학술논문

Verification and implications of the multiple pin treatment in the SASSYS-1 LMR systems analysis code
Document Type
Conference
Author
Source
Conference: International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994; Other Information: PBD: [1994]
Subject
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE LMFBR TYPE REACTORS
SYSTEMS ANALYSIS
HEAT TRANSFER
S CODES
HYDRAULICS
EBR-2 REACTOR
REACTOR KINETICS
FUEL PINS
TEMPERATURE MEASUREMENT
PRIMARY COOLANT CIRCUITS
TRANSIENTS
REACTOR SAFETY 220900
REACTOR SAFETY
POWER REACTORS, BREEDING
MATHEMATICS AND COMPUTERS
Language
English
Abstract
As part of a program to obtain realistic, as opposed to excessively conservative, analysis of reactor transients, a multiple pin treatment for the analysis of intra-subassembly thermal hydraulics has been included in the SASSYS-1 liquid metal reactor systems analysis code. This new treatment has made possible a whole new level of verification for the code. The code can now predict the steady-state and transient responses of individual thermocouples within instrumented subassemlies in a reactor, rather than just predicting average temperatures for a subassembly. Very good agreement has been achieved between code predictions and the experimental measurements of steady-state and transient temperatures and flow rates in the Shutdown Heat Removal Tests in the EBR-II Reactor. Detailed multiple pin calculations for blanket subassemblies in the EBR-II reactor demonstrate that the actual steady-state and transient peak temperatures in these subassemblies are significantly lower than those that would be calculated by simpler models.