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.
R. T. Santoro, J. M. Barnes,R. G. Alsmiller, Jr.,J. D. Drischler
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 584-595
Technical Notes | doi.org/10.13182/NSE86-A18614
Articles are hosted by Taylor and Francis Online.
Measured and calculated neutron and gamma-ray energy spectra from ∼14-MeV neutrons streaming through a stainless steel duct having a length-to-diameter ratio of 4.6 are compared. The 1.45-m-long duct is imbedded in a concrete block. The spectra were measured with an NE-213 liquid scintillator as a function of detector location relative to the mouth of the duct. The calculated data were obtained using the Monte Carlo code MCNP and the discrete ordinates code DOT 4.3. The calculations were performed using a two-dimensional cylindrical model of the experiment with symmetry about the duct axis. The measured and calculated neutron and gamma-ray spectra are compared at two distances from the mouth of the duct and at detector locations on and off the duct axis. The neutron spectra calculated with MCNP agree with the measured data within ∼5 to 50% at all detector locations. The data calculated using the discrete ordinates method are in good agreement with the experiment for the cases where the detector is on axis but are in poor agreement at the off-axis detector locations. The gamma-ray spectra calculated with both radiation transport methods are in good agreement (∼5 to 25%, depending on photon energy) with the measured spectra.