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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
John T. Mihalczo, Victor I. Neeley
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 6-11
Technical Paper | doi.org/10.13182/NSE62-A26121
Articles are hosted by Taylor and Francis Online.
The infinite medium neutron multiplication factor, k∞, of a mixture of 92.1 wt% UF4 and 7.9 wt% paraffin has been measured both in the Physical Constants Testing Reactor at the Hanford Atomic Products Operation and in critical experiments at the Oak Ridge National Laboratory. The density of the mixture is 4.5 gm/cc and the U235 enrichment of the uranium is 2.0 wt%, resulting in an H:U235 atomic ratio of 195. The values of k∞ 0.013 and 1.197 ± 0.013 and 1.197 ± 0.015, respectively. In the analysis of the critical experiments a two group model was assumed for the nonleakage probability. The neutron age to thermal was determined from buckling perturbation measurements as 43.1 ± 3.4 cm2. The critical buckling was measured to be (4344 ± 65) × 10−6 cm−2, the bare extrapolation distance 2.7 ± 0.3 cm, and the fast fission factor 1.039 ± 0.004. Within the experimental error, the values of k∞ from critical experiments at ORNL and from the PCTR at HAPO agree.