The Three Mile Island Incident

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The Three Mile Island Incident

Joel Goncalves

Computer Science (Bsc)

Abstract        The Three Mile Island wrote its name in history after the accident in one of the generating station’s nuclear reactors.  The TMI-2 reactor suffered a partial core meltdown, leading to small quantities of radioactivity releases.  The results of this incident were mainly political, and no injuries or deaths were reported.

1.  The nuclear power generating station: introduction

Three Mile Island is an island in the Susquehanna River in Dauphin County, Pennsylvania, near Harrisburg.  The nuclear station had two pressurized water reactors: Unit 1 of 800 MWe, activated in 1974, remains one of the best-performing units in the USA; Unit 2, of 900 MWe, was almost brand new and its reactor was operating at 97% power just before the accident began.  The following image presents us with the schematics of the TMI-2 nuclear reactor, for a better understanding of the description of the accident.

Figure 1: Schematics of the TMI-2 Reactor

Figure reprinted from the U.S. Nuclear Regulatory Commission’s document on the accident:

http://www.nrc.gov/reading-rm/doc-collections/fact-sheets/tmi-2.gif

2.  The accident: summary of events

At 4.00 a.m. on the 28th of March 1979 there was a failure in the secondary non-nuclear cooling system.  The plant’s main feedwater pumps stopped running, preventing the steam generators from removing heat. The cause of this failure was believed to be either mechanical or electrical.  The nuclear reactor automatically shut down just after the turbine did.  The pressure in the primary nuclear system of the plant increased straightway, and the pressuriser relief valve opened.  This would prevent the pressure from becoming excessive, and when the amount of pressure decreased, the valve would close.  This did not happen because the signals available to the operator failed to show that the valve was still open, causing the pressure to continue decreasing in the system, pouring out cooling water.  As a result the core of the reactor overheated.

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Coolant flowed down from the core to the pressuriser, making the instruments return confusing information to the reactor operators.  Because there was no instrument showing the amount of coolant in the core, the operators determined the level of water by the amount of water shown in the pressuriser.  As the level indicated was high enough, they assumed that the core was covered with coolant and stopped adding water. They were unaware that, because of the stuck valve, the indicator was providing misleading readings.

Warning lights started to flash and alarms rang, as the operators failed to realise that ...

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