Conceptual Design and Neutronics Analyses of a Fusion Reactor Blanket Simulation Facility
- 1 November 1987
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 97 (3) , 175-189
- https://doi.org/10.13182/nse87-a23500
Abstract
A new conceptual design of a fusion reactor blanket simulation facility has been developed. This design follows the principles that have been successfully employed in the Purdue Fast Breeder Blanket Facility (FBBF), where experiments have resulted in the discovery of substantial deficiencies in neutronics predictions. With this design, discrepancies between calculation and experimental data can be nearly fully attributed to calculation methods because design deficiencies that could affect results are insignificant. The conceptual design of this FBBF analog, the Fusion Reactor Blanket Facility, is presented. Essential features are the cylindrical geometry and a distributed line source of 14-MeV neutrons with a cosine-shaped intensity distribution. The source design consists of a deuteron beam sweeping over an elongated titanium-tritide target. To predict the character of the neutron flux this source will produce, neutronics analyses were performed. Predictions for two- and one-dimensional calculati...Keywords
This publication has 21 references indexed in Scilit:
- Absolute Neutron Spectrum Measurements in a Lithium Fluoride Integral Assembly for Fusion Reactor Data AssessmentNuclear Science and Engineering, 1981
- Measurements and Calculations of Angular Flux Spectra Emitted from Lithium and Graphite Slabs with D-T Neutron SourceJournal of Nuclear Science and Technology, 1980
- Tritium Production in a Sphere of 6LiD Irradiated by 14-MeV NeutronsNuclear Science and Engineering, 1979
- Absolute Fission-Rate Distribution in Graphite-Reflected Lithium Oxide Blanket AssemblyJournal of Nuclear Science and Technology, 1979
- Tritium production measurement in a lithium metal sphere with new techniques in neutron source strength determinationNuclear Instruments and Methods, 1978
- Neutron Spectra and Tritium Production Measurements in a Lithium Sphere to Check Fusion Reactor Blanket CalculationsNuclear Science and Engineering, 1978
- Effect of Nonelastic Neutron Anisotropy on Fission Rates Measured in a Graphite-Reflected Lithium AssemblyJournal of Nuclear Science and Technology, 1977
- Absolute Fission-Rate Distributions in Lithium and Hybrid Fusion Blanket Assemblies, (II)Journal of Nuclear Science and Technology, 1977
- Absolute Fission-Rate Distributions in Lithium and Hybrid Fusion Blanket Assemblies, (I)Journal of Nuclear Science and Technology, 1977
- Experimental and Theoretical Investigations of Tritium Production in a Controlled Thermonuclear Reactor Blanket ModelNuclear Science and Engineering, 1976