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.
Keiji Tani, Ryuji Yoshino, Takashi Tuda, Tomonori Takizuka, Masafumi Azumi
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 103-113
Technical Paper | Plasma Engineering | doi.org/10.13182/FST92-A29730
Articles are hosted by Taylor and Francis Online.
The technique of ripple injection has been proposed for refueling in tokamak reactors. The usefulness of ripple-assisted fueling has been investigated by using an orbit-following Monte Carlo code. The penetration depth strongly depends on the beam energy. The ripple-enhanced outward flow of ripple-detrapped fast ions is not a serious problem. If Eb/Te0 ≤ 4 is chosen, the fuel efficiency becomes >80%. There is an optimum toroidal angle of the injection beamline to enhance the penetration depth of fast ions, and the range of angles that are effective for fueling is rather wide. The loss of alpha particles incident to the fueling has also been investigated by using the same code. By regulating the shape of the ripple-well region, the total alpha-particle loss can be reduced to <5%. Ripple-assisted fueling in the International Thermonuclear Experimental Reactor (ITER) has also been investigated. Because of the small aspect ratio, the field ripple is strongly decayed in the plasma. Consequently, central fueling presents some difficulties in ITER. However, fueling near one-half of the plasma minor radius is possible with an ∼6% alpha-particle power loss.