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
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
Imre Pázsit
Nuclear Science and Engineering | Volume 112 | Number 4 | December 1992 | Pages 369-374
Technical Paper | doi.org/10.13182/NSE92-A23985
Articles are hosted by Taylor and Francis Online.
A new and simple derivation of the neutron transport equation is given. The approach is similar to that used in the Liouville equation and its applications to the Boltzmann equation in that it is formulated in terms of the one-particle or one-point density function, as opposed to the traditional reactor physics approach of counting neutrons in a volume of the phase-space. It makes use of the recognition that the expected number of particles in a phase cell dV is the same as the probability of finding one particle in dV. A novelty of the derivation here is that because of the linear Markovian property of the process, it is possible to derive a master (Chapman-Kolmogorov) equation for the one-particle density, that is, for the neutron density or neutron flux of the traditional transport equation. This way, the forward and the backward (adjoint) equations of neutron transport can be derived from a single master equation. The variance of the one-point distribution function is also derived, and an explicit solution is given.