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
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
Last of Cs-137 irradiators removed from South Carolina
The Department of Energy’s National Nuclear Security Administration announced that it has successfully removed all cesium-137 irradiators from South Carolina, as the agency seeks to eliminate radiological threats and protect communities.
Cs-137 sources are commonly used to irradiate cellular blood cells prior to transfusion to prevent graft-versus-host disease, where the donated cells view the recipient’s cells as an unfamiliar threat. If stolen from a less-secure facility, however, the cesium inside the irradiators could be used to create a radiological dispersal device, commonly referred to as a dirty bomb.
Yoshihiro Asano, Takeshi Sugita, Hideyuki Hirose, Takenori Suzaki
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 251-259
Technical Paper | doi.org/10.13182/NSE05-A2544
Articles are hosted by Taylor and Francis Online.
The distributions of thermal neutrons and capture gamma rays in ordinary concrete were investigated by using 252Cf. Two subjects are considered. One is the benchmark experiments for the thermal neutron and the capture gamma-ray distributions in ordinary concrete. The thermal neutron and the capture gamma-ray distributions were measured by using gold-foil activation detectors and thermoluminescence detectors. These were compared with the simulations by using the discrete ordinates code ANISN with two different group structure types of cross-section library of a new Japanese version, JENDL-3.3, showing reasonable agreement with both fine and rough structure groups of thermal neutron energy. The other is a comparison of the simulations with two different cross-section libraries, JENDL-3.3 and ENDF/B-VI, for the deep penetration of neutrons in the concrete, showing close agreement in 0- to 100-cm-thick concrete. However, the differences in flux grow with an increase in concrete thickness, reaching up to approximately eight times near 4-m thickness.