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Station Blackout at Browns Ferry Unit One - accident sequence analysis. Volume 1

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TLDR
In this article, the authors describe the predicted response of Unit 1 at the Browns Ferry Nuclear Plant to Station Blackout, defined as a loss of offsite power combined with failure of all onsite emergency diesel-generators to start and load.
Abstract
This study describes the predicted response of Unit 1 at the Browns Ferry Nuclear Plant to Station Blackout, defined as a loss of offsite power combined with failure of all onsite emergency diesel-generators to start and load. Every effort has been made to employ the most realistic assumptions during the process of defining the sequence of events for this hypothetical accident. DC power is assumed to remain available from the unit batteries during the initial phase and the operator actions and corresponding events during this period are described using results provided by an analysis code developed specifically for this purpose. The Station Blackout is assumed to persist beyond the point of battery exhaustion and the events during this second phase of the accident in which dc power would be unavailable were determined through use of the MARCH code. Without dc power, cooling water could no longer be injected into the reactor vessel and the events of the second phase include core meltdown and subsequent containment failure. An estimate of the magnitude and timing of the concomitant release of the noble gas, cesium, and iodine-based fission products to the environment is provided in Volume 2 of this report. 58 refs., 75more » figs., 8 tabs.« less

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Citations
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Lessons Learned from the Fukushima Nuclear Accident for Improving Safety of U.S. Nuclear Plants

TL;DR: In this paper, the authors examined the causes of the crisis, the performance of safety systems at the plant, and the responses of its operators following the 2011 Japanese nuclear accident, and they made recommendations to improve plant systems, resources, and operator training.
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Insight from Fukushima Daiichi Unit 3 Investigations using MELCOR

TL;DR: During the emergency response period of the accidents that took place at the Fukushima Daiichi nuclear power plant (NPP) in March of 2011, researchers at Oak Ridge National Laboratory (ORNL) conduc...
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The Canary, the Ostrich, and the Black Swan: A Historical Perspective on our Understanding of BWR Severe Accidents and Their Mitigation

S.R. Greene
- 01 May 2014 - 
TL;DR: In this paper, Oak Ridge National Laboratory (ORNLNL) was engaged in an intense effort to understand commercial boiling water reactor severe accident phenomenology, severe accident phenology, and severe accident pr...
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The role of BWR secondary containments in severe accident mitigation: Issues and insights from recent analyses

TL;DR: In this paper, a brief overview of US BWR secondary containment designs and highlights plant-specific features that could influence secondary containment severe accident survivability and accident mitigation effectiveness are discussed and insights gained from recent secondary containment studies of Browns Ferry, Peach Bottom, and Shoreham are presented.
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BWR Station Blackout: A RISMC Analysis Using RAVEN and RELAP5-3D

TL;DR: The existing fleet of nuclear power plants is in the process of having its lifetime extended and having the power generated from these plants increased via power uprates and improved operations as mentioned in this paper. But the existing fleet is not suitable for nuclear power generation.
References
More filters
Book

Lessons Learned from the Fukushima Nuclear Accident for Improving Safety of U.S. Nuclear Plants

TL;DR: In this paper, the authors examined the causes of the crisis, the performance of safety systems at the plant, and the responses of its operators following the 2011 Japanese nuclear accident, and they made recommendations to improve plant systems, resources, and operator training.
Journal ArticleDOI

Insight from Fukushima Daiichi Unit 3 Investigations using MELCOR

TL;DR: During the emergency response period of the accidents that took place at the Fukushima Daiichi nuclear power plant (NPP) in March of 2011, researchers at Oak Ridge National Laboratory (ORNL) conduc...
Journal ArticleDOI

The Canary, the Ostrich, and the Black Swan: A Historical Perspective on our Understanding of BWR Severe Accidents and Their Mitigation

S.R. Greene
- 01 May 2014 - 
TL;DR: In this paper, Oak Ridge National Laboratory (ORNLNL) was engaged in an intense effort to understand commercial boiling water reactor severe accident phenomenology, severe accident phenology, and severe accident pr...
Journal ArticleDOI

The role of BWR secondary containments in severe accident mitigation: Issues and insights from recent analyses

TL;DR: In this paper, a brief overview of US BWR secondary containment designs and highlights plant-specific features that could influence secondary containment severe accident survivability and accident mitigation effectiveness are discussed and insights gained from recent secondary containment studies of Browns Ferry, Peach Bottom, and Shoreham are presented.
Journal ArticleDOI

BWR Station Blackout: A RISMC Analysis Using RAVEN and RELAP5-3D

TL;DR: The existing fleet of nuclear power plants is in the process of having its lifetime extended and having the power generated from these plants increased via power uprates and improved operations as mentioned in this paper. But the existing fleet is not suitable for nuclear power generation.