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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Alp Tezbasaran, Maria N. Avramova, Kostadin N. Ivanov (NCSU), Osman S. Celikten (Hacettepe Univ)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 729-738
In this work, the sub-channel thermal-hydraulic code CTF is applied to the hottest fuel assembly of a VVER-1000 core, aiming to investigate the code sensitivity to uncertainties of the initial and boundary conditions. The core thermal-hydraulic solver CTF is a modernized version of the COBRA-TF sub-channel code, which is being maintained and developed by the Reactor Dynamics and Fuel Modeling Group (RDFMG) at North Carolina State University (NCSU) in cooperation with Oak Ridge National Laboratory (ORNL).
In this study, first, a full core model of a VVER-1000 reactor with its initial loading pattern is created for the Monte Carlo neutronics code MCNP6 under normal operating conditions using ENDF/B VII.1 / NJOY99. The assembly power factors and the pin-powers of the hottest fuel assembly, obtained by MCNP6, are used as power boundary conditions in CTF. The hottest assembly is simulated to calculate the fuel, cladding, and coolant temperatures at normal operating conditions.
Uncertainty analyses are performed using Dakota 6.5 and it is observed that CTF predictions of fuel, cladding, and coolant temperatures are most sensitive to uncertainties in core average power and inlet coolant temperature.
