EPRI--CURL dynamic analysis of loop type LMFBRs. Final report
A computer-aided simulation is developed to analyze the transient behavior of loop type liquid metal-cooled fast breeder reactor plants. A set of nuclear, heat transfer, sodium dynamics, steam/water thermodynamics and control models for the multi-loop plant is developed to simulate operational, incident and accident transients. The major important features of the model include: (1) a multi-loop simulation, consisting of a single loop and the remaining lumped loops; (2) a method to calculate the characteristic times for every differential equation, and apply the Runge--Kutta algorithm to variables with slow and moderate time responses as compared to the integration time step and evaulate the variables with fast responses from a prompt approximation to assure numerical stability and reduce the computation time; and (3) a pre-accident initialization method by forcing most variables into their prompt approximation. The analytical submodels of the EPRI--CURL Code simulates: (a) the dynamics of sodium flows in the primary and secondary systems governed by forced and natural circulation; (b) reactor heat transfer; (c) neutron kinetics, reactivity feedbacks, and reactor power control; (d) intermediate heat exchanger heat transfer; (e) sodium transport delays in the primary and secondary systems; (f) steam/water thermodynamics, normal feed water flow and auxiliary feed water flow control; and (g) turbine header, throttle, steam bypass and relief flow control. There is a total of 489 first order ordinary differential equations modelling the entire plant. The EPRI--CURL systems analysis computer code for loop-type liquid metal cooled fast breeder reactors is used to model the plant response of a typical LMFBR to several transient conditions.
- Research Organization:
- Cornell Univ., Ithaca, NY (United States)
- OSTI ID:
- 6142359
- Report Number(s):
- EPRI-NP-1001; TRN: 79-016969
- Country of Publication:
- United States
- Language:
- English
Similar Records
System modeling for transient analysis of loop-type liquid-metal-cooled fast breeder reactors. [CURL-L code]
EPRI-CURL-P systems modeling for a pool-type liquid metal fast breeder reactor. Final report
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
E CODES
LMFBR TYPE REACTORS
TRANSIENTS
MATHEMATICAL MODELS
HEAT TRANSFER
HYDRODYNAMICS
REACTOR ACCIDENTS
REACTOR KINETICS
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
KINETICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding