Uncertainties in modeling and scaling in the prediction of fuel stored energy and thermal response
The steady-state temperature distribution and the stored energy in nuclear fuel elements are computed by analytical methods and used to rank, in the order of importance, the effects on stored energy from statistical uncertainties in modeling parameters, in boundary and in operating conditions. An integral technique is used to calculate the transient fuel temperature and to estimate the uncertainties in predicting the fuel thermal response and the peak clad temperature during a large-break loss of coolant accident. The uncertainty analysis presented here is an important part of evaluating the applicability, the uncertainties and the scaling capabilities of computer codes for nuclear reactor safety analyses. The methods employed in this analysis merit general attention because of their simplicity. It is shown that the blowdown peak is dominated by fuel stored energy alone or, equivalently, by linear heating rate. Gap conductance, peaking factors and fuel thermal conductivity are the three most important fuel modeling parameters affecting peak clad temperature uncertainty. 26 refs., 10 figs., 6 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5535250
- Report Number(s):
- BNL-NUREG-40498; CONF-8710111-24; ON: DE88003484; TRN: 88-004845
- Resource Relation:
- Conference: 15. water reactor safety information meeting, Gaithersburg, MD, USA, 26 Oct 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Uncertainty analysis for a PWR loss-of-coolant accident. I. Blowdown phase employing the RELAP4/MOD6 computer code
Development of a RELAP5-3D Multidimensional Model of a VVER-1000 NPP for Analysis of a Large-Break Loss-of-Coolant Accident
Related Subjects
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
NUCLEAR POWER PLANTS
REACTOR SAFETY
FUEL CANS
FUEL ELEMENTS
TEMPERATURE DISTRIBUTION
THEORETICAL DATA
THERMAL CONDUCTIVITY
TRANSIENTS
ACCIDENTS
DATA
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUCLEAR FACILITIES
NUMERICAL DATA
PHYSICAL PROPERTIES
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
SAFETY
THERMAL POWER PLANTS
THERMODYNAMIC PROPERTIES
220900* - Nuclear Reactor Technology- Reactor Safety
220100 - Nuclear Reactor Technology- Theory & Calculation