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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.
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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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Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Neil Mitchell, Denis Bessette, Hirobumi Fujieda, Yuri Gribov, Cees Jong, Fabrice Simon
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 676-684
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8987
Articles are hosted by Taylor and Francis Online.
The ITER magnet system, particularly the Poloidal Field Coils (PFC) and Central Solenoid Coils (CSC), was originally designed to drive, confine and stabilise a set of plasmas about a baseline of a reference 15MA 400s inductive burn, with capability for inductive short burn at currents up to 17MA and 10MA non-inductive plasmas depending on the plasma parameters that can be achieved.Recent assessments of experimental data and improved plasma modelling have identified some constraints in the 2001 design that may limit the range of plasmas that can be generated in ITER. The constraints are a mixture of coil superconducting performance, structural and electrical limits, and concern both the accuracy of the formation of the plasma configuration (including the position of the separatrix lines in the divertor) and the stabilisation of the plasma position.