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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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NRC issues interim guidance on reactor component disposal
The Nuclear Regulatory Commission is providing guidance to nuclear power plant licensees looking to use decommissioning trust fund (DTF) money to dispose of major reactor components like steam generators and reactor vessel heads while the plant is still operational.
On August 5, the NRC issued the interim staff guidance Use of the Decommissioning Trust Fund During Operations for Major Radioactive Component Disposal (REFS-ISG-2024-01), which provides the NRC staff’s regulatory position regarding the use a reactor’s DTF for the disposal of major radioactive components while the plant is still operational. Under NRC regulations, the DTF may be accessed solely for decommissioning expenses as defined in 10 CFR 50.2, unless an exemption is granted by the NRC.
Robert C. Doerner, Theodore H. Bauer, James A. Morman, John W. Holland
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 124-136
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34656
Articles are hosted by Taylor and Francis Online.
Prototypic oxide fuel was subjected to simulated, fast reactor severe accident conditions in a series of in-pile tests in the Transient Reactor Test Facility reactor. Seven experiments were performed on fresh and previously irradiated oxide fuel pins under transient overpower and transient undercooled/overpower accident conditions. For each of the tests, fuel motions were observed by the hodoscope. Hodoscope data are correlated with coolant flow, pressure, and temperature data recorded by the loop instrumentation. Data were analyzed from the onset of initial failure to a final mass distribution at the end of the test. Results of these analyses are compared to pre- and posttest accident calculations and to posttest metallographic examinations and computed tomographic reconstructions from neutron radiographs.