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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
Dennis G. Vasilik, Richard L. Murri, George P. Fisher
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 279-283
Technical Paper | Instrument | doi.org/10.13182/NT72-A31117
Articles are hosted by Taylor and Francis Online.
Neutron radiography studies have been conducted using an accelerator source of 14.3 ± 0.3 MeV neutrons and a water moderator. The yield of the accelerator was 6.18 × 101 n/sec. The peak thermal-neutron flux of the system was measured to be 6.87 × 107 n/(cm2 sec) at 5.1 cm from the source. A cadmium ratio of 3.4 was measured at this position. A theoretical two-group analysis of the thermal-neutron flux distribution was also performed. The experimental data verified the theoretical results. Neutron multiplication experiments were also conducted by bombarding a 238U target surrounded by the water moderator. It was experimentally determined that 2.5 cm of 238U yielded a maximum multiplication factor of 2.5.
