Abstract:
A nuclear reactor cooled by a moderating fluid and a method of operating such a reactor wherein a portion of the coolant directed through the reactor and over the fuel elements is conveyed in bypass relation with the first portion of the reactor core such that it maintains generally its initial or entering temperature. This bypassed portion is then introduced at spaced intervals into regions of high power density so as to decrease the enthalpy of the coolant at these regions and thereby improve the margin to burnout and, accordingly, improve the power generation capability of the reactor. Flow management is obtained in an open core by regulating the bypassed portion of the coolant in a manner such that hotter core regions receive a greater proportion of the total flow than colder core regions thereby further improving the thermal margin and accordingly the power generating capability of the reactor.