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Neutron absorbers have been used for criticality control in spent nuclear fuel pools and in spent fuel transportation casks for decades. However, since the late 1980s, as spent fuel storage pools have been filled, utilities have transferred spent fuel into dry dual-purpose (storage/transportation) canisters. The neutron absorbers used in dual-purpose canisters are subjected to different operating…
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Since 1998, when ASTM International Committee F05 on Business Imaging Products first approved standard F 1856 , Practice for Determining Toner Usage for Printer Cartridges, there has been a rapid increase in the use of color in office printing. In order to address this important change, Subcommittee F05.04 on Electrostatic Imaging Products has developed F 2632 , Practice for Determining the Toner…
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ASTM International Committee C26 on Nuclear Fuel Cycle has recently published a new standard and has begun the development of a proposed new standard. Subcommittee C26.14 on Remote Systems is responsible for the newly approved standard, C 1661 , Guide for Viewing Systems for Remotely Operated Facilities, while Subcommittee C26.02 on Fuel and Fertile Material Specifications is currently at work on…, C 1661, Guide for Viewing Systems for Remotely Operated Facilities, A new ASTM International standard establishes minimum requirements for viewing systems for remotely operated facilities, including hot cells, used for the processing and handling of nuclear and radioactive materials. The standard, C 1661 , Guide for Viewing Systems for Remotely Operated Facilities, was developed by Subcommittee C26.14 on Remote Systems, which is part of ASTM International…, WK14330, Nuclear Fuel Pellet Physical Integrity Limits: Chips, Cracks, Defects, The quality of fuel pellets is currently an important topic being studied throughout the nuclear industry, with study groups such as the Electric Power Research Institute and Institute of Nuclear Power Operations examining the effect of pellet quality on the performance of nuclear fuel. ASTM International Committee C26 on Nuclear Fuel Cycle is addressing the topic of fuel pellets with a proposed…
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The ability to determine the number of pages an ink jet printer cartridge will print in its lifetime is essential for anyone who manufactures or remanufactures them. A new ASTM International standard, F 2555 , Practice for Determining Page Yield of Ink Jet Printer Cartridges — Continuous Printing Method, has been developed to aid in this endeavor. Practice F 2555 is under the jurisdiction of…
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ASTM International Committee F05 on Business Imaging Products is currently seeking participation in the development of proposed new standards under the jurisdiction of Subcommittee F05.07 on Ink Jet Imaging Products. Users, original equipment manufacturers and ink producers are needed to assist in the following task groups: F05.07.01 This task group is working on developing a user-friendly…
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ASTM International Committee C26 on Nuclear Fuel Cycle has approved two new standards, both under the jurisdiction of Subcommittee C26.05 on Methods of Test. All interested parties are invited to participate in the standards developing activities of Committee C26. ASTM International standards are available for purchase from Customer Service (phone: 610/832-9585; https://www.astm.org/contact )…, ASTM C 1637 , Test Method for the Determination of Impurities in Plutonium Metal: Acid Digestion and Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) Analysis, The approval of C 1637 is part of Subcommittee C26.05’s project involving the approach to keeping the analytical methodology used for determining specifications for nuclear materials up to date. This project began in 1990 when the subcommittee decided to develop separate standards from methods that were part of larger multi-methods materials specification standards. Once the new test methods…, ASTM C 1638 , Guide for the Determination of Iodine-129 in Uranium Oxide, Guide C 1638 covers the determination of iodine-129 in uranium oxide by gamma-ray spectrometry. Users may include U.S. Department of Energy sites that are dispositioning excess uranium to waste sites. Although there is no specification for the levels of I-129 in fuel, waste disposal sites may set limits due to the potential mobility of iodine in the environment. This guide may be used to ensure…