The efficient calculation of chemical interactions in the primary circuit of LWR's (light water reactors) during severe accidents

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:6968357

Wheatley, C J

Interactions between fission products, structural, control rod and clad materials, steam, fuel and neutron poisons can give rise to hundreds of different chemical species in the primary circuit of an LWR during the course of a severe accident. Such interactions affect fission product transport within the primary circuit in a variety of important ways. Consequently, they must be treated if fission product release in particular is to be at all realistically predicted. We will first summarize a model for treating these interactions and state the form of the equations that govern the chemical reactions in the model. We discuss the difficulties with solving the equations using standard methods in the context of our application and devote the body of the paper to a description of an efficient method we have developed for their solution. We show that the equations can be recast into nearly linear form through the identification of a complete set of dominant independent species. We will describe our solution method based on this and give illustrative results which show it to be computationally efficient and reliable.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6968357
• Report Number(s): SAND-88-1596C; CONF-8806143-3; ON: DE88013023
• Resource Relation: Conference: 2. nuclear reactor severe accident chemistry symposium, Toronto, Canada, 5 Jun 1988; Other Information: Portions of this document are illegible in microfiche products
• 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
REACTOR ACCIDENTS
FISSION PRODUCTS
CHEMICAL REACTIONS
PWR TYPE REACTORS
AEROSOLS
FUEL CANS
HEAT TRANSFER
HYDRAULICS
M CODES
PRIMARY COOLANT CIRCUITS
RADIOACTIVE EFFLUENTS
RADIOACTIVITY TRANSPORT
REACTOR SAFETY
SOURCE TERMS
V CODES
ACCIDENTS
COLLOIDS
COMPUTER CODES
COOLING SYSTEMS
DISPERSIONS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
ISOTOPES
MATERIALS
MECHANICS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SOLS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
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