Oyster Creek RETRAN model benchmark to pressure and level perturbation tests

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6890054

Alammar, M A

As part of GPU Nuclear's program to establish an in-house reload capability for Oyster Creek, the RETRAN-02 MOD4 SPL Computer Code has been chosen to analyze Chapter 15 Final Safety Analysis Report transients. To qualify Oyster Creek RETRAN model, a series of startup tests has been chosen to benchmark the model. Two of those tests, involved water level and vessel pressure perturbations at 100% power. Both tests were analyzed using point kinetics and one-dimensional kinetics with no noticeable impact on level or pressure. A small impact was noticed on power but was thought to be of minor significance. This is because for such mild transients the neutron flux shape function does not change appreciably throughout the transient.

• Research Organization: GPU Nuclear Corp., Parsippany, NJ
• OSTI ID: 6890054
• Report Number(s): CONF-861102-; TRN: 87-008124
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 53; Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
OYSTER CREEK-1 REACTOR
REACTOR SAFETY
TRANSIENTS
HEAT TRANSFER
HYDRAULICS
R CODES
BENCHMARKS
COMPUTER CODES
COMPUTERIZED SIMULATION
FEEDWATER
NEUTRON FLUX
ONE-DIMENSIONAL CALCULATIONS
PRESSURE VESSELS
REACTOR KINETICS
REACTOR START-UP
BWR TYPE REACTORS
CONTAINERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HYDROGEN COMPOUNDS
KINETICS
MECHANICS
OPERATION
OXYGEN COMPOUNDS
POWER REACTORS
RADIATION FLUX
REACTOR OPERATION
REACTORS
SAFETY
SIMULATION
START-UP
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled