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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
David D. Clark, Carol G. Ouellet, J. Scott Berg
Nuclear Science and Engineering | Volume 110 | Number 4 | April 1992 | Pages 445-454
Technical Paper | doi.org/10.13182/NSE92-A23917
Articles are hosted by Taylor and Francis Online.
Two major parts of the design study for a cold source for the cold neutron beam facility under construction at the Cornell University 500-kW TRIG A reactor are presented. The reasons are discussed for choosing mesitylene as the cold moderator and for choosing conduction through copper rods between the source and a cryogenic refrigerator as the cooling method, the basic criteria for these choices being safety and simplicity of operation. Measurements of the neutron fluxes and nuclear heating rates at the proposed source location are reported. A description is provided of studies to optimize the size and shape of the cold source within the restrictions imposed by the limited available volume, the measured radiation levels, and the chosen materials using Monte Carlo simulation with a personal computer. It is concluded that mesitylene cooled by conduction through copper can provide a very satisfactory, safe, and simple cold source for an intermediate-power research reactor.