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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
William P. Kelleher, J. Wiley Davidson, Gary R. Thayer, Donald J. Dudziak
Fusion Science and Technology | Volume 17 | Number 3 | May 1990 | Pages 466-475
Technical Note | Shielding | doi.org/10.13182/FST90-A29221
Articles are hosted by Taylor and Francis Online.
A radiation shielding analysis was performed on the Confinement Physics Research Facility (CPRF) under construction at Los Alamos National Laboratory. A reversed-field pinch device, the ZTH, was examined in an effort to obtain an estimate of the spatial distribution of the dose seen by both personnel and electronic components. In the Monte Carlo transport analysis, the MCNP code was used to estimate the neutron and gamma-ray doses and differential flux (in energy) spectra at ten locations within the CPRF. The complex geometry of the ZTH dictated that the problem be solved in a two-step process: First, a cylindrical surface source enclosing the ZTH was computed, and then this source was used as the radiation source for the CPRF building calculations. Using a source strength of 1015 neutrons, identical calculations were performed for both deuterium-deuterium and deuterium-tritium fusion plasmas.