Neutron Activation Self-Shielding Factors for Common Dosimetry Foils in an ACRR Equivalent Environment
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
The results of a computational analysis of self-shielding factors are presented. The analysis highlights the total self-shielding, which is a combination of energy and spatial self-shielding, associated with different neutron detection materials. The Monte Carlo N-Particle (MCNP) transport code was used in conjunction with the Evaluated Nuclear Data File (ENDF) and the International Reactor Dosimetry and Fusion Files (IRDFF). This analysis was done with neutron activation analysis in mind, and therefore is modeled and presented in a similar fashion.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC04-94AL85000; NA0003525
- OSTI ID:
- 1762959
- Report Number(s):
- SAND-2019-9540; 678498; TRN: US2215024
- Country of Publication:
- United States
- Language:
- English
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