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
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.
A. Kumar, Y. Ikeda, C. Konno
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1979-1988
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29632
Articles are hosted by Taylor and Francis Online.
The experimental measurement of nuclear heat deposition rates in a simulated D-T fusion neutron environment has assumed importance due to untested nature of large body of kerma factor libraries. An experimental effort was recently initiated to develop and apply calorimetric technique to measure heat deposition in various materials subjected to D-T neutron fields, in the framework of JAERI/USDOE collaborative program on fusion neutronics. Thermistors and platinum RTD's were employed as thermal sensors within calorimeters made of single materials (or probes). The first experiments were conducted during June 1989 and the tested materials included: Fe, Al, C, Cu. Each of these calorimeters was placed inside a vacuum chamber and the mean distance from the target was ∼8 cm. The calorimeters were subjected to spaced neutron pulses of 3 to 10 min duration. The measured heat deposition rates ranged from 7 to 30 µW/g for a normalized source strength of 1012 n/s-iron and graphite providing the lowest and the highest rates respectively. These single probe experiments were analyzed using 3D code MCNP. The single probe experiments were carried out again in december 1989. This allowed to verify the reproducibility. This time, the average target-probe distance was shortened to ∼5 cm which led to 2 to 3 times higher rates. Tungsten was also included. Ratio of computed (C) to measured (E) rates varied from 0.79 to 1.77 for RMCCS evaluation of MCNP. Four evaluations, available with MCNP, throw up large deviations; For example, C/E for iron for an experiment ranges from 0.40 to 0.94. In addition to single probe experiments, two novel experiments were conducted with multiple probes in separate host media of iron and graphite. C/E varied from 0.51 to 2.36.