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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
J. Papin, B. Cazalis, J. M. Frizonnet, J. Desquines, F. Lemoine, V. Georgenthum, F. Lamare, M. Petit
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 230-250
Technical Paper | Reactivity-Initiated Accident (RIA) | doi.org/10.13182/NT07-A3815
Articles are hosted by Taylor and Francis Online.
The CABRI REP-Na program was performed in the sodium loop of the CABRI reactor by the French Institut de Radioprotection et de Sûreté Nucléaire. The objective was to study the behavior of high-burnup UO2 and mixed-oxide (MOX) fuel during a reactivity-initiated accident (RIA) and involved eight tests with UO2 and four with MOX fuel. Failures of some UO2 and MOX fuel rods at enthalpy levels ranging from 125 to 472 J/g (30 to 113 cal/g) demonstrated the need for further development of the present safety criteria pertaining to fuel behavior. Detailed interpretation of the test data led to identifying the deleterious influence of a high clad corrosion level with hydride concentrations on clad failure, the contribution of grain boundary gases on fission gas release, and potential clad loading, mainly in MOX fuel during the first phase of the transient without significant clad temperature increase.Questions still remain concerning the transient fission gas behavior and its impact on clad loading during the entire transient, the rod behavior with high clad temperature and internal pressure, and the postfailure phenomena (fuel ejection, fuel/coolant interaction with finely fragmented solid fuel). These issues will be addressed by the CABRI International Program tests under typical pressurized water reactor conditions.