Assessment of RAMONA-3B methodology with FRIGG dynamic tests
Description
The computer codes used at Brookhaven National Laboratory to compute BWR safety parameters are the Engineering Plant Analyzer (EPA) and RAMONA-3B/MOD1. Both codes have the same methodology for modeling thermal hydraulic phenomena: drift-flux formulation, two-phase multipliers for the wall friction and form losses calculations, and the momentum integral approach for spatial integration of the loop momentum equations. Both codes use explicit integration methods for solving ordinary differential equations. It is concluded that both the codes are capable of modelling the instability problems for a BWR. The accuracy of thermohydraulics code predictions was assessed by modelling oscillatory FRIGG tests. Nodalizations studies showed that 24 axial nodes were sufficient for a converged solution, 12 axial nodes produced an error of 4.4% in the gain of the power to flow transfer function. The code predicted consistently the effects of power and inlet subcooling on gain and system resonance frequency. The comparisons showed that the code predicted the peak gains with a mean difference from experiments of 7% ± 30% for all the tests modeled. The uncertainty in the experimental data is -11% to + 12%. The mean difference in the predicted frequency at the peak gain is -6% ± 14%
Additional details
Publishing Information
- Imprint Title
- Proceedings of the International Workshop on Boiling Water Reactor Stability
- Imprint Pagination
- 548 p.
- Journal Page Range
- p. 412-432.
- Report number
- CSNI-R--178
Conference
- Title
- International Workshop on Boiling Water Reactor Stability.
- Dates
- 17-19 Oct 1990.
- Place
- Brookhaven, NY (USA).
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 22063740
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FLOW RATE; FLUID FLOW; OSCILLATIONS; R CODES; REACTOR STABILITY; TEST FACILITIES; VERIFICATION
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; STABILITY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS