Neutronic calculations of a thorium-based fusion–fission hybrid reactor blanket-Reference-Cited by-同舟云学术

Neutronic calculations of a thorium-based fusion–fission hybrid reactor blanket

Published:2010-12 Issue:10-12 Volume:85 Page:2227-2231
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Ma X.B.,Chen Y.X.,Wang Y.,Zhang P.Z.,Cao B.,Lu D.G.,Cheng H.P.

Publisher

Elsevier BV

Subject

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

Reference18 articles.

1. Conceptual study on high performance dual-cooled blanket in a spherical tokamak fusion-driven transmuter;Chen;Chinese Journal of Nuclear Science and Engineering,2004

2. Conceptual study on the fusion-driven sub-critical system;Wu;Chinese Journal of Nuclear Science and Engineering,2004

3. Comparison study of transmutation neutronics calculation for a spherical tokamak;Deng;Nuclear Fusion and Plasma Physics,2003

4. Reactor core design of spherical tokamak transmutation of nuclear wastes;Deng;Chinese Journal of Nuclear Science and Engineering,2002

5. ITER-FEAT—Outline Design Report by the ITER Director, Tokyo, ITER Meeting, 1, 2000, p. 6.

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. Study on the fusion reactor performance with different materials and nuclear waste actinides;International Journal of Energy Research;2020-07-29

2. Monte Carlo analysis of LWR spent fuel transmutation in a fusion-fission hybrid reactor system;Nuclear Engineering and Technology;2018-12

3. A 232Th closed fuel cycle utilizing both a thermal and hybrid nuclear systems;Progress in Nuclear Energy;2015-08

4. Neutronic Study of a Molten Salt Cooled Natural Thorium–Uranium Fueled Fusion–Fission Hybrid Energy System;Journal of Fusion Energy;2014-11-19

5. 3D Neutronic Analysis in MHD Calculations at ARIES-ST Fusion Reactors Systems;Journal of Fusion Energy;2013-10-02