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
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
Bechtel-led SIMCO awarded three-year WIPP contract extension
The Department of Energy has issued a three-year contract extension to Salado Isolation Mining Contractors (SIMCO), a single-purpose entity comprising Bechtel National and Los Alamos Technical Associates as a teaming contractor, for the continued management and operations of the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-generated transuranic waste in southeastern New Mexico.
Yoshihiro Yamane, Minoru Shinkawa, Kojiro Nishina
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 244-255
Technical Paper | doi.org/10.13182/NSE79-A19469
Articles are hosted by Taylor and Francis Online.
For single-core reflected neutronic systems, generalized neutron generation time is derived and given physical interpretations in terms of importance. A system kinetic equation containing the moderator region response function previously introduced is reduced by a slow-variation approximation to the form of a conventional one-point kinetic equation, in which a parameter can be identified as generalized neutron generation time by analogy with a bare system. In such a mathematical expression for the parameter, one can further identify the amount of increase due to reflection over the bare system generation time. This amount is found to be the reflection time multiplied by the number of migrations that neutrons undergo between reflector and core in one generation. The theoretical generation time of the SHE assembly, a thermal-energy, graphite-moderated critical assembly, calculated by such a formulation with cylindrical geometry, agreed well with that from pulsed neutron experiments.