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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
N. K. Popov, H. Sills, A. Abdul-Razzak
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 2-17
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3820
Articles are hosted by Taylor and Francis Online.
The Advanced CANDU Reactor (ACR) is an evolutionary advancement of the current CANDU 6® reactor, aimed at producing electrical power for a capital cost and at a unit-energy cost significantly less than that of the current reactor designs. The ACR retains the modular concept of horizontal fuel channels surrounded by a heavy water moderator, as with all CANDU reactors. However, ACR uses low enriched uranium fuel, compared to the natural uranium used in CANDU 6. This achieves the twin goals of improved economics (e.g., via reductions in the heavy water requirements and the use of a light water coolant), as well as improved safety.This paper presents the approach used in developing two phenomena identification and ranking tables (PIRTs) for selected ACR-700 events and their results. One of the two selected events is a large loss-of-coolant accident, which is an ACR design basis event, while the other is a severe flow blockage, which is proposed to be classified as a limited core damage event (beyond design basis event).The paper outlines the design characteristics of the ACR-700 reactor that impact the PIRT process and computer code applicability, lists all components and systems that have an important role during the event, discusses the PIRT process and results, and presents the finalized PIRTs.The ACR-1000 reactor design is currently in detailed design at AECL, and it retains similar design features as the ACR-700 design. Although the PIRTs presented in this paper were developed for the ACR-700 design, they are generally applicable to the ACR-1000 design.