ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
M. L. Simmons, Donald J. Dudziak
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 337-345
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31599
Articles are hosted by Taylor and Francis Online.
An essential element of any fusion or fission reactor materials development effort is the availability of irradiation facilities for conducting radiation effects experiments. A Radiation Effects Facility (REF) was provided for such studies at the Los Alamos Meson Physics Facility. Neutron spectra at the REF can be tailored to approximate those in either a fusion or fission reactor, while providing flux levels of ∼1.4 × 1018 m−2 s−1 at design maximum beam currents. An intranuclear-cascade/evaporation model was used for computing neutron production. Detailed Monte Carlo neutron transport calculations were performed, some of which were experimentally verified in a foil dosimetry program. Such calculations provide the radiation effects experimentalist with information on spatial-spectral variations of the neutron flux over much of the easily accessible experimental volume (∼19 000 cm3), which includes irradiation specimen capsule locations and a rabbit tube. From these data, radiation damage indices such as ratios of parts per million helium to displacements per atom can be calculated and compared to those anticipated in fusion reactor blankets or fast fission reactor cores.