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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Wyoming as a hub for new nuclear manufacturing and microreactor deployment?
A 60-year-old Wyoming industrial machinery company is partnering with nuclear innovator BWX Technologies to deploy 50-megawatt microreactors in America’s heartland over the coming years to provide carbon-free heat and power for industrial users.
Robert E. Einziger, Bobby R. Seidel
Nuclear Technology | Volume 50 | Number 1 | August 1980 | Pages 25-39
Technical Paper | Fuel | doi.org/10.13182/NT80-A17067
Articles are hosted by Taylor and Francis Online.
The Experimental Breeder Reactor II Mark-II metallic-driver-fuel element has been irradiated to high burnup to assess element lifetime and performance reliability. The elements breached at 10 at.% burnup or greater. This increase in burnup potential compared to its predecessor, the Mark-IA (limited to a burnup of 3 at.%), is due to the reduction of fuel-cladding mechanical interaction (FCMI) resulting from the smaller smear density, a lower fission-gas-induced cladding stress resulting from the increased plenum volume and increased cladding thickness, and a reduction in fuel-cladding chemical interaction (FCCI) due to a change in cladding material. The cladding breach in the solution-annealed Type 316 stainless-steel-clad elements was in the restrainer dimple located above the original fuel column, not in the upper half of the fuel column as in the Type 304L stainless-steel-clad elements. During irradiation, the prime cause of cladding deformation was swelling. Due to the extensive release of fission gas after interconnected porosity developed, the fuel deformation was restricted by the cladding. After fuel-cladding contact, a small amount of FCCI, as predicted by out-of-pile measurements, occurred, but little FCMI is thought to have taken place.