A Hybrid Radiation Transport Detector Response Function Methodology for Modeling Contaminated Sites

In order to model the energy deposition response of a gamma-ray detector for a broad range of wide area contamination scenarios accurately and a timely manner, the proposed study seeks to develop a detector response function methodology by coupling the stochastic Monte Carlo radiation transpor method with the CADIS hybrid radiation transport method to significantly increa the computational efficiency of thousands of Monte Carlo pulse height simulatio The CADIS hybrid method, available through the newly-developed Monte Carlo code, Shift, coupled with the 3D adjoint transport solver Denovo, will be harness to develop high-fidelity detector response functions for a range of gamma-ray detectors for radionuclides of interest in the environmental assessment process. Capabilities and limitations of the radiation transport codes will be assessed for breadth of contaminated media scenarios, modeled gamma-ray detectors, and radionuclide photon energies. To demonstrate the rationale behind the propose methodology, an analysis study will be conducted to address the capabilities an limitations associated with pulse height tally variance reduction in the following: native MCNP, the CADIS hybrid method in Shift coupled with MCNP, the ADVAN code developed at Oak Ridge National Laboratory, the MCNP DXTRAN variance reduction technique, and the MCNP weight window generator. In addition, a method to determine the contribution of bremsstrahlung radiation from highly-attenuated beta-emitters in various environmental media will be incorporated into the detector response function methodology.

 Adjoint flux distribution for 2.5-3.0 MeV source photons for a 2×2-inch NaI(Tl) detector simulation defined for a 2.54 cm source-detector distance at x = -2.54 (soil contamination).