Fission product transport analysis. Quarterly progress report, January 1--March 31, 1978. [PWR; BWR; primary system reflooding following LOCA]

Technical Report · Thu Feb 01 00:00:00 EST 1979

DOI:https://doi.org/10.2172/6407274· OSTI ID:6407274

Gieseke, J A; Baybutt, P; Jordan, H; Jung, R G

Technical efforts during the reporting period were concerned primarily with developing the TRAP-MELT code by addition of specific mechanisms describing particle transport and deposition, and by continuing the preparation of thermal-hydraulic data for use with the code. Particle deposition mechanisms added to the TRAP-MELT code include deposition by thermophoresis and by diffusion and inertia from laminar and turbulent steam flows. Efforts concerned with describing thermal-hydraulic conditions have led to specification of data for a specific assumed accident sequence, AB with a cold-leg break, that will be used as the reference case during completion of the code development efforts.

• Research Organization: Battelle Columbus Labs., OH (United States)
• OSTI ID: 6407274
• Report Number(s): NUREG/CR-0697; BMI-2022
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
MELTDOWN
PRIMARY COOLANT CIRCUITS
FISSION PRODUCT RELEASE
MATHEMATICAL MODELS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
CORE FLOODING SYSTEMS
DEPOSITION
FISSION PRODUCTS
LOSS OF COOLANT
RADIOACTIVITY TRANSPORT
T CODES
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ECCS
ENGINEERED SAFETY SYSTEMS
ISOTOPES
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled