ANFIBE: A Comprehensive Model for Swelling and Tritium Release from Neutron-Irradiated Beryllium—II: Comparison of Model Predictions with Experimental Results-Reference-Cited by-同舟云学术

ANFIBE: A Comprehensive Model for Swelling and Tritium Release from Neutron-Irradiated Beryllium—II: Comparison of Model Predictions with Experimental Results

Published:1998-03 Issue:2 Volume:33 Page:146-163
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Scaffidi-Argentina Francesco¹,Donne Mario Dalle¹,Ronchi Claudio²,Ferrero Claudio³

Affiliation:

1. Forschungszentrum Karlsruhe, Institut für Neutronenphysik und Reaktortechnik P.O. Box 3640, D-76021 Karlsruhe, Germany

2. Commission of the European Union, Joint Research Centre Karlsruhe Establishment, European Institute for Transuranium Elements P.O. Box 2340, D-76125 Karlsruhe, Germany

3. European Synchroton Radiation Facility B.P. 220, F-38043 Grenoble Cedex, France

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST98-A25

Reference36 articles.

1. ANFIBE: A Comprehensive Model for Swelling and Tritium Release from Neutron-Irradiated Beryllium—I: Theory and Model Capabilities

2. Diffusion/desorption of tritium from irradiated beryllium

3. Tritium and Helium Behavior in Irradiated Beryllium

4. L. SANNEN et al. “Helium Content and Swelling of Low Temperature Irradiated/Post-Irradiated Annealed Beryllium,” CEN/SCK report FT/Mol/93-07.

5. J. M. BEESTON, “Properties of Irradiated Beryllium: Statistical Evaluation,” TREE-1063, EG&G Idaho, Inc. (1976).

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