Perturbations of reactor flow and inlet temperature in EBR-II for reactivity feedback validation

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5986501

Mohr, D; Chang, L K

A loss-of-flow (LOF) accident in current LMFBR safety studies is a total loss of pumping power coupled with a failure of the reactor shutdown system (RSS). Another accident of current interest is a loss-of-heat sink for the primary system without involving the RSS. Both types of transients are included in the Shutdown Heat Removal Tests (SHRT) presently being conducted in the Experimental Breeder Reactor II (EBR-II). An initial series of tests in EBR-II was successfully completed in June of 1984 which included investigation of the inherent reactivity feedback characteristics. In these tests, the reactor was perturbed at various power levels by independent variations in primary flow and reactor inlet temperature, and the reactor power and temperature response were measured. The reactor and balance of plant are extensively instrumented and measurements were recorded on a data acquisition system. Results show that the plant responds safely without any external control and confirm that the effects of reduced primary flow or reduced heat rejection are mitigated. More specifically, the data provide a basis for model validation and confidence in predictions of an upcoming series of unprotected LOF and loss-of-heat sink tests. In this paper, the pretest predictions, measured results, and posttest analyses are described in detail. Finally, the application of this feedback model to future EBR-II core loadings and implications for other LMFBR's are discussed.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5986501
• Report Number(s): CONF-850410-9; ON: DE85002769
• Country of Publication: United States
• Language: English

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