Published 1991 | Version v1
Report

Assessment of RAMONA-3B methodology with FRIGG dynamic tests

  • 1. Brookhaven National Lab., Upton, NY (USA)

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%

Part of:
Proceedings of the International Workshop on Boiling Water Reactor Stability

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

Optional Information