Shielding materials for fusion reactors

Abstract

There is described neutron shielding for a nuclear fusion reactor. The neutron shielding includes a cemented carbide or boride comprising a binder and an aggregate, the aggregate comprising particles of a carbide or boride compound.

1 . A divertor for a nuclear fusion reactor, the divertor including a cemented carbide or boride comprising a binder and an aggregate, the aggregate comprising particles of a carbide or boride compound of tungsten, tantalum or hafnium. 
     
     
         2 . A divertor according to  claim 1 , wherein the composition of the cemented carbide or boride varies through the thickness of the cemented carbide or boride. 
     
     
         3 . A divertor according to  claim 2 , wherein a plasma-facing side of the cemented carbide or boride comprises a lower proportion of neutron absorbing material than a non-plasma facing side of the cemented carbide or boride. 
     
     
         4 . A divertor according to  claim 1 , wherein the binder comprises a metal. 
     
     
         5 . Neutron shielding according to  claim 4 , wherein the binder comprises iron and/or chromium. 
     
     
         6 . Neutron shielding according to  claim 1 , wherein the cemented carbide or boride does not comprise cobalt or nickel.