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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
The JT-60SA project
JT-60SA (Japan Torus-60 Super Advanced) is the world’s largest superconducting tokamak device. Its goal is the earlier realization of fusion energy (see Fig. 1). Fusion is the energy that powers the Sun, and just 1 gram of deuterium-tritium (D-T) fuel produces enormous energy—the equivalent of 8 tons of crude oil.
Last fall, the JT-60SA project announced an important milestone: the achievement of the tokamak’s first plasma. This article describes the objectives of the JT-60SA project, achievements in the operation campaign for the first plasma, and next steps.
H. G. Groehn
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 392-400
Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32866
Articles are hosted by Taylor and Francis Online.
The effect of cross flow on the main coolant flow was studied at a two block test section on the model scale of 1:1. The cross flow was introduced through a wedge-shaped gap located between the two succeeding fuel blocks mentioned. The gap width varied from 1.85 to 6 mm. The entrance area for the cross flow was modified by the arrangement of blocking pieces around the circumference of the gap. The velocity distribution over the cross section of the fuel blocks and the pressure loss over the gap were measured. The experimental results allow the prediction of the flow reduction in each coolant channel of the fuel block depending on the transverse pressure gradient driving the cross flow.