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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.
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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!
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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.
Masaaki Mori and Mitsuru Kawamura, Koichi Yamate
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 41-51
Technical Paper | doi.org/10.13182/NSE95-A24127
Articles are hosted by Taylor and Francis Online.
A benchmark study is presented of new methodologies of the Studsvik CASMO-4/SIMULATE-3 advanced nuclear design code system against a pressurized water reactor (PWR)-type mixed-oxide (MOX) fuel critical experiment with high plutonium content. Both CASMO-4 two-dimensional transport core calculations and SIMULATE-3 nodal core calculations that use the pin power reconstruction model are performed for the experimental geometries. All the assembly two-group constants for SIMULATE-3, including those for MOX assemblies, are generated by CASMO-4 singleassembly calculations. The CASMO-4 improved transmission probability method and the SIMULATE-3 improved nodal and spectral interaction models are verified to be effective for accurate prediction of the pin power distribution inside high plutonium content PWR MOX assemblies and UO2 assemblies that are adjacent to the MOX assemblies.
