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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
R. G. Alsmiller, Jr., J. Barish
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 318-321
Technical Note | Material | doi.org/10.13182/NT77-A31794
Articles are hosted by Taylor and Francis Online.
Calculated results are presented of the variation with position in the experimental volume of a Li(D,n) neutron radiation damage facility of the damage energy and helium and hydrogen production in copper and in niobium when this volume is partially filled with experimental samples. At a given position in the experimental volume for either copper or niobium, the ratio of the damaged energy with no absorber to the damaged energy with a 50-mm-thick iron absorber or a 100-mm-thick carbon absorber is never >3 and in most positions is <2. The neutron nonelastic cross-section data at the higher energies (>15 to 20 MeV) needed to carry out the transport calculations were obtained from the intranuclear-cascade model of nuclear reactions.
