Monte Carlo analysis of TRX lattices with ENDF/B version 3 data

Conference · Sat Mar 01 04:00:00 EDT 1975

OSTI ID:4081356

Hardy, J Jr

Four TRX water-moderated lattices of slightly enriched uranium rods have been reanalyzed with consistent ENDF/B Version 3 data by means of the full-range Monte Carlo program RECAP. The following measured lattice parameters were studied: ratio of epithermal-to-thermal $sup 238$U capture, ratio of epithermal- to-thermal $sup 235$U fissions, ration of $sup 238$U captures to $sup 235$U fissions, ratio of $sup 238$U fissions to $sup 235$U fissions, and multiplication factor. In addition to the base calculations, some studies were done to find sensitivity of the TRX lattice parameters to selected variations of cross section data. Finally, additional experimental evidence is afforded by effective $sup 238$U capture integrals for isolated rods. Shielded capture integrals were calculated for $sup 238$U metal and oxide rods. These are compared with other measurements. (auth)

• Research Organization: Brookhaven National Lab., Upton, N.Y. (USA)
• NSA Number: NSA-33-016357
• OSTI ID: 4081356
• Report Number(s): BNL-NCS--50451
• Country of Publication: United States
• Language: English

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