Comparisons of TORT and MCNP dose calculations for BNCT treatment planning

Conference · Tue Dec 31 00:00:00 EST 1996

OSTI ID:459310

Ingersol, D T; Slater, C O; Williams, L R ^[1]; Redmond, II, E L ^[2]; Zamenhof, R G ^[3]

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1. Oak Ridge National Lab., TN (United States)
2. Hholtec International, (United States)
3. New England Deaconess Hospital, Boston, MA (United States)

The relative merit of using a deterministic code to calculate dose distributions for BNCT applications were examined. The TORT discrete deterministic ordinated code was used in comparison to MCNP4A to calculate dose distributions for BNCT applications

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464; FG02-87ER60600
• OSTI ID: 459310
• Report Number(s): CONF-9609293-7; ON: DE97001035
• Resource Relation: Conference: 7. international symposium on neutron capture therapy for cancer, Zurich (Switzerland), 4-7 Sep 1996; Other Information: PBD: [1996]
• Country of Publication: United States
• Language: English

Related Subjects

55 BIOLOGY AND MEDICINE
BASIC STUDIES
NEUTRON DOSIMETRY
COMPUTER CALCULATIONS
NEUTRON CAPTURE THERAPY
GLIOMAS
BORON 10