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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
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Andrey A. Troshko, Yassin A. Hassan
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 228-238
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3113
Articles are hosted by Taylor and Francis Online.
A simulation of VVER1000/320 operational transients was performed with the CATHARE2 V1.3L computer program. These transients consisted of consecutive shutdowns of two primary side pumps, prior to which, the reactor was under nominal operational condition with 72 and 52% power levels, respectively. The comparison between calculated and measured data indicated that the program was able to qualitatively predict the main phenomena taking place in both the primary and the secondary sides of the plant. The role of pump inertia was studied. It was found that implementation of inertial pump shutdown led to a better agreement with experiment. There was a lack of detailed information on the secondary-side geometry. Thus, it was difficult to conclude whether the quantitative discrepancy between experiment and calculation was due to the physical model or the geometric uncertainty.