RADTRAN 6 Technical Manual
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 1323552
- Report Number(s):
- SAND2014--0780; 503388
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
61 RADIATION PROTECTION AND DOSIMETRY
97 MATHEMATICS AND COMPUTING
CALCULATION METHODS
ENVIRONMENTAL EXPOSURE PATHWAY
HAZARDS
MANUALS
MATHEMATICAL MODELS
MOTOR VEHICLE ACCIDENTS
NUMERICAL SOLUTION
PACKAGING
PROBABILITY
R CODES
RADIATION DOSES
RADIOACTIVE MATERIALS
RISK ASSESSMENT
TRANSPORT
61 RADIATION PROTECTION AND DOSIMETRY
97 MATHEMATICS AND COMPUTING
CALCULATION METHODS
ENVIRONMENTAL EXPOSURE PATHWAY
HAZARDS
MANUALS
MATHEMATICAL MODELS
MOTOR VEHICLE ACCIDENTS
NUMERICAL SOLUTION
PACKAGING
PROBABILITY
R CODES
RADIATION DOSES
RADIOACTIVE MATERIALS
RISK ASSESSMENT
TRANSPORT