European Research and Development Programme for Water-Cooled Lithium-Lead Blankets Present Status and Future Work-Reference-Cited by-同舟云学术

European Research and Development Programme for Water-Cooled Lithium-Lead Blankets Present Status and Future Work

Published:1992-05 Issue:3P2B Volume:21 Page:2075-2080
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Giancarli L.¹,Barbier F.²,Flament T.²,Futterer M.²,Leroy P.¹,Proust E.¹,Sannier J.²,Raepsaet X.¹,Terlain A.²,Coen V.³,Perujo A.¹,Sample T.¹,Benamati G.⁴,Agostini P.⁴,

Affiliation:

1. (DRN/DMT/SERMA, CEN Saclay, 91191 Gif-sur-Yvette, France Fax (33) 1 69 08 23 81

2. CEREM/DTM/SCECF, CEN FaR, 92265 Fontenay-aux-Roses, France

3. EC Commission, Joint Research Center, 21020 Ispra (VA), Italy

4. ENEA, Dipartimento Fusione Brasimone, 40032 Camugnano (BO), Italy

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST92-A30027

Reference8 articles.

1. A water cooled, lithium lead breeding blanket for a DEMO fusion reactor

2. S. MALANG, H. JOHN, H. SEBENING, et al. “Self Cooled Liquid Metal Breeder Blanket Status Report. KfK Contribution to the Development of a DEMO-Relevant Test Blanket for NET/ITER”, KfK Internal Report (1991).

3. Kinetics of deuterium desorption from Pb17Li eutectic

4. The use of aluminising on 317 austenitic and 1.4914 martensitic steels for the reduction of tritium leakage from the net blanket

Cited by 8 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development of the EU water-cooled Pb-17Li blanket;Fusion Engineering and Design;1998-09

2. Thermal Breeding of Tritium: A Comparative Study of the Li + C and3He + C Systems;Nuclear Science and Engineering;1997-03

3. Overview of EU activities on DEMO liquid metal breeder blankets;Fusion Engineering and Design;1995-03

4. European Reference Design of the Water-Cooled Lithium-Lead Blanket for a Demonstration Reactor;Fusion Technology;1994-11

5. LIBRETTO-3: Performance of tritium permeation barriers under irradiation at the HFR Petten;Journal of Nuclear Materials;1994-09