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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
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Fusion Science and Technology
Latest News
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
Micah D. Lowenthal
Fusion Science and Technology | Volume 34 | Number 1 | August 1998 | Pages 46-65
Technical Paper | doi.org/10.13182/FST98-A52
Articles are hosted by Taylor and Francis Online.
An analysis is presented of the radioactive wastes from the International Thermonuclear Experimental Reactor (ITER) and how those wastes would fit into the regulatory environments of four potential host nations: France, Germany, Japan, and the United States. The reactor described in the ITER Draft Interim Design Report is used as the basis for the radioactive inventory assessments that are carried out using ONEDANT for the neutron transport calculations and ACAB for the activation calculations. The radioactive material produced by operation of the reactor is rated according to the protocols for waste management in each nation and at specific disposal sites currently operating in those nations. Results of the assessments vary drastically between disposal sites - even between near-surface-burial sites within the U.S. Department of Energy. One disposal site (Westinghouse Hanford Company) could accept all of ITER's wastes after a storage and cooling period (all wastes are assessed at 30 yr after shutdown). Other sites (the Savannah River and the Nevada Test Sites) could not accept any components within the toroidal field coils, similar to the restrictions in Germany. Blanket modules would be excluded from near-surface burial in France and Japan, but other components may qualify.