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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Investment bill would provide funding options for energy projects
Coons
Moran
The bipartisan Financing Our Futures Act, which expands certain financing tools to all types of energy resources and infrastructure projects, was reintroduced to the U.S. Senate on February 20 by Sens. Jerry Moran (R., Kan.) and Chris Coons (D., Del.).
Via amendment to the Internal Revenue Code, the legislation would allow advanced nuclear energy projects to form as master limited partnerships (MLPs), a tax structure currently available only to traditional energy projects.
An MLP is a business structure that is taxed as a partnership but the ownership interests of which are traded like corporate stock on a market. Until the Internal Revenue Code is amended, MLPs will continue to be available only to investors in energy portfolios for oil, natural gas, coal extraction, and pipeline projects that derive at least 90 percent of their income from these sources. This change would take effect on January 1, 2026.
K. Vinjamuri, D. E. Owen
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 119-124
Technical Paper | Fuel | doi.org/10.13182/NT80-A32416
Articles are hosted by Taylor and Francis Online.
Instrumented Fuel Assembly 429, an experimental assembly designed to study helium fill gas absorption and fission gas release in pressurized uranium dioxide (UO2) fuel rods used in light water reactors, is operating in the Halden Heavy Boiling Water Reactor in Halden, Norway. Preliminary assessment of results from fuel rod internal pressure measurements and from the postirradiation examination of selected fuel rods indicates that helium fill gas is absorbed into the UO2 during the first several months of operation. The fuel absorbs ∼5.7 × 10−3 cm3 He (STP)/g UO2 at the irradiation conditions of a 5.4-MPa helium pressure and a peak steady-state fuel temperature of 1500 K. The estimated effective helium diffusion coefficient is ∼1 × 10−8 cm2/s. Periodic transients with power increases of up to 50% do not drive the helium from the UO2 matrix.
