Analyzing the rod drop accident in a BWR with high burnup fuel. Revised

Conference · Sat Feb 01 00:00:00 EST 1997

OSTI ID:465206

Diamond, D J; Neymotin, L

The response of fuel in a boiling water reactor to the rod drop accident (RDA) was studied using the RAMONA-4B computer code. In this study, a fit of RAMONA-4B bundle powers was used to estimate the local power peaking. It was determined that the peaking factor could be 25% higher than the factor usually assumed for RDA analysis. Combining this error with the 2 sigma random error means that for this analysis the actual fuel rod enthalpy could be 100% larger than calculated by RAMONA-4B. This is much larger than the uncertainty in most parameters that are calculated with best-estimate methods for other design-basis events.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 465206
• Report Number(s): BNL-NUREG-63663-Rev.; CONF-970315-1-Rev.; ON: DE97004576; TRN: 97:010032
• Resource Relation: Conference: ANS international topical meeting on light water reactor fuel performance, Portland, OR (United States), 2-6 Mar 1997; Other Information: PBD: Feb 1997
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
DESIGN BASIS ACCIDENTS
ROD DROP ACCIDENTS
FUEL PELLETS
BURNUP
REACTOR SAFETY
REACTIVITY
ENTHALPY
R CODES
HEAT TRANSFER
REACTOR COOLING SYSTEMS
HYDRAULICS
CONTROL ELEMENTS
SENSITIVITY ANALYSIS
CONTROL ROD WORTHS