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.
Jerry E. Dick, Vijay I. Nath, Erl Kohn, Thomas K. Min, Soedi Prawirosoehardjo
Nuclear Technology | Volume 90 | Number 2 | May 1990 | Pages 155-167
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34411
Articles are hosted by Taylor and Francis Online.
The CANDU-6 nuclear reactor is a 600-MW(elec-tric) channel reactor in which natural uranium fuel is located in channels and surrounded by three separate water systems containing a total of ∼900 000 kg of water. Its four steam generators contain an additional 129000 kg of water. A recent study of a dominant core melt category indicates that this abundance of water effectively retards the melt progression and mitigates accident consequences. The inventory of all three water systems plus that of the steam generators must boil off before the core’s calandria vessel is breached. The steam produced from this boiloff vents to the containment atmosphere where it enhances passive heat removal on surfaces, promotes rapid aerosol settling by condensation on airborne particles, and reduces the concentration and flammability of the hydrogen generated. Breach of the calandria vessel allows molten core to enter a thick-walled concrete calandria vault. The resulting core/concrete reaction penetrates the calandria vault floor ∼2½ days after the beginning of the accident. Core debris, well diluted by decomposition products, then falls into an estimated 2 000 000 kg of water in the reactor basement. This water quenches and disperses the debris and essentially terminates the event sequence. Continuing decay heat is dissipated by minor steaming and by heat transfer through the basement floor and walls into the surrounding bedrock.