PIUS boron transport phenomena - A comparison of experiments with simulations

Conference · Mon Jan 01 00:00:00 EST 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5874189

Bredolt, U

In the process inherent ultimate safety (PIUS) reactor, the primary system is via thermal barriers in direct contact with a large pool of cold, highly borated water. In severe transients that would normally entail a risk of core damage, this borated water enters the primary system and shuts down the reactor, or reduces its power to a safe level and ensures cooling. The distribution of this inflowing borated water in the primary system is important for the transient behavior of the reactor. An example of such a transport phenomenon encountered in a PIUS reactor is an uncollected boron dilution transient, corresponding to inadvertent control rod withdrawal in a present-day pressurized water reactor. In this transient, a non-uniform boron distribution occurs in the primary system, and it is important to predict the boron distribution correctly in the primary system during the entire transient. A test loop of PIUS at ABB Atom's engineering laboratories was used to investigate large-scale boron transport phenomena. The test loop was used for comparing the standard solution methods in the RIGEL code with the improved model for tracking boron and entalphy front propagation. The test cases have demonstrated and verified the ability of the RIGEL code to predict boron transport phenomena with sufficient accuracy, using the improved transport delay model.

• OSTI ID: 5874189
• Report Number(s): CONF-901101-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 62; Conference: American Nuclear Society (ANS) winter meeting, Washington, DC (USA), 11-15 Nov 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

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