Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket-Reference-Cited by-同舟云学术

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Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket

Published:2017-11 Issue: Volume:124 Page:1257-1262
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Palermo Iole,Garcia Raquel,Garcia Mauricio,Sanz Javier

Funder

Euratom research and training programme

Spanish MINECO

Comunidad de Madrid

ETS II-UNED

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference33 articles.

1. Assessment of the activation, decay heat, and waste disposal of the US helium-cooled ceramic breeder test blanket module in ITER

2. Activation, decay heat and waste analysis for a European HCLL DEMO concept

3. JET experience on managing radioactive waste and implications for ITER

4. Radioactive waste assessment for the IFMIF/EVEDA facility

5. Activation analysis and waste management of China ITER helium cooled solid breeder test blanket module

Cited by 10 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 waste products of EU DEMO – Focus on tungsten dust reprocessing;Fusion Engineering and Design;2024-03

2. Preliminary assessment of the safety factors in K-DEMO for fusion compatible regulatory framework;Scientific Reports;2022-05-18

3. Activation analysis and radwaste assessment of CFETR;Fusion Engineering and Design;2022-03

4. Radiological characterization of ceramic materials considered for the HT-DCLL DEMO reactor;Nuclear Materials and Energy;2022-03

5. Waste expectations of fusion steels under current waste repository criteria;Nuclear Fusion;2021-01-27

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