Enhancements to the MCNP6 background source
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
The particle transport code MCNP has been used to produce a background radiation data file on a worldwide grid that can easily be sampled as a source in the code. Location-dependent cosmic showers were modeled by Monte Carlo methods to produce the resulting neutron and photon background flux at 2054 locations around Earth. An improved galactic-cosmic-ray feature was used to model the source term as well as data from multiple sources to model the transport environment through atmosphere, soil, and seawater. A new elevation scaling feature was also added to the code to increase the accuracy of the cosmic neutron background for user locations with off-grid elevations. Furthermore, benchmarking has shown the neutron integral flux values to be within experimental error.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC52-06NA25396
- OSTI ID:
- 1235894
- Report Number(s):
- LA-UR-14-29240
- Journal Information:
- Nuclear Technology, Vol. 192, Issue 3; ISSN 0029-5450
- Publisher:
- American Nuclear Society (ANS)Copyright Statement
- Country of Publication:
- United States
- Language:
- English
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