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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
G. P. Airey, A. R. Vaia, R. G. Aspden
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 436-448
Technical Paper | Materials | doi.org/10.13182/NT55-436
Articles are hosted by Taylor and Francis Online.
Inconel 690 is an austenitic nickel base alloy that has been considered for use as steam generator tubing in pressurized water reactors. It has a composition comparable to the currently used Inconel 600 apart from a higher chromium content (30%). Inconel 690 was evaluated for stress corrosion cracking (SCC) resistance in deaerated sodium hydroxide solutions and all-volatile treatment (AVT) environments, and the results are compared with those from thermally treated Inconel 600. The effect of such metallurgical variables as grain size and thermal treatment on SCC resistance was investigated. The caustic SCC resistance of Inconel 690 was significantly improved, compared to the mill-annealed product, when thermally treated over a wide range of temperatures [649 to 871°C (1200 to 1600°F)] and times (1 to 30 h). The SCC resistance of thermally treated Inconel 690 was found to be excellent when exposed to deaerated sodium hydroxide at 343°C (650°F) and 316°C (600°F). There was an increase in caustic SCC susceptibility with decreasing grain size in mill-annealed tubing. However, the corresponding thermally treated tubing showed no caustic SCC susceptibility. No evidence of SCC degradation has been found in either mill-annealed or thermally treated Inconel 690 exposed to high temperature AVT and “pure water” environments.
