Scaling criteria for modeling natural- and forced-convection loops. [PWR]
Nuclear reactor safety regulations have required extensive thermal-hydraulic testing of simulated reactor systems and components. In view of the inherent difficulties associated with full-scale testing, scale models for prototype systems have been extensively used to predict the behavior of nuclear reactor systems during normal and abnormal operations as well as under accident conditions. Several studies have been performed to establish similarity relations between a prototype and scale model. It is the purpose of the present study to develop scaling criteria for a forced and natural circulation loop under single- and/or two-phase flow conditions, and to apply the criteria to obtain the preliminary conceptual design parameters for the B and W 2 x 4 loop system. The 2 x 4 loop scaled system contains representative components of all thermal-hydraulic systems considered important in performing tests to obtain data representative of the response of the prototype plant.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5867006
- Report Number(s):
- CONF-831047-15; ON: DE83014747
- Resource Relation:
- Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
- Country of Publication:
- United States
- Language:
- English
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Scaling criteria for two-phase flow natural- and forced-convection loop and their application to conceptual 2 x 4 simulation-loop design. [PWR]
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRIMARY COOLANT CIRCUITS
MOCKUP
SCALE MODELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
HEAT TRANSFER
HYDRAULICS
ACCURACY
FORCED CONVECTION
NATURAL CONVECTION
REACTOR SAFETY
TEST FACILITIES
ACCIDENTS
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
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STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
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