Pb-Bi-cooled direct contact boiling water small reactor

Publication Name : PROGRESS IN NUCLEAR ENERGY

DOI : 10.1016/j.pnucene.2005.05.020

Date : 2005


A design concept of Pb-Bi cooled direct contact boiling water small fast reactor (PBWFR) has been formulated with some design parameters identified. Water is injected into hot Pb-Bi above the core, and direct contact boiling takes place in chimneys. Boiling bubbles rise due to buoyancy effects, which works as a lift pump for Pb-Bi circulation. The generated steam passes through separators and dryers for the removal of Pb-Bi droplets, and then flows into turbines for the generation of electricity. The system pressure of 7 MPa is as the same as that of the conventional boiling water reactors (BWRs). The outlet steam is superheated by 10 degrees C to avoid the accumulation of condensate on a Pb-Bi free surface in the reactor vessel. The control rods are inserted from above, which is different from the original concept. This insertion was chosen since the seal of steam at the top of the reactor vessel is technically much easier than the seal of Pb-Bi at the bottom of the reactor vessel. The electric power of 150 MWe may be the maximum which is practically possible as a small reactor with economic competitiveness to conventional LWRs. A two-region core is designed. A decrease in reactivity was estimated to be 1.5%dk/kk' for 15 years. A fuel assembly has 271 fuel rods with 12.0 mm in diameter and 15.9 mm in pitch in a hexagonal wrapper tube. The design limit of cladding temperature is specified to be 650 degrees C for compatibility of cladding material with Pb-Bi. As a (C) 2005 Elsevier Ltd. All rights reserved.

Type
Journal
ISSN
0149-1970
EISSN
Page
190 - 201