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.
F. N. McDonnell, A. P. Baudouin, P. M. Garvey, J. C. Luxat
Nuclear Science and Engineering | Volume 64 | Number 1 | September 1977 | Pages 95-105
Technical Paper | doi.org/10.13182/NSE77-A27081
Articles are hosted by Taylor and Francis Online.
A description of reactor kinetics benchmark activity in support of the Canadian naturaluranium heavy water (CANDU) reactor program is presented. Two benchmark problems with neutronic characteristics resembling current generation CANDU reactors have been defined, and accurate solutions to both problems are summarized. In addition, the performance of an improved quasi-static code has been tested and compared with a finite difference method. A brief description of the reactor kinetics experimental program related to reactor transient studies is also given.