Analysis of a water moderated critical assembly with anisn-Vitamin C

Green, L.

doi:10.2172/5923191

Cited by 1 publication

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“…The thicknesses of the various zones as shown in Fi~ure 5-3 were chosen •through a series of parametric ••runs for each configuration so that T at BOL was .rl.05..:i. 10. They do •not•, however, represent fully optimized results.…”

Section: Inner Blanket Composition Variationsmentioning

confidence: 98%

Blanket design study for a Commercial Tokamak Hybrid Reactor (CTHR)

Chapin¹,

Green²,

Lee³

et al. 1979

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In this report the results are presented of a study on two blanket design concepts for application in a Commercial Tokamak Hybrid Reactor (CTHR). Both blankets operate on the U-Pu cycle and are designed to achieve tritium self-sufficiency while maximizing the fissile fuel production within thermal and mechanical design constraints., The two blanket concepts that were evaluated were: 1) a UC fueled, stainless steel clad and structure, helium cooled blanket; and 2) a uo 2 fueled, zircaloy clad, stainless. steel structure, boiling water cooled blanket. Two different tritium breeding media, Li 2 0 and LiH, were evaluated for use in both blanket concepts. The use of lead as a neutron multiplier or reflector and graphite as a reflector was also considered for both blankets. 4-5 Neutron Transport Calculation Configuration for the Li 2 0, uo 2 Outer Fertile Blanket Only. 4-13 " 4-6 Neutron Transport Calculation Configuration for the LiH, uo 2 Full Fertile Blanket. 4-16 4-7 Spatial Distribution of the Tritium Production Rate in the U0 2-LiH Blanket ~Jith Constant 80% Quality Steam Coolant. 4-19 4-8 Neut.ran Transport Calculation Configuration for the LiH, uo 2 Full Fertile Blanket, Lead Reflectors. 4-20 4-9 Time Dependent Variation of the Tritium and Fissile Production Rates and the Fissile Enrichment for the U02-Li H Full Fertile Blanket with Constant 30% Quality Steam Coolant 4-24 Figure No.' 4-10 4-11 4-12 4-13 4-14 4-15 5-1 5-2 5-3 5-4• 5-5 LIST OF FIGURES (CONTINUED) Time Dependent Variation of the Thermal Power foi the U02-LiH and U0 2-Li20 Full Fertile Blankets With Constant 30% QuaTity Steam Coolant. Heating Rate Spatial Profiles in the uo 2-LiH Full Fertile Blanket With Constant 30% Quality Steam Coolant. Neutron Transport Calculation Configuration for the LiH, U02 Outer Fertile Blanket Only. Effect of Variations in the Fuel-to-Structure Volume Ratio on the Power and Fissile Fuel Production in the U02-• LiH Outer Fertile Blanket With Constant 80% Quality Steam Coolant. • Time Dependent Variation of the Fissile Fuel and Power Production for Two Different Water Coolant Densities in the uo 2-Li. 2 0 Full Blanket Concept. Time Dependent Variation of the Fissile Fuel and Power Production for Two Different Water Coolant Densities in the UO~-LiH Full Blanket Concept. • Schematic Diagram of the Zone Thicknesses and Material Compositions Used in the Neutronics Analysis of the UC-Li 2 0 Outer Blanket Coverag~ Concept. Effect of Variations in the Fuel-to-Structure Volume Ratio. on the lJC-Li 2 0 Outer Blanket Fissile Atom Production and Energy Multi pl i ca ti on... Simple Schematic Illustration of Three Inner Blanket Ar~angement Variations Considered for the CTHR.

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Section: Inner Blanket Composition Variationsmentioning

confidence: 98%