A simplified approach for predicting radionuclide releases from light water reactor accidents

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6320884

Nourbakhsh, H P; Cazzoli, E G

This paper describes a personal computer-based program (GENSOR) that utilizes a simplified time-dependent approach for predicting the radionuclide releases during postulated reactor accidents. This interactive computer program allows the user to generate simplified source terms based on those severe accident attributes that most influence radionuclide release. The parameters entering this simplified model were derived from existing source term data. These data consists mostly of source term code package (STCP) calculations performed in support of Draft NUREG-1150. An illustrative application of the methodology is presented in this paper. 7 refs., 3 figs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6320884
• Report Number(s): BNL-NUREG-44449; CONF-910213-5; ON: DE90016314; TRN: 91-000637
• Resource Relation: Conference: Probabilistic safety assessment and management, Beverly Hills, CA (USA), 4-7 Feb 1991
• 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
PWR TYPE REACTORS
FISSION PRODUCT RELEASE
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONCRETES
CONTAINMENT
G CODES
PRESSURE EFFECTS
RADIOISOTOPES
REACTOR SAFETY
S CODES
SOURCE TERMS
ACCIDENTS
BUILDING MATERIALS
COMPUTER CODES
ISOTOPES
MATERIALS
REACTORS
SAFETY
SIMULATION
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