High-speed radiation dose calculations for severe accidents using INDOS
- 1. Fauske ampersand Associates, Inc., Burr Ridge, IL (United States)
Description
The computer code INDOS (in-plant dose) has been developed for the high-speed calculation of in-plant radiation dose rates and doses during and/or due to a severe accident at a nuclear power plant. This paper describes the current capabilities of the code and presents the results of calculations for several severe-accident scenarios. The INDOS code can be run either as a module of MAAP, a code widely used in the nuclear industry for simulating the response of a light water reactor system during severe accidents, or as a stand-alone code using output from an alternative companion code. INDOS calculates gamma dose rates and doses in major plant compartments caused by airborne and deposited fission products released during an accident. The fission product concentrations are determined by the companion code
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 407-408.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24049879
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CALCULATION METHODS; DOSE RATES; FISSION PRODUCT RELEASE; GAMMA RADIATION; I CODES; M CODES; MICROCOMPUTERS; RADIATION DOSES; REACTOR ACCIDENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COMPUTERS; DIGITAL COMPUTERS; ELECTROMAGNETIC RADIATION; ENRICHED URANIUM REACTORS; IONIZING RADIATIONS; POWER REACTORS; RADIATIONS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-921102--.