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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
B.A. Magurno, O. Ozer
Nuclear Technology | Volume 25 | Number 2 | February 1975 | Pages 376-380
Technical Paper | Material Dosimetry | doi.org/10.13182/NT75-A24374
Articles are hosted by Taylor and Francis Online.
The present dosimetry file consists of 36 reactions in 26 isotopes and is being issued with Version IV of the ENDF/B library. The file evolved from the efforts of the Normalization and Standards Subcommittee of the Cross-Section Evaluation Working Group to review the status of multigroup cross-section sets used for dosimetry purposes in the Interlaboratory LMFBR Reaction Rate (ILRR) program. The recommendation of the subcommittee was the creation of a multigroup library based on the best available estimates of microscopic data even though these data might not initially agree with some of the integral tests. A task force to assemble this library was drawn from the subcommittee and member laboratories in the ILRR program. The library was tested with procedures similar to those used on the ENDF/B general file. Phase-I tests included processing with computer codes CHECKER to be sure the dosimetry file complied with the standard ENDF format and INTER to calculate the resonance integral of the exoergic reactions in the file. Phase II consisted of calculating spectrum-averaged cross sections with a variety of spectra and comparing the results with designated integral results.