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The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
R. Durrer, T.A. Parish, G. Schlapper, R. Carrera
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1337-1341
Result of Large Experiment and Plasma Engineering | doi.org/10.13182/FST91-A29528
Articles are hosted by Taylor and Francis Online.
The IGNITEX experiment is being designed to study the physics of ignited plasmas. Over the service lifetime of the device (two years), it is expected to be pulsed 2,000 times with each pulse producing 150 MW of DT fusion power for approximately five seconds. Neutrons from each pulse will activate the magnet structure, liquid nitrogen in the cryostat and test cell air. Radioactive effluents from IGNITEX will primarily result from activated air, activated liquid nitrogen, and tritium. To provide a perspective for evaluating the doses resulting from the gaseous effluents from IGNITEX, the doses from the gaseous effluents from a 1 MW fission research reactor were also calculated.For both facilities, the primary effluents are airborne. Two dose receptor locations were assumed. The first was taken to be the building nearest to the facility and it was taken to be 400 m distant. The second was the nearest residence and it was taken to be 1.2 km distant. For the dose calculations, the air stability was assumed to be neutral and the dose receptors were assumed to be in the direction of a 4.5 m/sec prevailing wind. All releases were taken to be at ground level. The equations used to calculate the annual doses were taken from Regulatory Guide 1.109. The gaseous effluents from IGNITEX were assumed to consist of 41Ar, 13N, 16N, 14C, and 3H. Effluents from the fission research reactor consisted of 41Ar, gaseous and semi-volatile fission products. Each facility's dose was compared to the 10CFR50 Appendix I limits. In each dose category, with the exception of the thyroid dose the dose resulting from the operation of IGNITEX were more than that of the fission reactor. The increased doses were due primarily to the activated nitrogen releases.
