Natural circulation experiments with a VVER reactor geometry

Stephen Lomperski, Jyrki Kouhia

Research output: Contribution to journalArticleScientificpeer-review

9 Citations (Scopus)

Abstract

Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-scale integral test loop patterned after Soviet-designed VVER pressurized water reactors. Using stepwise inventory reduction and small-break experiments, primary loop flow behaviour was studied over a range of coolant inventories. The tests revealed a trend toward decreasing primary side mass flow rate with inventory. In the small-break experiments, flow stagnation and system repressurization were observed when the water level in the upper plenum fell below the entrances to the hot legs and coolant flow into the hot legs changed from single to two-phase flow. The cause of this flow interruption was attributed to the hot leg loop seals, which are a unique feature of the VVER geometry. Finally, an experiment was conducted to demonstrate how loop seal refilling behaviour at low coolant inventories depends upon the steam flow rate through an individual hot leg. It was shown that loop seal refilling results when low steam velocities permit countercurrent flow in the upflow side of the loop seal.
Original languageEnglish
Pages (from-to)409-424
Number of pages16
JournalNuclear Engineering and Design
Volume147
Issue number3
DOIs
Publication statusPublished - 1994
MoE publication typeA1 Journal article-refereed

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Seals
reactors
Coolants
geometry
Geometry
Steam
coolants
refilling
experiment
Experiments
Flow rate
Pressurized water reactors
Water levels
stagnation flow
steam flow
Two phase flow
pressurized water reactors
mass flow rate
countercurrent
interruption

Cite this

Lomperski, Stephen ; Kouhia, Jyrki. / Natural circulation experiments with a VVER reactor geometry. In: Nuclear Engineering and Design. 1994 ; Vol. 147, No. 3. pp. 409-424.
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Natural circulation experiments with a VVER reactor geometry. / Lomperski, Stephen; Kouhia, Jyrki.

In: Nuclear Engineering and Design, Vol. 147, No. 3, 1994, p. 409-424.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Natural circulation experiments with a VVER reactor geometry

AU - Lomperski, Stephen

AU - Kouhia, Jyrki

PY - 1994

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AB - Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-scale integral test loop patterned after Soviet-designed VVER pressurized water reactors. Using stepwise inventory reduction and small-break experiments, primary loop flow behaviour was studied over a range of coolant inventories. The tests revealed a trend toward decreasing primary side mass flow rate with inventory. In the small-break experiments, flow stagnation and system repressurization were observed when the water level in the upper plenum fell below the entrances to the hot legs and coolant flow into the hot legs changed from single to two-phase flow. The cause of this flow interruption was attributed to the hot leg loop seals, which are a unique feature of the VVER geometry. Finally, an experiment was conducted to demonstrate how loop seal refilling behaviour at low coolant inventories depends upon the steam flow rate through an individual hot leg. It was shown that loop seal refilling results when low steam velocities permit countercurrent flow in the upflow side of the loop seal.

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