Transport and retention of radioiodine on the secondary side of U-tube steam generator during tube rupture event

Conference · Mon Jan 01 04:00:00 EST 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5875840

Ghiaasiaan, S M; Wassel, A T; Kalra, S P

Corrosion and mechanically induced damage can result in rupture of the pressurized water reactor steam generator tubes. Such a rupture will result in the leakage of the radioactive primary-side fluid to the secondary-side of a steam generator. A fraction of the leaked primary-side radioactive species will be retained in the secondary side, and the rest will be released in the form of vapor and entrained aerosols. The STARRS (secondary-side transport and retention of radioactive species) computer code was developed to simulate the transport and retention of aerosols and gaseous fission products on the secondary side of a U-tube steam generator during a steam generator tube rupture (SGTR) transient and to quantify the activity dose associated with the release. This paper provides an overview of the modeling approach and validation and application results. Validation calculations used the data generated at the Model Boiler No. 2 (MB-2) test facility. Plant calculations measured the release of radioiodine and the resulting thyroid dose for SGTR transients involving high and low secondary-side water levels.

• OSTI ID: 5875840
• Report Number(s): CONF-901101--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTIVITY LEVELS
AEROSOLS
BOILERS
BUBBLES
CHEMICAL REACTIONS
COLLOIDS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
CORROSION
DEPOSITION
DISPERSIONS
DOSES
ENERGY SYSTEMS
FAILURES
FISSION PRODUCT RELEASE
FISSION PRODUCTS
IODINE ISOTOPES
ISOTOPES
LEAKS
MATERIALS
MATHEMATICAL MODELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIATION DOSES
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RUPTURES
S CODES
SECONDARY COOLANT CIRCUITS
SEPARATION EQUIPMENT
SIMULATION
SOLS
STEAM GENERATORS
STEAM SEPARATORS
TESTING
TRANSIENTS
TUBES
VALIDATION
VAPOR GENERATORS
VAPOR SEPARATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS