학술논문

Measurements and computation of the reactivity effects of accident-caused core distortions in liquid-metal fast breeder reactors
Document Type
Journal Article
Author
Source
Nucl. Sci. Eng.; (United States); 87:3
Subject
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS LMFBR TYPE REACTORS
REACTOR CORE DISRUPTION
COMPUTERIZED SIMULATION
SNEAK REACTOR
COMPACTING
DIFFUSION
EIGENVALUES
MEASURING METHODS
PERTURBATION THEORY
S CODES
TWO-DIMENSIONAL CALCULATIONS
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
COMPUTER CODES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
ZERO POWER REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety
210500 -- Power Reactors, Breeding
220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
Language
English
Abstract
The reactivity effects of material rearrangements, simulating conditions in a postulated liquid-metal fast breeder reactor accident, were measured in SNEAK-12A, a single-zone uranium fueled critical assembly, and calculated using current Kernforschungszentrum Karlsruhe methods and data and, in part, also using the corresponding modules of the SIMMER-II accident analysis system. For all cases investigated, satisfactory agreement between theory and experiment was reached when two-dimensional transport eigenvalue calculations were used. The application of first-order perturbation theory or diffusion theory in a number of cases led to larger discrepancies, particularly when the experiments involved fuel compaction.