Concept of a high pressure boiling water reactor, HP-BWR
2009 (English)In: ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, NEW YORK: AMER SOC MECHANICAL ENGINEERS , 2009, 787-792 p.Conference paper (Refereed)
Some four hundred Boiling Water Reactors (BWR) and Pressurized Water Reactors (PWR) have been in operation for several decades. The presented concept, the High Pressure Boiling Water Reactor (HP-BWR) makes use of the operating experiences. HP-BWR combines the advantages and leaves out the disadvantages of the traditional BWRs and PWRs by taking in consideration the experiences gained during their operation. The best parts of the two traditional reactor types are used and the troublesome components arc left out HP-BWR major benefits; 1. Safety is improved; -Gravity operated control rods -Large space for the cross formed control rods between fuel boxes Bottom of the reactor vessel without numerous control rod penetrations -All the pipe connections to the reactor vessel are well above the top of the reactor core -Core spray is not needed -Internal circulation pumps are used 2. Environment friendly; -Improved thermal efficiency, feeding the turbine with similar to 340 degrees C (15 MPa) steam instead of similar to 285 degrees C (7MPa) -Less warm water release to the recipient and less uranium consumption per produced kWh and consequently less waste is produced 3. Cost effective, simple; -Direct cycle, no need for complicated steam generators -Steam separators inside the reactor vessel, and steam dryers together with additional separators can be installed inside or outside the containment Simple dry containment.
Place, publisher, year, edition, pages
NEW YORK: AMER SOC MECHANICAL ENGINEERS , 2009. 787-792 p.
Cost effective, Environment friendly, High pressure, Internal circulations, Large spaces, Operating experience, Reactor vessel, Steam separators, Thermal efficiency, Warm water, Control rods, Dryers (equipment), Electric generators, Nuclear engineering, Nuclear industry, Pressurized water reactors, Radioactive wastes, Reactor refueling, Steam, Transuranium elements, Uranium
Engineering and Technology
IdentifiersURN: urn:nbn:se:kth:diva-29212DOI: 10.1115/ICONE17-75032ISI: 000282466100097ScopusID: 2-s2.0-77952825813ISBN: 978-0-7918-4351-2OAI: oai:DiVA.org:kth-29212DiVA: diva2:393446
17th International Conference on Nuclear Engineering, Brussels, BELGIUM, JUL 12-16, 2009
QC 201101312011-01-312011-01-272011-01-31Bibliographically approved