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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Charles Forsberg, Per F. Peterson
Nuclear Technology | Volume 191 | Number 2 | August 2015 | Pages 113-121
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-88
Articles are hosted by Taylor and Francis Online.
The fluoride salt–cooled high-temperature reactor (FHR) is a new reactor type that combines the graphite-matrix coated-particle fuel and graphite moderator from high-temperature gas-cooled reactors (HTGRs) with a clean liquid fluoride salt coolant. No FHR has yet been built. The proposed fuel cycle is a once-through fuel cycle—essentially identical to that of HTGRs. There is the option of adopting closed fuel cycles. Relative to light water reactor (LWR) spent nuclear fuel (SNF), all graphite-matrix coated-particle SNFs share the common characteristics of superior proliferation resistance and long-term performance as a waste form in a geological repository. The allowable HTGR and FHR SNF storage temperatures are much higher than allowable LWR SNF storage temperatures. These SNF characteristics are (a) a consequence of the high-temperature fuel form with a graphite matrix and SiC coating of the fuel microspheres and (b) to a first-order approximation independent of the reactor type in which the fuel is used.
There are differences. The FHR reactor core power density is four to ten times higher than in an HTGR, so the short-term decay heat of the SNF per unit volume upon discharge is four to ten times higher. The volume of FHR SNF is one-half to one-third that of an HTGR per unit energy output because (a) the salt provides some neutron moderation thus reducing the carbon-to-uranium ratio of the fuel and (b) the economic optimization with higher power densities increases the fuel loading. The FHR SNF volume is about four times that of a LWR per unit of electricity. The coolant generates significant tritium that is partly absorbed by the graphite and can be partly desorbed at higher temperatures. Last, any residual solid salt coolant with the SNF at low temperatures can undergo radiolysis with the potential generation of fluorine gas. The presence of the salt coolant on the SNF and graphite moderator will require treatment, removal of residual coolant salt, or demonstration that the small quantities of radiolysis products of frozen salt do not impact long-term performance of storage or disposal facilities.