Probability and consequences of a rapid boron dilution sequence in a PWR

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The reactor restart scenario is one of several beyond-design-basis events in a pressurized water reactor (PWR) which can lead to rapid boron dilution in the core. This in turn can lead to a power excursion and the potential for fuel damage. A probabilistic analysis had been done for this event for a European PWR. The estimated core damage frequency was found to be high partially because of a high frequency for a LOOP and assumptions regarding operator actions. As a result, a program of analysis and experiment was initiated and corrective actions were taken. A system was installed so that ... continued below

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12 p.

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Diamond, D.J.; Kohut, P.; Nourbakhsh, H.; Valtonen, K. & Secker, P. November 1, 1995.

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Description

The reactor restart scenario is one of several beyond-design-basis events in a pressurized water reactor (PWR) which can lead to rapid boron dilution in the core. This in turn can lead to a power excursion and the potential for fuel damage. A probabilistic analysis had been done for this event for a European PWR. The estimated core damage frequency was found to be high partially because of a high frequency for a LOOP and assumptions regarding operator actions. As a result, a program of analysis and experiment was initiated and corrective actions were taken. A system was installed so that the suction of the charging pumps would switch to the highly borated refueling water storage tank (RWST) when there was a trip of the RCPs. This was felt to reduce the estimated core damage frequency to an acceptable level. In the US, this original study prompted the Nuclear Regulatory Commission to issue an information notice to follow work being done in this area and to initiate studies such as the work at BNL reported herein. In order to see if the core damage frequency might be as high in US plants, a probabilistic assessment of this scenario was done for three plants. Two important conservative assumptions in this analysis were that (1) the mixing of the injectant was insignificant and (2) fuel damage occurs when the slug passes through the core. In order to study the first assumption, analysis was carried out for two of the plants using a mixing model. The second assumption was studied by calculating the neutronic response of the core to a slug of deborated water for one of the plants. All three types of analyses are summarized below. More information is available in the original report.

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12 p.

Notes

INIS; OSTI as TI96002010

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  • OECD/Committee on Safety of Nuclear Installations (CSNI) specialist meeting on boron dilution reactivity transients, State College, PA (United States), 18-20 Oct 1995

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  • Other: TI96002010
  • Report No.: BNL-NUREG--61713
  • Report No.: CONF-9510225--2
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 117794
  • Archival Resource Key: ark:/67531/metadc626148

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  • November 1, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 8, 2016, 12:19 p.m.

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Diamond, D.J.; Kohut, P.; Nourbakhsh, H.; Valtonen, K. & Secker, P. Probability and consequences of a rapid boron dilution sequence in a PWR, article, November 1, 1995; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc626148/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.