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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
August 2026
Nuclear Technology
July 2026
Fusion Science and Technology
Latest News
Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
K. M. Barry, J. A. Corbett
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 120-130
Technical Paper | Analysis | doi.org/10.13182/NT71-A30910
Articles are hosted by Taylor and Francis Online.
Experimental irradiations of pressure vessel materials were conducted at the Saxton reactor and Babcock & Wilcox Test Reactor to provide radiation effects data for fast neutron fluences up to 1 × 1020 n/cm2 (E > 1 MeV). Included in the capsule assemblies were 237Np and 238U dosimeters and 54Fe correlation monitors. The activities of the dosimeters were combined with the neutron spectrum calculations of a multigroup diffusion code to establish the fast-neutron (E > 1 MeV) fluences experienced by the dosimeters. For both reactors the fluences derived from the different dosimeters were in good agreement indicating both the adequaey of the spectral predictions and the successful application of the fission dosimeters. It is shown that the 237Np and 238 U dosimeters are responsive to a wider range of neutron energies than the more commonly used threshold detectors and are therefore better able to ensure the aptness of calculated neutron spectra. This effort has indicated that the use of 237Np and 238U dosimeters in power reactor vessel surveillance programs leads to more meaningful correlations between neutron fluence and induced radiation effects.