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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
T. R. Herold
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 269-278
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31116
Articles are hosted by Taylor and Francis Online.
A new electronic method has been developed that requires about 10 min to assay 252Cf sources between 1 μg and 50 mg. The assay is made by placing the 252Cf source in the center of a polyethylene moderator and measuring the resulting thermalized neutrons with fission counters in the moderator. All measurements are referenced to a 252Cf calibrated with a manganese sulfate bath by the National Bureau of Standards. Sources smaller than 1 μg and larger than 50 mg could be similarly assayed with appropriate modifications to the moderator. The new method is routinely compared with the manganese bath method to determine the precision and sensitivity of the measurements so that the new method can be used as a secondary standard. Measurements of 252Cf content agree with manganese sulfate bath determinations to within ±0.6%. The present design is tailored for a fission neutron spectrum but could be used with proper calibration in assaying between 106 and 1011 n/sec from sources having different spectra.