Search
Now showing items 11-12 of 12
An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle
(2015-12-01)
The thorium fuel cycle is a promising future option for an alternative to uranium. The pressure tube heavy water reactor (PT-HWR) has for decades been considered capable of achieving net breeding on the thorium fuel cycle, ...
Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices
(2010-04-01)
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutron transport equation for a detailed-geometry model using several tens of energy groups. However, performing such detailed ...