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Materials Science & Technology
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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
IAEA promoting nuclear energy with G20
The International Atomic Energy Agency launched a collaboration with the Group of 20 this week to highlight the key role that nuclear energy can play in achieving energy security and climate-change goals.
The aim of this first-of-its-kind partnership with G20—the world’s largest economic group—is to build momentum for nuclear power. This is the first time the IAEA has presented to G20 on issues relating to nuclear power.
A C Bell, J L Hemmerich, R Lässer, N Bainbridge, G Bishop, D Brennan, C Caldwell-Nichols, J Campbell, A Dearden, B Grieveson, G Jones, J Lupo, J Mart, A Perevezentsev, N Skinner, R Stagg, K Walker, R Warren, J Yorkshades
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1301-1306
Design, Operation, and Maintenance of Tritium System | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30590
Articles are hosted by Taylor and Francis Online.
The Joint European Torus (JET) carried out the first preliminary experiment with a deuterium-tritium plasma in 1991. This utilised an on-site inventory of 0.25g. The future experimental programme for the JET machine includes two discrete phases using plasmas fuelled by deuterium and tritium. The first of these, in mid-1996, will generate around 2 × 1020 neutrons and require a site inventory of a few grams of tritium. The second is proposed to take place in 1999 if an extension to the JET project from 1996 is granted. This will require a few tens of grams of tritium and will generate up to 5 × 1021 neutrons. The JET Active Gas Handling System has been constructed to enable tritium to be recovered from the plasma exhaust and stored for re-injection. The design also minimises tritium discharges to the environment. It is currently being commissioned to meet the above programme and has been modified to take into account a new requirement for operation over extended periods during maintenance and D-D operation with tritium contaminated plasma exhaust. Commissioning of the Active Gas Handling System consists of inactive, trace tritium (∼40TBq) and full tritium (<3g) phases. The experience and main results of inactive commissioning are presented and the status of tritium commissioning is reviewed.
