American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 7 / Number 1

Integral Transport Theory of Thermal Utilization Factor in Infinite Slab Geometry

Michel H. Theys

Nuclear Science and Engineering / Volume 7 / Number 1 / January 1960 / Pages 58-63

Technical Paper / dx.doi.org/10.13182/NSE60-A25697

Using transport theory in the cylindrical fuel region of a heterogenous reactor, Amouyal and Benoist have proposed new formulas to compute the disadvantage factors used in the determination of the thermal utilization factor. The same method when applied to an infinite slab geometry gives simple expressions for the fuel and moderator disadvantage factors.