Published 1992 | Version v1
Journal article

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).

Optional Information

Secondary number(s)
CONF-921102--.