The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied for variations in: fuel volume fraction in the core from 0.2 to 0.6; fertile material volume fraction in the blanket from 0.2 to 0.6; blanket thickness 3 in. to 24 in.; fuel materials of UC, U metal, UC/ sub 2/, PuC-- UC, Pu-- U metal, and PuO/sub 2/-...
The core of a subcritical, low-power research reactor in a lead matrix has been designed using the M...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.Includes ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...
In order to improve a new design for a uranium startup sodium cooled fast reactor which was proposed...
Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an ...
An optimization of an Ultra-long Cycle Fast Reactor (UCFR) design with a power rating of 1000 MW (el...
Traditional designs of sodium cooled fast reactors have a positive sodium expansion feedback. During...
The purpose of this study was to demonstrate the neutronic feasibility and competitive fuel cycle ec...
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions fr...
This paper presents a new design for a small modular sodium-cooled fast reactor core with an optimiz...
The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly foc...
AbstractMixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fa...
The primary objective of this study was to develop fuel cycle options that minimize the nuclear wast...
Physics scoping studies of a 300-Mw(e) PuO/sub 2/-UO/sub 2/-fueled fast- breeder reactor are reporte...
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, ...
The core of a subcritical, low-power research reactor in a lead matrix has been designed using the M...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.Includes ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...
In order to improve a new design for a uranium startup sodium cooled fast reactor which was proposed...
Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an ...
An optimization of an Ultra-long Cycle Fast Reactor (UCFR) design with a power rating of 1000 MW (el...
Traditional designs of sodium cooled fast reactors have a positive sodium expansion feedback. During...
The purpose of this study was to demonstrate the neutronic feasibility and competitive fuel cycle ec...
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions fr...
This paper presents a new design for a small modular sodium-cooled fast reactor core with an optimiz...
The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly foc...
AbstractMixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fa...
The primary objective of this study was to develop fuel cycle options that minimize the nuclear wast...
Physics scoping studies of a 300-Mw(e) PuO/sub 2/-UO/sub 2/-fueled fast- breeder reactor are reporte...
A core parameter study of the operating costs was performed for a 300- Mwe sodium graphite reactor, ...
The core of a subcritical, low-power research reactor in a lead matrix has been designed using the M...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.Includes ...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...