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== Overview == A boiling water reactor uses [[demineralized water]] as a coolant and [[neutron moderator]]. Heat is produced by nuclear fission in the reactor core, and this causes the cooling water to boil, producing steam. The steam is directly used to drive a [[turbine]], after which it is cooled in a [[Condenser (heat transfer)|condenser]] and converted back to liquid water. This water is then returned to the reactor core, completing the loop. The cooling water is maintained at about 75 [[Atmosphere (unit)|atm]] (7.6 [[Pascal (unit)|MPa]], 1000–1100 [[Pounds per square inch|psi]]) so that it boils in the core at about 285 °C (550 °F). In comparison, there is no significant boiling allowed in a [[pressurized water reactor]] (PWR) because of the high pressure maintained in its primary loop—approximately 158 atm (16 MPa, 2300 psi). The [[core damage frequency]] of the reactor was estimated to be between 10<sup>−4</sup> and 10<sup>−7</sup> (i.e., one core damage accident per every 10,000 to 10,000,000 reactor years).<ref name=":0">{{cite web|author1=Susan Dingman|author2=Jeff LaChance|author3=Allen Canip|author4=Mary Drouin|url=http://www.osti.gov/scitech/servlets/purl/205567 |title=Core damage frequency perspectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results|date=31 December 1995|publisher=Osti.gov |access-date=2013-08-02}}</ref>
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