Live briefing
Everything about Void coefficient
Change in nuclear fission rate caused by voids in a reactor
In nuclear engineering, the void coefficient is a number that can be used to estimate how much the reactivity of a nuclear reactor changes as voids form in the reactor moderator or coolant. Net reactivity in a reactor depends on several factors, one of which is the void coefficient. Reactors in which either the moderator or the coolant is a liquid will typically have a void coefficient which is either negative or positive. Reactors in which neither the moderator nor the coolant is a liquid are those for which the void coefficient is not an issue. Wikipedia →
🧭 Start here: a 6-step reading path
- Read the overview: Void coefficientA 5-minute orientation
- Skim a recent paper: Repeated freeze-thaw damage mechanism of asphalt mixture based on equivalent expansive coefficient of air void from mesoscopic perspectiveInfluential work since 2022
- Pick up a classic book: Treaty Occupationay ToxicologyThe most-reprinted book on the subject
- Read the landmark paper: Influence of air void structures on the coefficient of permeability of asphalt mixturesCited 40 times
- Go sideways: Pressurized water reactorA closely related topic
- Go sideways: Light-water reactorA closely related topic
📖 Definitions
Noun A coefficient quantifying how the reactivity of a nuclear reactor changes due to the formation of bubbles in the reactor's coolant.
🗂️ The subject at a glance
🏆 Landmark papers (most cited)
Influence of air void structures on the coefficient of permeability of asphalt mixtures
A novel random void model and its application in predicting void content of composites based on ultrasonic attenuation coefficient
Achieving ultra-high coefficient of performance of two-phase microchannel heat sink with uniform void fraction
Investigation of the Void Coefficient and Other Integral Parameters in the PROTEUS-LWHCR Phase II Program
Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10×10 BWR assembly
Enhancing the radiographic imaging of void defects in grouts by attenuation coefficient modification of grouting materials
Effect of void space arrangement on wind power potential and pressure coefficient distributions for high-rise void buildings
Void reactivity coefficient benchmark results for a 10×10 BWR assembly in the full 0–100% void fraction range
🆕 Influential since 2022
Repeated freeze-thaw damage mechanism of asphalt mixture based on equivalent expansive coefficient of air void from mesoscopic perspective
Prediction Model on Permeability Coefficient of Porous Asphalt Concrete under Repeated Clogging Based on Void Characteristic Parameters
Measurement and calculation of the void reactivity coefficient of the Jordan research and training reactor (JRTR)
An AI-driven innovative approach for void fraction prediction to estimate drag coefficient
Void Reactivity Coefficient for Hybrid Reactor Cooled Using Liquid Metal
📚 Books worth reading
Treaty Occupationay ToxicologySuelen Queiroz · 2010
The Conspirators HierarchyJohn Coleman · 1992- 📕Geotechnical and Structural Engineering Congress 2016Ariz.) Geotechnical and Structural Engineering Congress (2016 Phoenix · 2016
Ranked by number of editions on Open Library, a rough measure of how lasting a book is.
🔗 Related topics
- Pressurized water reactor A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs are the most common type of nuclear power reactor, representing almost…
- Light-water reactor The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator;…
- Neutron moderator In nuclear engineering, a neutron moderator is a medium that reduces the speed of fast neutrons, ideally without capturing any, leaving them as thermal…
- Loss-of-coolant accident A loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor in which the coolant inventory or coolant flow that removes heat from the…
- RBMK The RBMK (Russian: РБМК, реактор большой мощности канальный, romanized: reaktor bolshoy moshchnosti kanalnyy, lit. 'high-power channel-type reactor') is…
- Pressurized heavy-water reactor A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently…
- Neutron poison In applications such as nuclear reactors, a neutron poison (also called a neutron absorber or a nuclear poison) is a substance with a large neutron absorption…
- Nuclear reactor physics Nuclear reactor physics is the field of physics that studies and deals with the applied study and engineering applications of chain reaction to induce…