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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
General Kenneth Nichols and the Manhattan Project
Nichols
The Oak Ridger has published the latest in a series of articles about General Kenneth D. Nichols, the Manhattan Project, and the 1954 Atomic Energy Act. The series has been produced by Nichols’ grandniece Barbara Rogers Scollin and Oak Ridge (Tenn.) city historian David Ray Smith. Gen. Nichols (1907–2000) was the district engineer for the Manhattan Engineer District during the Manhattan Project.
As Smith and Scollin explain, Nichols “had supervision of the research and development connected with, and the design, construction, and operation of, all plants required to produce plutonium-239 and uranium-235, including the construction of the towns of Oak Ridge, Tennessee, and Richland, Washington. The responsibility of his position was massive as he oversaw a workforce of both military and civilian personnel of approximately 125,000; his Oak Ridge office became the center of the wartime atomic energy’s activities.”
D. Lousteau, K. Ioki, L. Bruno, A. Cardella, F. Elio, M. Hechler, T. Kodama, A. Lodato, D. Loesser, N. Miki, K. Mohri, R. Raffray, M. Yamada
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 384-389
International Thermonuclear Experimental Reactor (ITER) | doi.org/10.13182/FST98-A11963644
Articles are hosted by Taylor and Francis Online.
The ITER blanket system removes the surface heat flux from the plasma and from bulk heating by the neutrons, reduces the activity in the vacuum vessel (W) structural material to the level allowable to ensure vessel reweldability for the ITER fluence goal and, in combination with the vacuum vessel, protects the superconducting coils and other ex-vessel components from excessive nuclear heating and radiation damage. The blanket system contributes with its eddy currents to the passive stabilization of the plasma motion. It minimizes the effects of electromagnetic loads on the VV due to plasma disruptions, and provides a well defined load path to the VV for net vertical and horizontal loads arising from vertical displacement events (VDE's). The system is designed to allow the possibility of replacing the shield with a breeding blanket, within the same dimensional, maintenance, and coolant constraints, to provide the tritium to meet the technical objectives of the Enhanced Performance Phase.
The basic blanket system concept as well as the arrangement and function of its components is essentially unchanged from that established in 19951. However, as discussed in this paper, the design of each component has progressed significantly as a result of the detail design and technical analysis efforts of the last two years. The main components of the blanket system are:
• A back plate: a structure comprising a double wall shell that supports the first wall/shield modules and routes the coolant water to them.
• First wall/shield modules: comprising a plasma facing first wall (FW) section, and a shielding (or later breeding) section. Primary wall and baffle modules are distinguishable by the function of their FW.
• Limiters: define the plasma boundary during plasma start-up and shutdown and are located in equatorial ports.
• Flexible connectors, electrical straps, and branch pipes: the remote handling compatible structural, electrical, and cooling connections between the modules and back plate.
• Filler shields: shielding permanently mounted to the back plate in the triangular gaps between FW/shield modules.
The system will use austenitic stainless steel 316L(N)-IG (ITER Grade) as the primary structural material cooled by water with inlet conditions of 3.8 MPa and 140°C. The plasma facing surface of the FW will be beryllium except the lower region of the baffles, where tungsten is used. The electrical straps and heat sink layer in the FW will be copper alloy. A titanium alloy is the prime candidate material for the flexible connectors.