MCNPX vs. DORT for sns shielding design studies

Irina I. Popova

doi:10.1093/rpd/nci217

MCNPX vs. DORT for sns shielding design studies

Irina I. Popova

Research output: Contribution to journal › Article › peer-review

3 Scopus citations

Abstract

Radiation transport occurs through the 18 m long access way adjacent to the Spallation Neutron Source accelerator tunnel and the 2.2 m thick massive shielding door which closes the access way. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for construction of the door to study radiation penetration. A comparison was carried out using both Monte Carlo (code MCNPX) and discrete ordinates (code DORT) methods. The beam losses during the accelerator operation are the sources for the radiation calculations. Analyses show that the results from the two methods are in good agreement.

Original language	English
Pages (from-to)	559-563
Number of pages	5
Journal	Radiation Protection Dosimetry
Volume	115
Issue number	1-4
DOIs	https://doi.org/10.1093/rpd/nci217
State	Published - Dec 2005
Externally published	Yes

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10.1093/rpd/nci217

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abstract = "Radiation transport occurs through the 18 m long access way adjacent to the Spallation Neutron Source accelerator tunnel and the 2.2 m thick massive shielding door which closes the access way. A variety of typical materials for accelerator shielding, such as concrete and steel, were used for construction of the door to study radiation penetration. A comparison was carried out using both Monte Carlo (code MCNPX) and discrete ordinates (code DORT) methods. The beam losses during the accelerator operation are the sources for the radiation calculations. Analyses show that the results from the two methods are in good agreement.",

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MCNPX vs. DORT for sns shielding design studies

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