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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2021 Student Conference
April 8–10, 2021
Virtual Meeting
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
March 2021
Nuclear Technology
February 2021
Fusion Science and Technology
January 2021
Latest News
Complaint filed with FERC over Grand Gulf management
The Louisiana Public Service Commission (LPSC), the New Orleans City Council, and the Arkansas Public Service Commission on March 2 filed a complaint with the Federal Energy Regulatory Commission against Entergy Corporation, seeking damages of more than $360 million for what they term the utility’s “imprudent operation” of the Grand Gulf nuclear plant.
Located in Port Gibson, Miss., Grand Gulf is a single-unit plant with a 1,433-MWe boiling water reactor. The unit, which entered commercial operation in 1985, supplies power to customers of Entergy Louisiana, Entergy Mississippi, Entergy Arkansas, and Entergy New Orleans.
Janne Wallenius, Erdenechimeg Suvdantsetseg, Andrei Fokau
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 303-313
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT12-A13477
Articles are hosted by Taylor and Francis Online.
The design of a low-power fast neutron reactor cooled by liquid lead (ELECTRA) is presented. Application of (Pu,Zr)N fuel permits the design of a core with very small volume and fuel column height, resulting in highly negative coolant, fuel, and structure temperature coefficients and very low channel pressure drop. Full design power of 0.5 MW(thermal) may be completely removed by natural circulation in the primary circuit, thus eliminating the need for pumps. Analysis of flow stability and performance under unprotected transients show that the suggested design is very safe, supporting its intended use for training and educational purposes.
