The REBUS-MCNP linkage.

Stevens, J. G. ; Argonne National Laboratory. Nuclear Engineering Division.

Argonne National Laboratory

关键词: Research And Test Reactors;    Diffusion;    Fuel Cycle;    Neutron Flux;    Reactor Physics;   

DOI  :  10.2172/964248
RP-ID  :  ANL/RERTR/TM-08-04
RP-ID  :  DE-AC02-06CH11357
RP-ID  :  964248

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来源: UNT Digital Library

【 摘 要 】

The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup. REBUS-PC models the complete fuel cycle including shuffling capability. REBUS-PC evolved using the neutronic capabilities of multi-group diffusion theory code DIF3D 9.0, but was extended to apply the continuous energy Monte Carlo code MCNP for one-group fluxes and cross-sections. The linkage between REBUS-PC and MCNP has recently been modernized and extended, as described in this manual. REBUS-PC now calls MCNP via a system call so that the user can apply any valid MCNP executable. The interface between REBUS-PC and MCNP requires minimal changes to an existing MCNP model, and little additional input. The REBUS-MCNP interface can also be used in conjunction with DIF3D neutronics to update an MCNP model with fuel compositions predicted using a DIF3D based depletion.