Microstructure, thermophysical properties and neutron shielding properties of Gd/316 L composites for spent nuclear fuel transportation and storage

Author:

Qi Zheng-Dong,Yang Zhong,Meng Xian-Fang,Yang Xi-Gang,Liang Min-Xian,Li Chang-Yuan,Dai Ye

Publisher

Elsevier BV

Subject

Materials Chemistry,Mechanics of Materials,General Materials Science

Reference41 articles.

1. Uranium the element: its occurrence and uses;Awan;J. Chem. Soc. Pak.,2015

2. Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials;Kim;Ann. Nucl. Energy,2019

3. Research progress in neutron absorbers materials for reactor spent fuel store and transportation applications;Li;Mater. Rep.,2011

4. Research status and prospect of neutron absorbing materials for nuclear shielding;Chen;Rare Met. Mater. Eng.,2020

5. The advancement of neutron-shielding materials for the transportation and storage of spent nuclear fuel;Qi;Materials,2022

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