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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
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Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Tim D. Bohm, Edward P. Marriott, Mohamed E. Sawan
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 595-600
Technical Paper | doi.org/10.1080/15361055.2017.1350484
Articles are hosted by Taylor and Francis Online.
The ITER vacuum vessel (VV) is a double walled toroidal shaped stainless steel structure divided into nine 40 degree sectors. In the design process for the ITER blanket system (which provides shielding for the VV), determining integrated nuclear heating loads on the VV is important for cooling system sizing and determining localized nuclear heating on the VV is important for assessing thermal stress loads. Further, determining radiation damage, displacements per atom (dpa) on the VV, is important in meeting pressure vessel limits. Near the neutral beam injection (NBI) region of the VV (both sector 2 and sector 3), there are significant gaps and cut-outs in the blanket system to accommodate the 3 heating neutral beam (HNB) ports and the diagnostic neutral beam (DNB) port. These features lead to higher localized radiation loads. Previous analysis indicated high nuclear heating and dpa in the NBI region. The CAD based DAG-MCNP5 transport code was used to perform neutronics calculations in detailed, updated CAD models of the NBI region. For this work, a 40 degree model of sector 2 (which includes the HNB1 port, the DNB port, and the HNB2 port) was analyzed. Three design options were investigated which add shielding in the DNB port region by using port liners. Mesh tally maps of both nuclear heating and dpa are provided for the VV in the BM13-16 region. Peak dpa values ranged from 0.41–0.65 dpa. Two of the 3 design options investigated had peak dpa values near the DNB port within the ITER dpa limit of 0.5 dpa. Peak nuclear heating results ranged from 1.7 W/cm3 to 2.0 W/cm3. The mesh tally maps of nuclear heating have been provided to the ITER Organization for subsequent finite element engineering analysis. Preliminary analysis has shown the thermal stress levels are unacceptable with the added shielding. The results of this work are being used by the ITER Blanket and Tokamak Integration groups to assess the current design and modify blanket module (BM) design where needed if radiation loads are excessive.
