Fusion Reactor Blanket Neutronic Studies in France-Reference-Cited by-同舟云学术

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Fusion Reactor Blanket Neutronic Studies in France

Published:1983-09 Issue:2P3 Volume:4 Page:799-804
ISSN:0272-3921
Container-title:Nuclear Technology - Fusion
language:en
Short-container-title:Nuclear Technology - Fusion

Author:

Barré F.¹,Gervaise F.¹,Giancarli L.¹

Affiliation:

1. Centre d’Etudes Nucléaires de Saclay, Service d’Etudes des Réacteurs et de Mathématiques Appliquées, 91191 GIF-sur-YVETTE CEDEX (16-6) 908-21-37

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST83-A22958

Reference2 articles.

1. D.J. DUDZIAK, “Discrete-Ordinate Neutronic Analysis of a Reference Theta-Phinch Reactor (RTPR),” LA-DC-72-1427, Los Alamos National Laboratory (1972).

2. D. GARBER (Compiler), ENDF/B Summary Documentation. BNL-1761, Brookhaven National Laboratory (1975).

Cited by 7 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. Solid breeder blanket design and tritium breeding;Fusion Engineering and Design;1991-12

2. Optimal Use of Beryllium for Fusion Reactor Blankets;Fusion Technology;1988-01

3. Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base;Fusion Technology;1986-03

4. Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors;Fusion Technology;1986-03

5. AN ALTERNATIVE NEUTRONICS SOLUTION FOR LIQUID LITHIUM BLANKETS;Fusion Technology 1986;1986

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