Test prediction for the German PKL test K5A using RELAP4/MOD6. [PWR]
Conference
·
OSTI ID:6607052
RELAP4/MOD6 is a computer code developed specifically to predict the transient thermal-hydraulic behavior of a PWR and related experimental reactor systems during reflood phase of postulated LOCA conditions. A ''blind'' test prediction for the German PKL reflood Test K5A was conducted using RELAP4/MOD6. The results of the prediction were in good agreement with experimental data indicating that RELAP4/MOD6 is capable of predicting transient reflood phenomena in the 200 percent cold-leg break test configuration of the PKL reflood facility.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6607052
- Report Number(s):
- CONF-781022-12
- Country of Publication:
- United States
- Language:
- English
Similar Records
Test prediction for the German PKL Test K5A using RELAP4/MOD6
Prediction of KWU PKL experiments K5A and K7A using RELAP4/MOD6. [PWR]
Calculations of flow oscillations during reflood using RELAP4/MOD6. [BWR; PWR]
Journal Article
·
Fri Nov 30 23:00:00 EST 1979
· Nucl. Technol.; (United States)
·
OSTI ID:5713378
Prediction of KWU PKL experiments K5A and K7A using RELAP4/MOD6. [PWR]
Technical Report
·
Thu Jun 01 00:00:00 EDT 1978
·
OSTI ID:6354245
Calculations of flow oscillations during reflood using RELAP4/MOD6. [BWR; PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6872133
Related Subjects
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
LOSS OF COOLANT
MOCKUP
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS