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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Argonne research aims to improve nuclear fuel recycling and metal recovery
Servis
Scientists at Argonne National Laboratory are investigating a used nuclear fuel recycling technology that could lead to a scaled-down and more efficient approach to metal recovery, according to a recent news article from the lab. The research, led by Argonne radiochemist Anna Servis with funding from the Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E), could have an impact beyond the nuclear fuel cycle and improve other high-value metal processing, such as rare earth recovery, according to Argonne.
The research: Servis’s work is being carried out under ARPA-E’s CURIE (Converting UNF Radioisotopes Into Energy) program. The specific project—Radioisotope Capture Intensification Using Rotating Packed Bed Contactors—started in 2023 and is scheduled to end in January 2026.
Hitesh Patel, Nirmal Panda, Nitin Kanoongo, K. Balasubramanian, M. J. Singh, Arun Chakraborty
Fusion Science and Technology | Volume 77 | Number 4 | May 2021 | Pages 298-309
Technical Paper | doi.org/10.1080/15361055.2021.1898856
Articles are hosted by Taylor and Francis Online.
High heat flux components form the primary interface for thermal management of injectors in fusion devices. The requirement for such application varies from 1 to 10 MW/m2. Ultra-high-vacuum compatibility is the inherent characteristic of such components, and manufacturing processes involve the development of specific materials, process qualification of special processes like electron beam welding (EBW), and component performance validation. One such component of active thermal management in a neutral beam injector is the hypervapatron-based heat transfer element (HTE), which is designed to absorb heat flux as high as 10 MW/m2. The route to realization is through a prototype and a one-to-one model and evaluating their performance. The development route of HTEs includes several important areas. One area is development of precipitation-hardened CuCrZr material characterized for its fatigue life (more than 100 000 stress-controlled cycles); mechanical properties at ambient temperature [ultimate tensile strength (UTS) >384 MPa, elongation >13%] and at operational temperature, i.e., 350°C (UTS >263 MPa, elongation >14%); and restricted chemical composition range of Cr, Zr, Cd, and O2 to enhance the precipitation effect and weldability of the component. A second area is similar material (CuCrZr to CuCrZr) and dissimilar material (CuCrZr-Ni-SS316L) joining by an advanced technology like EBW in a controlled environment to enhance the localized high heat input over a large weld penetration depth with minimal distortion and thereby overcome the effect of thermal diffusion by typical copper during welding. A third area is validation of these weld joints with respect to international codes/standards. Successful realization of this route establishes HTEs as main baseline components of the high heat flux system or neutral beam system. Similar application areas can be identified in various fusion devices. The paper presents the implementation of this realization route of prototype HTEs including details of the assessment carried out with respect to application.
