Reactor-transient tests at ANO-2. Final report
Technical Report
·
OSTI ID:6756888
This report documents experimental data generated from a series of reactor transient tests performed at Arkansas Nuclear One - Unit 2 (ANO-2) during December 1979 and January 1980. Four tests were conducted: complete loss of forced primary coolant flow, full-length control element assembly (CEA) drop, part-length CEA drop and turbine trip. These tests are part of a program to obtain plant transient test data which will be used for simulation code qualification. Two companion reports, ANO-2 Design and Cycle One Operating History Data and NSSS Transient Tests at ANO-2, provide plant design data and NSSS test data which may be used in conjunction with this report.
- Research Organization:
- Combustion Engineering, Inc., Windsor, CT (USA). Power Systems Group
- OSTI ID:
- 6756888
- Report Number(s):
- EPRI-NP-1709; ON: DE83900534
- Resource Relation:
- Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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· Nucl. Technol.; (United States)
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF FLOW
HEAT TRANSFER
HYDRAULICS
REACTOR KINETICS
PWR TYPE REACTORS
ROD DROP ACCIDENTS
NEUTRON FLUX
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
KINETICS
MECHANICS
RADIATION FLUX
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF FLOW
HEAT TRANSFER
HYDRAULICS
REACTOR KINETICS
PWR TYPE REACTORS
ROD DROP ACCIDENTS
NEUTRON FLUX
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
KINETICS
MECHANICS
RADIATION FLUX
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled