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November 9–12, 2025
Washington, DC|Washington Hilton
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Russia withdraws from 25-year-old weapons-grade plutonium agreement
Russia’s lower house of Parliament, the State Duma, approved a measure to withdraw from a 25-year-old agreement with the United States to cut back on the leftover plutonium from Cold War–era nuclear weapons.
G. W. Brunson, W. D. Booth, R. Carrera, W. F. Weldon
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1149-1153
Ignition Device | doi.org/10.13182/FST91-A29498
Articles are hosted by Taylor and Francis Online.
A basic requisite of the Fusion Ignition Experiment (IGNITEX)1 is the production of a high (20 T) toroidal field (TF) by a single turn coil. The proposed high-field technology uses precooling and preloading systems. The Ignition Technology Demonstration (ITD) program, designed to produce 20 T on axis in a 0.06 scale prototype TF coil, utilizes a preloading structure and a precooling system. The preloading structure is a hydraulic press built around the TF coil, capable of a force of 1.1 Mlb (4.9 MN) and a stroke of 0.5 in. (1.3 cm). The precooling system is an open-top LN2 cryostat tub integrated into the preload press. The IGNITEX experiment is estimated to use a preload press with force capacity of approximately 150,000 tons (1.3 GN), and with a stroke on the order of 2 in. (5.1 cm). Design considerations include efficient use of material, design of large scale hydraulic actuators, shielding to reduce radiation from activated material, maintenance, cost, and reliability. The precooling system design involves considerations of feedthroughs, minimal cooling time between pulses, maintenance and reliability.