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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
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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.
Abd Y. Lafi, Jose N. Reyes, Jr.
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 177-183
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3085
Articles are hosted by Taylor and Francis Online.
A comparison is presented between station blackout tests conducted in both the Advanced Plant Experiment (APEX) facility and in the modified Rig of Safety Assessment (ROSA/AP600) Large-Scale Test Facility. The comparison includes the depressurization and liquid-level behavior during secondary-side blowdown, natural circulation, automatic depressurization system operation, and in-containment refueling water storage tank injection. Reasonable agreement between the test results from APEX NRC-2 and ROSA/AP600 AP-BO-01 has been observed with respect to the timing of depressurization and liquid draining rates. This indicates that the reduced height and pressure scaling of APEX preserves the sequence of events relative to the full-height and pressure ROSA/AP600.
