The RADionuclide Transport, Removal, and Dose (RADTRAD) code

Conference · Thu Jul 01 00:00:00 EDT 1993

OSTI ID:10173689

Miller, L A ^[1]; Chanin, D I ^[2]; Lee, J ^[3]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)
3. Nuclear Regulatory Commission, Washington, DC (United States)

The RADionuclide Transport, Removal, And Dose (RADTRAD) code is designed for US Nuclear Regulatory Commission (USNRC) use to calculate the radiological consequences to the offsite population and to control room operators following a design-basis accident at Light Water Reactor (LWR) power plants. This code utilizes updated reactor accident source terms published in draft NUREG-1465, ``Accident Source Terms for Light-Water Nuclear Power Plants.`` The code will track the transport of radionuclides as they are released from the reactor pressure vessel, travel through the primary containment and other buildings, and are released to the environment. As the radioactive material is transported through the primary containment and other buildings, credit for several removal mechanisms may be taken including sprays, suppression pools, overlying pools, filters, and natural deposition. Simple models are available for these different removal mechanisms that use, as input, information about the conditions in the plant and predict either a removal coefficient ({lambda}) or decontamination factor. The user may elect to use these models or input a single value for a removal coefficient or decontamination factor.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 10173689
• Report Number(s): SAND-93-1485C; CONF-931160-10; ON: DE93017658; TRN: 93:019878
• Resource Relation: Conference: American Nuclear Society (ANS) winter meeting,San Francisco, CA (United States),14-18 Nov 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
61 RADIATION PROTECTION AND DOSIMETRY
54 ENVIRONMENTAL SCIENCES
RADIATION DOSES
R CODES
WATER COOLED REACTORS
DESIGN BASIS ACCIDENTS
RADIONUCLIDE MIGRATION
AIR
OCCUPATIONAL EXPOSURE
HUMAN POPULATIONS
RADIOACTIVE EFFLUENTS
PRESSURE VESSELS
CONTAINMENT BUILDINGS
220504
210100
210200
990200
560101
540130
DESIGN BASIS AND HYPOTHETICAL ACCIDENTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS
DOSIMETRY AND MONITORING
RADIOACTIVE MATERIALS MONITORING AND TRANSPORT