Neutronics Assessment of Molten Salt Breeding Blanket Design Options

2005 ◽  
Vol 47 (3) ◽  
pp. 510-517 ◽  
Author(s):  
M. E. Sawan ◽  
S. Malang ◽  
C. P. C. Wong ◽  
M. Z. Youssef
Keyword(s):  
Molten Salt ◽  
Blanket Design ◽  
Design Options

Safety assessment of two advanced ferritic steel molten salt blanket design concepts

2004 ◽  
Vol 72 (1-3) ◽  
pp. 277-306 ◽  
Author(s):  
B.J. Merrill ◽  
M. Sawan ◽  
C.P.C. Wong ◽  
R.E. Nygren ◽  
L.C. Cadwallader ◽  
...  
Keyword(s):  
Molten Salt ◽  
Ferritic Steel ◽  
Safety Assessment ◽  
Design Concepts ◽  
Blanket Design ◽  
Molten Salt Blanket

scholarly journals CORE DESIGN OF BREED & BURN MOLTEN SALT FAST REACTOR

2021 ◽  
Vol 247 ◽  
pp. 01004
Author(s):  
Eduardo Cuoc ◽  
Eugene Shwageraus ◽  
Alisha Kasam ◽  
Ian Scott
Keyword(s):  
Molten Salt ◽  
Natural Uranium ◽  
Irradiation Damage ◽  
Molten Salt Reactor ◽  
Blanket Design ◽  
Breed And Burn ◽  
Fuel Salt ◽  
Uranium Blanket ◽  
Neutronic Performance ◽  
Fuel Tube

Previous designs of once-through solid-fuelled breed-and-burn (B&B) reactor and the conventional molten salt reactor (MSR) concepts suffer from material limitation of neutron irradiation damage and chemical corrosion. A novel breed-and-burn molten salt reactor (BBMSR) concept uses separate molten salt fuel and coolant in a linear assembly core configuration. Similar to Moltex Energy Stable Salt Reactor (SSR) design, the configuration with fuel salt contained in fuel tubes and coolant salt in pool type reactor vessel has been previously studied. The study confirmed that breed-and-burn operation is feasible in principle, however with a low neutronic margin. The objective of this paper was to seek improvements of the neutronic margin with a metallic natural uranium blanket design. A parametric study was performed for the natural uranium blanket design. BBMSR neutronic performance simulation was modelled using Serpent, a Monte Carlo reactor physics code, with a single 3D hexagonal channel containing a single fuel tube in an infinite lattice with reflective radial and vacuum axial boundary conditions. The addition of a metallic natural uranium blanket inside the fuel tube, which increases the natural uranium metal to fuel salt ratio (ϒ) of the BBMSR, was shown to significantly increase the neutronic performance of the BBMSR.

Molten salt self-cooled solid first wall and blanket design based on advanced ferritic steel

2004 ◽  
Vol 72 (1-3) ◽  
pp. 245-275 ◽  
Author(s):  
C.P.C. Wong ◽  
S. Malang ◽  
M. Sawan ◽  
I. Sviatoslavsky ◽  
E. Mogahed ◽  
...  
Keyword(s):  
Molten Salt ◽  
Ferritic Steel ◽  
First Wall ◽  
Blanket Design

Mission design options for human Mars missions

Mars ◽  
2007 ◽  
Author(s):  
Paul D Wooster ◽  
Robert D Braun ◽  
Jaemyung Ahn ◽  
Zachary R Putnam
Keyword(s):  
Mission Design ◽  
Design Options ◽  
Mars Missions
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