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论文类型：期刊论文

发表时间：2015-08-01

发表刊物：21st International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI)

收录刊物：SCIE、EI、CPCI-S、Scopus

卷号：463

页面范围：970-973

ISSN号：0022-3115

摘要：Prediction and control of tritium inventory in plasma-facing components (PFCs) is a critical nuclear safety issue for ITER and future fusion devices. This goal can be achieved through rate equations models as presented here. We calibrate our models with thermal desorption spectrometry results to obtain a validated set of material parameters relevant to hydrogen inventory processes in bulk tungsten. The best fits are obtained with two intrinsic trap types, deep and shallow, and an extrinsic trap created by plasma irradiation and plastic deformation of the tungsten matrix associated with blister formation. We then consider a realistic cycle of plasma discharges consisting of 400 s of plasma exposure followed by a resting period of 1000 s, repeating for several hours. This cycle is then closed by a long "overnight" period, thus providing an estimate of the amount of tritium retained in the PFCs after a full day of standard operation. (C) 2014 Elsevier B.V. All rights reserved.