2000
DOI: 10.1016/s0969-8043(00)00231-1
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Present and future capabilities of MCNP

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Cited by 27 publications
(12 citation statements)
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“…This approach allows appropriate contributions to each segment after the normal completion of the substep. 24,25 Boundary-crossing artifacts could potentially be larger if a finer scoring mesh with true surfaces is used. Hence, we recommend using MCNPX with the mesh tally for future work to calculate the 3D dose distribution around beta sources.…”
Section: Resultsmentioning
confidence: 99%
“…This approach allows appropriate contributions to each segment after the normal completion of the substep. 24,25 Boundary-crossing artifacts could potentially be larger if a finer scoring mesh with true surfaces is used. Hence, we recommend using MCNPX with the mesh tally for future work to calculate the 3D dose distribution around beta sources.…”
Section: Resultsmentioning
confidence: 99%
“…It was later updated to include the ITS 3 use of the newer stopping powers and bremsstrahlung cross sections, becoming MCNP4B (Briesmeister, 1997). The current version is MCNP4C (Briesmeister, 2000;Hendricks et al, 2000). MCNP does include the relevant sampling for an emitting volume.…”
Section: Mcnpmentioning
confidence: 99%
“…Among the SMC codes used to simulate the interaction of radiation with matter, EGS [17], MCNP [18] and, more recently, PENELOPE [19] and GEANT [20] have been applied to radiology. The quality of the results provided by different simulation codes is directly linked with the accuracy of the transport model and implemented by libraries that contain the data associated with the cross section of particles transported [4].…”
Section: Penelope Simulation Codementioning
confidence: 99%