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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.
Jennifer S. Butler, Darvin Kapitz, Robert P. Martin, Farrokh Seifaee, Ramu K. Sundaram
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 244-260
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Reactor Safety | doi.org/10.13182/NT10-A9462
Articles are hosted by Taylor and Francis Online.
AREVA NP's U.S. EPR is a 4590-MW(thermal) evolutionary pressurized water reactor that incorporates proven technology with an innovative system architecture to provide an unprecedented level of safety. One of the measures of safety is provided by probability risk assessment (PRA). PRA Level 1 concerns the evaluation of core damage frequency based on various initiating events and the success or failure of various plant event mitigation features. Determination of this measure requires mission success criteria, which are used to build the logic that makes up the fault trees and event trees of the Level 1 PRA. Developing mission success criteria for the wide variety of accident sequences modeled in the PRA Level 1 model requires a large number of thermal-hydraulic calculations. AREVA selected the MAAP4 code to perform these calculations because of its fast computation times relative to more sophisticated thermal-hydraulic codes. This is a unique application of the MAAP4 code, which was developed specifically for severe accident and PRA Level 2 analysis. As such, a study was performed to assess MAAP4's thermal-hydraulic response capabilities against AREVA's S-RELAP5 best-estimate integral systems thermal-hydraulic analysis code.