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Filtering by: Subject Reactor fuel reprocessing Subject Fuel burnup (Nuclear engineering)

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Creator:

Abdul-hamid, Shahab A.

Abstract:

Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...

Resource Type:

Masters Thesis

Full Text:

is uniformly mixed in the fuel. MCNPBURN was benchmarked using a standard Pressurized Water Reactor
Design and analysis of a nuclear reactor core for innovative small light water reactors

Creator:

Soldatov, Alexey I.

Abstract:

In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...

Resource Type:

Dissertation

Full Text:

fuel assembly design………………… 45 3.2.2. MASLWR reactor vessel geometry……………………………….. 45 3.5.2. CASMO-4