RAMONA analysis of the Peach Bottom-2 turbine trip transients. Final report

Technical Report · Mon Jun 01 00:00:00 EDT 1981

OSTI ID:6213936

Moberg, L; Rasmussen, J; Sauar, T O; Oye, O

This report documents the RAMONA computer code analysis of three turbine trip tests performed at the Peach Bottom-2 BWR in 1977. Utilizing the point kinetics model and the one-dimensional and three-dimensional (3-D) neutron kinetics models, the RAMONA simulations present experimental data on severe pressurization transients in a BWR. Emphasis is placed on the systematic comparison between different core model approximations and on specific results from the 3-D simulation using the neutron kinetics model.

• Research Organization: Scandpower, Inc., Bethesda, MD (USA)
• OSTI ID: 6213936
• Report Number(s): EPRI-NP-1869; ON: DE81903560; TRN: 81-012139
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PEACH BOTTOM-2 REACTOR
STEAM TURBINES
TRANSIENTS
COMPUTER CALCULATIONS
HYDRAULICS
POWER DENSITY
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MACHINERY
MECHANICS
POWER REACTORS
REACTORS
SAFETY
TURBINES
TURBOMACHINERY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled