| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 297008 | Nuclear Engineering and Design | 2012 | 12 Pages |
Prototype fast breeder reactor (PFBR) is a 500 MWe (1250 MWt) liquid sodium cooled pool type reactor currently under construction in India. For a safe and efficient operation of the plant, it is necessary that the reactor is protected from all the transients that may occur in the plant. In order to accomplish this, adequate number of SCRAM parameters is required in the plant protection system with reliable instrumentation. For identifying the SCRAM parameters, the neutronic and thermal hydraulic responses of the plant for various possible events need to be established. Towards this, a one dimensional plant dynamics code DYANA-P has been developed with thermal hydraulic models for reactor core, hot and cold pools, intermediate heat exchangers, pipelines, steam generator, primary sodium circuits and secondary sodium circuits. The code also incorporates neutron kinetics and reactivity feedback models. By a comprehensive plant dynamics study an optimum list of SCRAM parameters and the maximum permissible response time for various instruments used for deriving them have been arrived at.
► Analysis of various design basis events in a fast breeder reactor towards design of plant protection system. ► Plant dynamic modeling of a sodium cooled fast breeder reactor. ► Selection of optimum set of plant parameters for considering best plant availability.
