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This document is an examination for NRC operator licensing, focusing on the fundamentals of pressurized water reactor operation, including questions on reactor theory, thermodynamics, and plant systems.
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Who needs Pressurized Water Reactor Generic Fundamentals Examination?

01
Individuals seeking to obtain a license or certification to operate a pressurized water reactor.
02
Nuclear power plant personnel involved in safety, operations, or regulatory compliance.
03
Engineers and technicians working in the nuclear industry.
04
Students and professionals pursuing careers in nuclear engineering or related fields.
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In BWRs (boiling water reactors) and PWRs (pressurized water reactors), collectively known as LWRs (light water reactors), the light water (H2O) coolant is also the moderator. PHWRs (pressurized heavy water reactors) use heavy water (deuterium oxide, D2O) as moderator.
In a PWR, water is used both as a neutron moderator and as coolant fluid for the reactor core. In the core, water is heated by the energy released by the fission of atoms contained in the fuel. Using high pressure (around 155 bar) ensures that the water stays in a liquid state.
Since the pressurizer is connected to the reactor coolant system via the surge line, the water will expand up into the pressurizer. This will cause the steam in the top of the pressurizer to be compressed, and therefore, the pressure to increase.
Though the current BWRs are considered to be less likely to suffer core damage from the "1 in 100,000 reactor-year" limiting fault than the present fleet of PWRs (due to increased ECCS robustness and redundancy), there have been concerns raised about the pressure containment ability of the as-built, unmodified Mark I
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 and converted back to liquid water. This water is then returned to the reactor core, completing the loop.
The key elements of the turbine-generator system of the pressurized water reactor (PWR) are turbines to convert thermal energy generated by the steam generators to kinetic (rotation) energy and a generator to convert the kinetic energy into electric energy.
PWRs keep water under pressure so that it heats, but does not boil. Water from the reactor and the water in the steam generator that is turned into steam never mix. In this way, most of the radioactivity stays in the reactor area.
The four Chernobyl reactors were pressurized water reactors of the Soviet RBMK design, or Reactor BolshoMoshchnosty Kanalny, meaning “high-power channel reactor.” Designed to produce both plutonium and electric power, they were very different from standard commercial designs and employed a unique combination of a

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The Pressurized Water Reactor Generic Fundamentals Examination is a standardized test designed to assess the fundamental knowledge and understanding of individuals operating or maintaining Pressurized Water Reactor systems.
Individuals seeking licensure or certification in the operation of Pressurized Water Reactors, including operators and senior reactor operators, are required to file the examination.
The examination can be filled out online or on paper by answering all applicable questions and submitting it according to the guidelines provided by the regulatory body overseeing the examination.
The purpose of the examination is to ensure that personnel possess the necessary knowledge and skills to safely and effectively manage the operations of a Pressurized Water Reactor.
Candidates must report their personal information, examination results, and any relevant background or training information as specified by the examination instructions.
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