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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Nuclear Science and Engineering
March 2025
Nuclear Technology
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February 2025
Latest News
Investment bill would provide funding options for energy projects
Coons
Moran
The bipartisan Financing Our Futures Act, which expands certain financing tools to all types of energy resources and infrastructure projects, was reintroduced to the U.S. Senate on February 20 by Sens. Jerry Moran (R., Kan.) and Chris Coons (D., Del.).
Via amendment to the Internal Revenue Code, the legislation would allow advanced nuclear energy projects to form as master limited partnerships (MLPs), a tax structure currently available only to traditional energy projects.
An MLP is a business structure that is taxed as a partnership but the ownership interests of which are traded like corporate stock on a market. Until the Internal Revenue Code is amended, MLPs will continue to be available only to investors in energy portfolios for oil, natural gas, coal extraction, and pipeline projects that derive at least 90 percent of their income from these sources. This change would take effect on January 1, 2026.
F. Beranek, R. W. Conn
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 406-411
Technical Paper | Reactor | doi.org/10.13182/NT80-A32394
Articles are hosted by Taylor and Francis Online.
A standard time-dependent neutron transport computer code, TDA, is modified to allow time-varying material density to calculate the neutron spectrum from exploding inertial confinement fusion pellets with ρR values of 0 to 6 g/cm2. Softening of the spectra due to neutron-fuel interactions causes a time-of-flight broadening of the neutron arrival time distribution at the chamber wall. It is found that the total number of displacements per atom (dpa) produced in a graphite first wall increases with the ρR of the pellet over the ρR range investigated because the dpa cross section is larger at lower neutron energy. However, the total helium production decreases with increasing ρR, as does the peak damage rate. Neutron-induced radioactivity generated in a 10-mg iron tamper is of the same magnitude as that produced in the rest of an entire reactor system.
