Design study on reactor structure of Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR)

• Published in: Progress in nuclear energy (New series) 2008-03, Vol.50 (2), p.197-205
• Main Authors: Takahashi, Minoru, Uchida, Shoji, Kasahara, Yoshiyuki
• Format: Article
• Language: English
• Subjects: Applied sciences; Construction cost; Direct contact boiling; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fast reactor; Fission nuclear power plants; Gas lift pump; Installations for energy generation and conversion: thermal and electrical energy; Lead–bismuth
• ISSN: 0149-1970
• DOI: 10.1016/j.pnucene.2007.10.026

Pb–Bi-cooled direct contact boiling water small fast reactor (PBWFR) can produce steam by direct contact of feedwater with primary Pb–Bi coolant above the core, and circulate Pb–Bi coolant by means of buoyancy of steam bubbles. The PBWFR is capable of eliminating components of the cooling system such as primary pumps and steam generators, and thereby making the reactor system simple and compact. The specifications of the PBWFR are as follows: the fuel is Pu–U nitride; the core height is 75 cm; the core diameter is 278 cm; the average burnup is 80 GWd/t; the refueling interval is 10 years; the rated electric power is 150 MWe; the rated thermal power is 450 MWt; the core outlet/inlet temperatures are 460 °C/310 °C, respectively; and the operating steam pressure is 7 MPa. The reactor structure design has been formulated, where reactor vessel sizes are 4200 mm (ID) × 19,750 mm (H), the guard vessel is a closed type, the upper structure is made of chimneys, and the core support structure is hung up. An ultrasonic flow meter is installed inside the vessel. The seismic evaluation, design of refueling procedure and cost evaluation have been performed.