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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
Richard A. Wolfe
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 218-228
Reactor Siting | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28810
Articles are hosted by Taylor and Francis Online.
Calculations show that a 10% isotopic abundance of 238 Pu in a bare spherical 239 Pu-H2O system increases the minimum critical mass by ∼48%, thereafter the increase continues exponentially. These results, in addition to several subcritical neutron multiplication experiments with 238 Pu in both solution and dioxide form, confirm that 238 Pu behaves as a neutron poison in a well-moderated medium. Neutron multiplication experiments were conducted with four SNAP-19B (IRHS) heat sources with ∼1 kg 238 Pu per source. The results indicated that a neutron multiplication <1.2 existed when the heat sources were assembled in different array configurations. The criticality unit value for 238 Pu in either solution or dioxide form has been conservatively established at 2.0 kg. Thermocouples installed on process vessels have proven to be a new criticality control technique for determining gradual 238 Pu sludge buildup. Heterogeneous water-filled storage vaults provide the safest method for storing large quantities of PuO2 containing at least 76% 238Pu.