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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
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.
Kevin R. Robb, Matthew W. Francis, Larry J. Ott
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 145-160
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-43
Articles are hosted by Taylor and Francis Online.
During the emergency response period of the accidents that took place at the Fukushima Daiichi nuclear power plant (NPP) in March of 2011, researchers at Oak Ridge National Laboratory (ORNL) conducted a number of studies using the MELCOR code to help understand what was occurring and what had occurred. During the postaccident period, the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) jointly sponsored a study of the Fukushima Daiichi NPP accident with collaboration among ORNL, Sandia National Laboratories, and Idaho National Laboratory. The purpose of the study was to compile relevant data, reconstruct the accident progression using computer codes, assess the codes' predictive capabilities, and identify future data needs. The current paper summarizes some of the early MELCOR simulations and analyses conducted at ORNL of the Fukushima Daiichi NPP Unit 3 (1F3) accident. Extended analysis and discussion of the 1F3 accident are also presented taking into account new knowledge and modeling refinements made since the joint DOE-NRC study.