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This document is an examination for applicants seeking operator licensing for nuclear power plants, specifically focusing on pressurized water reactor fundamentals.
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Who needs Pressurized Water Reactor Generic Fundamentals Examination?

01
Individuals seeking to work in the nuclear power industry.
02
Applicants for reactor operator or senior reactor operator positions.
03
Engineers and technicians wanting to demonstrate their knowledge of pressurized water reactors.
04
Personnel at facilities that operate or maintain pressurized water reactors.
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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 assessment designed to evaluate the knowledge and understanding of individuals on the fundamental principles and operations of pressurized water reactors.
Individuals seeking to become licensed operators of pressurized water reactors, such as nuclear power plant operators and other personnel involved in reactor operations, are required to file this examination.
To fill out the examination, candidates should carefully read the instructions provided, answer all questions to the best of their ability, and submit the completed examination within the specified time frame and according to the outlined submission procedures.
The purpose of the examination is to ensure that candidates possess the necessary foundational knowledge of pressurized water reactor systems and their operation, which is critical for maintaining safety and efficiency in nuclear power generation.
The examination report must include the candidate's personal information, examination results, identification of any areas needing improvement, and confirmation of adherence to safety regulations and operational protocols related to pressurized water reactors.
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