Fission product monitoring of TRISO coated fuel for the advanced gas reactor-1 experiment
نویسندگان
چکیده
منابع مشابه
Identification of Silver and Palladium in Irradiated TRISO Coated Particles of the AGR-1 Experiment
Evidence of the release of certain metallic fission products through intact tristructural isotropic (TRISO) particles has been seen for decades around the world, as well as in the recent AGR-1 experiment at the Idaho National Laboratory (INL). However, understanding the basic mechanism of transport is still lacking. This understanding is important because the TRISO coating is part of the high t...
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TRISO (Tri-Isotropic)-coated fuel particle is widely applied due to its higher stability at high temperature and its efficient retention capability for fission products in the HTGR (high temperature gas-cooled reactor), one of the highly efficient Generation IV reactors. The typical balltype TRISO-coated fuel particle with a diameter of about 1 mm is composed of a nuclear fuel particle as a ker...
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Current research has identified Duplex pellets as an effective strategy for decreasing the centerline temperature of the fuel. However, before this design can be widely utilized several areas, including fission gas release, need to be better characterized. Therefore, this paper seeks to ascertain the relative difference in fission gas release between a standard solid UO2 reference design and a ...
متن کاملThermomechanics of Candidate Coatings for Advanced Gas Reactor Fuels
Candidate fuel/coating combinations for an advanced, coated-fuel particle for a gascooled fast reactor (GFR) have been evaluated. These all-ceramic fuel forms consist of a fuel kernel made of UC or UN, surrounded with two shells (a buffer and a coating) made of TiC, SiC, ZrC, TiN, or ZrN. These carbides and nitrides are analyzed with finite element models to determine the stresses produced in t...
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The safe and economic operation of nuclear power plants (NPPs) requires that the behaviour and performance of the fuel can be calculated reliably over its expected lifetime. This requires highly developed codes that treat the nuclear fuel in a general manner and which take into account the large number of in uences on fuel behaviour, e.g. thermal, mechanical, chemical, etc. Although many mature...
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ژورنال
عنوان ژورنال: Nuclear Engineering and Design
سال: 2010
ISSN: 0029-5493
DOI: 10.1016/j.nucengdes.2009.10.014