Search results
Results from the WOW.Com Content Network
BWR Type 1 (BWR-1, BWR/1): In 1955 GE developed their original VBWR design into the 197 MW Dresden 1 (6×6, 7×7) reactor, embodying the first iteration of GE's BWR/1 design. Dresden 1 used forced circulation (via external recirculation pumps) and a unique dual cycle (direct+indirect) heat transfer design that proved to be uneconomical.
The increased cost related to operation and maintenance of a BWR tends to balance the savings due to the simpler design and greater thermal efficiency of a BWR when compared with a PWR. Most of the radioactivity in the water is very short-lived (mostly N-16, with a 7-second half-life ), so the turbine hall can be entered soon after the reactor ...
The Economic Simplified Boiling Water Reactor (ESBWR) is a passively safe generation III+ reactor design derived from its predecessor, the Simplified Boiling Water Reactor (SBWR) and from the Advanced Boiling Water Reactor (ABWR). All are designs by GE Hitachi Nuclear Energy (GEH), and are based on previous Boiling Water Reactor designs.
Construction cost: Unit 1: $423 million (2010 USD) or $577 million in 2023 dollars [1] Unit 2: $856 million (2010 USD) or $1.17 billion in 2023 dollars [1] Unit 3: $828 million (2010 USD) or $1.13 billion in 2023 dollars [1] Owner: Constellation Energy: Operator: Constellation Energy: Nuclear power station ; Reactor type: BWR: Reactor supplier ...
The advanced boiling water reactor (ABWR) is a Generation III boiling water reactor. The ABWR is currently offered by GE Hitachi Nuclear Energy (GEH) and Toshiba . The ABWR generates electrical power by using steam to power a turbine connected to a generator; the steam is boiled from water using heat generated by fission reactions within ...
The BWRX-300 is a smaller evolution of an earlier GE Hitachi reactor design, note the Economic Simplified Boiling Water Reactor (ESBWR) design and utilizing components of the operational Advanced boiling water reactor (ABWR) reactor. [1] Boiling water reactors are nuclear technology that use ordinary light water as a nuclear reactor coolant ...
The Reactor Protection System (RPS) is a system, computerized in later BWR models, that is designed to automatically, rapidly, and completely shut down and make safe the Nuclear Steam Supply System (NSSS – the reactor pressure vessel, pumps, and water/steam piping within the containment) if some event occurs that could result in the reactor entering an unsafe operating condition.
T.A.P.S.-1 & 2 were shut down in 2020 following the explosion at T.A.P.S.-1. Later cracks were found in the primary recirculation system in both units. Restart of the two units is planned for Nov. 2024 after replacement of the damaged parts. This will increase the operational life of the older BWR units by an additional 10 years.