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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 449-459
Technical Paper | Blanket Engineering | doi.org/10.13182/FST91-A29385
Articles are hosted by Taylor and Francis Online.
Neutronics parameters including the source neutron spectrum, activation rates, and the tritium breeding in the Li2O test zone of the Fusion Neutron Source Phase II experiment performed at the Japan Atomic Energy Research Institute are calculated using the Monte Carlo code MORSE with ENDF/B-V transport and reaction cross sections. Favorable comparisons between the measured and calculated results are achieved for the 27Al(n,α), 58Ni(n,p), 93Nb(n,2n), and 197Au(n,2n) reactions. Calculated 58Ni(n,2n) and 197Au(n,γ) reactions do not agree with measured values within 10 to 40%. For the nickel reaction, the differences may be due to poor data in the ORACT files, while discrepancies for the gold data may be due to unknown quantities of hydrogen-rich epoxy used to coat the Li2CO3 blocks used in the test assembly walls. The calculated tritium breeding in the Li2O agrees with experimental values within ±10% for 6Li and ±15 to 20% for 7Li.