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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
3D-printed tool at SRS makes quicker work of tank waste sampling
A 3D-printed tool has been developed at the Department of Energy’s Savannah River Site in South Carolina that can eliminate months from the job of radioactive tank waste sampling.
D. B. MacMillan
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 329-336
Technical Paper | doi.org/10.13182/NSE70-A19994
Articles are hosted by Taylor and Francis Online.
A mathematical method is described for the computation of the probability distribution of neutron populations in a point reactor with a weak source. The author and his colleagues have previously described a method for doing such computations, and G. I. Bell has described a different method; the present paper uses ideas from both of these older methods plus new formulations for computing the probability distribution from values of the generating function, for evaluating the probability distribution of precursor decay rates instead of that of neutron populations, and for evaluating the effect of short neutron lifetime without using unnecessarily short time steps in numerical integration. As a result, the method presented here is more widely applicable and more accurate than the older methods. The reactor model used here permits taking account of six delayed-neutron precursor groups and of finite neutron lifetime.