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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
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.
Sergei Zimin
Fusion Science and Technology | Volume 24 | Number 2 | September 1993 | Pages 168-179
Technical Paper | Shielding | doi.org/10.13182/FST93-A30223
Articles are hosted by Taylor and Francis Online.
An extensive analysis of the sensitivity of the fast neutron flux in the superconductor, the dose to the electrical insulator, and the number of displacements per atom in the copper stabilizer to variations of the neutron cross sections for the International Thermonuclear Experimental Reactor (ITER)/OTR inboard region (first wall/blanket/shield/vacuum vessel) was carried out. All of the nuclides with a significant concentration in the ITER/OTR inboard region were investigated, namely, iron, chromium, nickel, lead, oxygen, hydrogen, boron, copper, 6Li, and 7Li. The integrated total sensitivities of iron, lead, hydrogen, and oxygen were compared with the results for the OTR and Next European Torus (NET) sensitivity analyses. The integrated total sensitivity of both the fast neutron flux and the dose to variation of lead cross sections for the ITER/OTR was much higher than that for the OTR, namely, 3.5 and 1.2, respectively. The difference in the integrated total sensitivities of the inboard toroidal field coil responses to a one standard deviation variation of the iron, hydrogen, and oxygen neutron cross sections was <30%. The most important energy regions and the types of neutron cross sections for shield calculations were identified. The uncertainty of the neutron cross sections in the important energy regions needs to be decreased to <10% to decrease the uncertainty of the calculated neutron dose and fast flux behind the ITER/OTR inboard shield to <15 to 30%.
