Assessment of dose during an SGTR. [Steam Generator Tube Rupture (SGTR)]
The Nuclear Regulatory Commission requires utilities to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the iodine concentration in the reactor coolant system (RCS) due to iodine spikes, primary flashing and bypass fractions, and iodine partitioning in the secondary coolant system (SCS). Experimental and analytical investigations have recently been completed wherein these assumptions were tested to determine whether and to what degree they were conservative (that is, whether they result in a calculated iodine source term/dose that is at least as large or larger than that expected during an actual event). The current study has the objective to assess the overall effects of the results of these investigations on the calculated iodine dose to the environment during an SGTR. To assist in this study, a computer program, DOSE, was written. This program uses a simple, non-mechanistic model to calculate the iodine source term to the environment during an SGTR as a function of water mass inventories and flow rates and iodine concentrations in the RCS and SCS. The principal conclusion of this study is that the iodine concentration in the RCS is the dominant parameter, due to the dominance of primary flashing on the iodine source term.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6573180
- Report Number(s):
- EGG-NRE-10644; ON: DE93012180
- Country of Publication:
- United States
- Language:
- English
Similar Records
Iodine release during a steam generator tube rupture
Assessment of dose during an SGTR
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
COMPUTER CODES
COOLANTS
COOLING SYSTEMS
D CODES
DOSES
ELEMENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FLUID MECHANICS
HALOGENS
HEAT TRANSFER
HYDRAULICS
IODINE
ISOTOPES
MATERIALS
MATHEMATICAL MODELS
MECHANICS
NONMETALS
POWER REACTORS
PWR TYPE REACTORS
RADIATION DOSES
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
SAFETY ANALYSIS
STEAM GENERATORS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS