Oyster Creek RETRAN model benchmark to pressure and level perturbation tests

Conference · Wed Jan 01 04:00:00 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-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
• Country of Publication: United States
• Language: English

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