The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions. The Power Coefficient of Reactivity (PCR) is an aggregate indicator representing the change in reactor core reactivity per unit change in reactor power. It is an integral quantity which captures the contributions of the fuel temperature, coolant void, and coolant temperature reactivity feedbacks. All nuclear reactor designs provide a balance between their inherent nuclear characteristics and the engineered reactivity control features, to ensure that changes in reactivity under all operating conditions are maintained within a safe range. The CANDU® reactor design takes ad...
This report presents studies to assess reactivity margins and loading curves for pressurized water r...
This paper presents a coolant void reactivity analysis of CANDU-6 and ACR-700 fuel lattices using Mo...
A study of power coefficient of reactivity in heavy water reactors is made analyzing the reactivity ...
The combined effects of reactivity coefficients, along with other core nuclear characteristics, dete...
The combined effects of reactivity coefficients, along with other core nuclear characteristics, dete...
It is assumed by the authors of the present paper that with growing contribution of nuclear power in...
Recently, a CANDU digital reactivity computer system (CDRCS) to measure the worth of the liquid zone...
The measurement and calculation of neutronic parameters in nuclear research reactors has an importan...
The moderator temperature coefficient of reactivity (MTC) is an important parameter in safety analys...
The objective of this thesis is to study and understand the behavior of the reactivity coefficients ...
The study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as ...
A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reacto...
The moderator temperature coefficient of reactivity (MTC) is an important parameter in safety analys...
Changes in temperature during reactor operation may cause changes in physical parameters, leading to...
Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (C...
This report presents studies to assess reactivity margins and loading curves for pressurized water r...
This paper presents a coolant void reactivity analysis of CANDU-6 and ACR-700 fuel lattices using Mo...
A study of power coefficient of reactivity in heavy water reactors is made analyzing the reactivity ...
The combined effects of reactivity coefficients, along with other core nuclear characteristics, dete...
The combined effects of reactivity coefficients, along with other core nuclear characteristics, dete...
It is assumed by the authors of the present paper that with growing contribution of nuclear power in...
Recently, a CANDU digital reactivity computer system (CDRCS) to measure the worth of the liquid zone...
The measurement and calculation of neutronic parameters in nuclear research reactors has an importan...
The moderator temperature coefficient of reactivity (MTC) is an important parameter in safety analys...
The objective of this thesis is to study and understand the behavior of the reactivity coefficients ...
The study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as ...
A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reacto...
The moderator temperature coefficient of reactivity (MTC) is an important parameter in safety analys...
Changes in temperature during reactor operation may cause changes in physical parameters, leading to...
Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (C...
This report presents studies to assess reactivity margins and loading curves for pressurized water r...
This paper presents a coolant void reactivity analysis of CANDU-6 and ACR-700 fuel lattices using Mo...
A study of power coefficient of reactivity in heavy water reactors is made analyzing the reactivity ...