castanon, P.; Gomez Barrado, A.; Rodriguez Martin, G.; Fernandez Bedoya, B.

    2011-07-01

    Acceptance testing of mammographic imaging systems technical is the first approach in order to guarantee that mammograms will be achieved with the minimum radiation dose compatible with an image quality suitable for diagnose purposes. The aim of this study is to assess the practical applicability of different protocols in acceptance test of digital mammographic systems. This study has been carried out on the results of the acceptance tests of five flat panel digital mammographic systems. Parameters established in the systems technical specifications and those evaluated in the consulted protocols were tested. Due to the fact that the legislation in our country does not demand to consider a specific protocol, the results obtained were also compared considering different existing protocols. Results show discrepancies between manufacturers limiting values and those established in the protocols. Some parameters, such as the automatic exposure control compensation and the detector noise, were found out to meet or not the limiting value, depending on the selected protocol. From our results we could suggest, that protocols from manufacturers should be adapted to acknowledged documents on acceptance testing in digital mammography. They buyer representative could even specify the protocol to be followed during the acceptance tests. (Author). 25 refs.

  17. Addendum 1 Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Vefa Yucel

    2001-01-01

    A disposal authorization statement (DAS) was issued by the U.S. Department of Energy/Headquarters (DOE/HQ) on December 5, 2000, authorizing the DOE's National Nuclear Security Administration Nevada Operations Office to continue the operation of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site for the disposal of low-level waste and mixed low-level waste. Prior to the issuance of the DAS, the Low-Level Waste Disposal Facility Federal Review Group (LFRG) had conducted reviews of the performance assessment (PA) and the composite analysis (CA) for the Area 5 RWMS, in accordance with the requirements of the DOE Radioactive Waste Management Order DOE O 435.1. A brief history of the reviews is as follows. (The reviews were conducted by independent review teams chartered by the LFRG; the review findings and recommendations were issued in review team reports to the LFRG.) The LFRG accepted the initial PA, with conditions, on August 30, 1996. Revision 2.1 to the PA was issued in January 1998, implementing the conditions of acceptance of the 1996 PA. The LFRG reviewed Revision 2.1 as part of the Area 5 RWMS CA review during 2000, and found it acceptable. The CA and the Supplemental Information provided in response to issues identified during the initial review of the CA were accepted by the LFRG. The Supplemental Information (including the responses to four key issues) is included in the Review Team Report to the LFRG, which recommends that it be incorporated into the CA and issued to all known holders of the CA. The Area 5 RWMS DAS requires that the Supplemental Information generated during the DOE/HQ review of the CA be incorporated into the CA within one year of the date of issuance of the DAS. This report, the first addendum to the Area 5 CA, is prepared to fulfill that requirement. The Supplemental Information includes the following: Issues Identified in the Review Team Report; Crosswalk Presentation; and Maintaining Doses As Low As Reasonably

  18. Feasibility and acceptability of artemisinin-based combination therapy for the home management of malaria in four African sites

    Directory of Open Access Journals (Sweden)

    Munguti Kaendi

    2008-01-01

    Full Text Available Abstract Background The Home Management of Malaria (HMM strategy was developed using chloroquine, a now obsolete drug, which has been replaced by artemisinin-based combination therapy (ACT in health facility settings. Incorporation of ACT in HMM would greatly expand access to effective antimalarial therapy by the populations living in underserved areas in malaria endemic countries. The feasibility and acceptability of incorporating ACT in HMM needs to be evaluated. Methods A multi-country study was performed in four district-size sites in Ghana (two sites, Nigeria and Uganda, with populations ranging between 38,000 and 60,000. Community medicine distributors (CMDs were trained in each village to dispense pre-packaged ACT to febrile children aged 6–59 months, after exclusion of danger signs. A community mobilization campaign accompanied the programme. Artesunate-amodiaquine (AA was used in Ghana and artemether-lumefantrine (AL in Nigeria and Uganda. Harmonized qualitative and quantitative data collection methods were used to evaluate CMD performance, caregiver adherence and treatment coverage of febrile children with ACTs obtained from CMDs. Results Some 20,000 fever episodes in young children were treated with ACT by CMDs across the four study sites. Cross-sectional surveys identified 2,190 children with fever in the two preceding weeks, of whom 1,289 (59% were reported to have received ACT from a CMD. Coverage varied from 52% in Nigeria to 75% in Ho District, Ghana. Coverage rates did not appear to vary greatly with the age of the child or with the educational level of the caregiver. A very high proportion of children were reported to have received the first dose on the day of onset or the next day in all four sites (range 86–97%, average 90%. The proportion of children correctly treated in terms of dose and duration was also high (range 74–97%, average 85%. Overall, the proportion of febrile children who received prompt treatment and the

  19. Hanford immobilized LAW product acceptance: Initial Tanks Focus Area testing data package

    Energy Technology Data Exchange (ETDEWEB)

    JD Vienna; A Jiricka; BP McGrail; BM Jorgensen; DE Smith; BR Allen; JC Marra; DK Peeler; KG Brown; IA Reamer; WL Ebert

    2000-03-08

    The Hanford Site's mission has been to produce nuclear materials for the US Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during plutonium production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The total volume of LAW requiring immobilization will include the LAW separated from the tank waste, as well as new wastes generated by the retrieval, pretreatment, and immobilization processes. Per the Tri-Party Agreement (1994), both the LAW and HLW will be vitrified. It has been estimated that vitrification of the LAW waste will result in over 500,000 metric tons or 200,000 m{sup 3} of immobilized LAW (ILAW) glass. The ILAW glass is to be disposed of onsite in a near-surface burial facility. It must be demonstrated that the disposal system will adequately retain the radionuclides and prevent contamination of the surrounding environment. This report describes a study of the impacts of systematic glass-composition variation on the responses from accelerated laboratory corrosion tests of representative LAW glasses. A combination of two tests, the product consistency test and vapor-hydration test, is being used to give indictations of the relative rate at which a glass could be expected to corrode in the burial scenario.

  20. Hanford immobilized LAW product acceptance: Initial Tanks Focus Area testing data package

    International Nuclear Information System (INIS)

    JD Vienna; A Jiricka; BP McGrail; BM Jorgensen; DE Smith; BR Allen; JC Marra; DK Peeler; KG Brown; IA Reamer; WL Ebert

    2000-01-01

    The Hanford Site's mission has been to produce nuclear materials for the US Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during plutonium production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The total volume of LAW requiring immobilization will include the LAW separated from the tank waste, as well as new wastes generated by the retrieval, pretreatment, and immobilization processes. Per the Tri-Party Agreement (1994), both the LAW and HLW will be vitrified. It has been estimated that vitrification of the LAW waste will result in over 500,000 metric tons or 200,000 m 3 of immobilized LAW (ILAW) glass. The ILAW glass is to be disposed of onsite in a near-surface burial facility. It must be demonstrated that the disposal system will adequately retain the radionuclides and prevent contamination of the surrounding environment. This report describes a study of the impacts of systematic glass-composition variation on the responses from accelerated laboratory corrosion tests of representative LAW glasses. A combination of two tests, the product consistency test and vapor-hydration test, is being used to give indictations of the relative rate at which a glass could be expected to corrode in the burial scenario