ARMP-02 documentation: Part 2, Chapter 7, MICBURN-E computer code manual: Volume 2, User's manual

Technical Report · Mon Dec 01 00:00:00 EST 1986

OSTI ID:7146073

Jones, D B

MICBURN-E is a multigroup pin cell lattice physics computer code designed for the burnup analysis of light water reactor fuel rods. It was specifically developed to handle fuel rods containing an initially homogeneous mixture of fuel (UO/sub 2/) and burnable absorber (Gd/sub 2/O/sub 3/) compositions. MICBURN-E features a fine mesh geometry model which makes it particularly suitable for the analysis of fuel rods which burn according to the phenomenon for ''onion-skin'' depletion effects. MICBURN-E employs integral transport theory based upon the method of collision probabilities to calculate neutron flux distributions and eigenvalues for cylindrical geometries. The primary application of MICBURN-E is to generate a burnable absorber data file containing effective microscopic absorption cross sections as a function of burnup for a pseudo nuclide. This file is then supplied as input to various assembly lattice physics codes including CPM-2, EPRI-CPM and CASM0-1. MICBURN-E is written entirely in FORTRAN and is supplied with a Nuclear Data Library which contains basic microscopic cross sections and burnup parameters for several nuclides.

• Research Organization: Levy (S.), Inc., Campbell, CA (USA); Electric Power Research Inst., Palo Alto, CA (USA)
• OSTI ID: 7146073
• Report Number(s): EPRI-NP-4574-CCM-Pt.2-Ch.7-Vol.2; ON: TI87920229
• Country of Publication: United States
• Language: English

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