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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
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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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
L. Crosatti, D. L. Sadowski, S. I. Abdel-Khalik, M. Yoda, ARIES Team
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 96-100
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8883
Articles are hosted by Taylor and Francis Online.
Extensive experimental and numerical studies of the planar jet impingement concept used in gas-cooled T-tube divertor modules have been previously performed at Georgia Tech.1 The experiments were used to validate the numerical CFD model based on the FLUENT[registered] software package. However, the test module used in those experiments did not duplicate the exact geometry of the T-tube divertor, particularly the single-sided nature of the incident heat flux. In this paper, the thermal performance of a prototypical T-tube divertor module is experimentally and numerically examined. The test module has been designed and constructed to match the geometry, dimensions, material properties, and single-sided heating configuration of the actual T-tube divertor. Experiments were performed using air as the coolant with different values of the incident heat flux. The coolant flow rate and inlet pressure were selected to span the expected range of non-dimensional parameters for the actual helium-cooled T-tube divertor design. The experimental values of the local heat transfer coefficient and pressure drop show good agreement with the numerical (FLUENT[registered] 6.3) predictions. The data obtained in this investigation provide added confidence in the predicted performance of the T-tube divertor concept, and the ability of the FLUENT CFD software package to predict its thermal performance, as well as the thermal performance of other complex gas-cooled high heat flux components.