Evaluation of the loss of residual heat removal systems in pressurized water reactors

Ward, L.W.; Arcieri, W.C.

doi:10.2172/10134124

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“…Reference [7] identified a fast reactivity accident scenario that may occur during de-boration. Reference [8] evaluated the scenario for three PWRs and took into consideration a number of deterministic issues, such as reactivity effects and mixing of the injected unborated water with the reactor coolant. It was found that the mixing issue cannot be easily resolved and depends on the geometry of the connection between the injection line and the cold leg.…”

Section: French Scenariomentioning

confidence: 99%

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Musicki¹

1995

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Section: French Scenariomentioning

confidence: 99%

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Musicki¹

1995

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Void Fraction in a Four by Four Rod Bundle under a Stagnant Condition

Kamei

Hosokawa

Tomiyama

et al. 2010

JPES

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In the case of a hypothetical failure of a residual heat removal (RHR) systems under mid-loop operation, vapor generated in a reactor core forms two-phase flow in a stagnant liquid and rises the water level in the core. The vapor flows into a steam generator through a hot leg, and condenses in the steam generator. Since the flow rate of vapor from the reactor core to the hot leg depends on the water level and the void fraction α in the reactor core, the reliable analysis of the RHR failure cannot be carried out without accurately estimating the void fraction in the reactor core. Although a number of studies on void fractions in two-phase flows in rod bundles have been carried out, there are few experimental data on void fractions in rod bundles under the stagnant condition. Void fractions in four by four rod bundles under the stagnant condition were measured for a wide range of gas volume fluxes to examine the validity of available void correlations. Flow patterns were visualized by using a high-speed video camera to examine the effects of flow pattern on the void fraction. As a result, the following conclusions were obtained: (1) Dependence of the void fraction on the gas volume flux J G changed at J G 1.5 m/s due to the flow pattern transition. (2) Murase's correlation agreed well with the void fraction in the two kinds of rod bundles having different dimensions under the stagnant condition.

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Evaluation of the loss of residual heat removal systems in pressurized water reactors

Cited by 2 publications

References 0 publications

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Void Fraction in a Four by Four Rod Bundle under a Stagnant Condition

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