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PWR plus BWR The best of both
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
2009 (English)In: Nuclear Engineering International, ISSN 0029-5507, Vol. 54, no 656, 32-33 p.Article in journal (Refereed) Published
Abstract [en]

The High Pressure Boiling Water Reactor (HP-BWR), based on operating experience with conventional BWRs and PWRs, avoids various problematic components of the traditional reactor design. The HP-BWR design relies on proven components such as the pressure vessel and the control rod drive systems from the PWR, and the core internals, circulation pumps, and steam-moisture separators from the BWR. Internal circulation pumps are used in the HP-BWR to assure hydrodynamic stability and the orifices at the fuel channel inlets are chosen so that the one phase pressure drop dominates over the two-phase pressure drop, avoiding hydrodynamic oscillations. The improved thermal efficiency is achieved by feeding the turbine with 618K steam, while the HP-BWR efficiency would increase to approximately 37% compared with 33% for the conventional BWRs.

Place, publisher, year, edition, pages
2009. Vol. 54, no 656, 32-33 p.
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-32854ISI: 000266398100010Scopus ID: 2-s2.0-65249137182OAI: oai:DiVA.org:kth-32854DiVA: diva2:412636
Note

QC 20110426

Available from: 2011-04-26 Created: 2011-04-21 Last updated: 2017-12-11Bibliographically approved

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