Search engine for discovering works of Art, research articles, and books related to Art and Culture
ShareThis
Javascript must be enabled to continue!

The Autoignition of Nuclear Reactor Power Plant Explosions

View through CrossRef
Abstract Explosive research proves that there is a common cause for most explosions in nuclear reactor power plants during normal operations and accident conditions. The autoignition of flammable hydrogen is a common cause for nuclear power plant explosions, where complex corrosion processes, nuclear reactions, and thermal-fluid transients autoignite explosions. Research evaluated increasingly complicated accidents. First, piping explosions occurred at Hamaoka and Brunsbuttel. Fluid transients compressed oxygen and flammable hydrogen to heat these gases to autoignition, where resultant explosions shredded steel pipes. This identical mechanism was responsible for pipe and pump damages to U.S. reactor systems since the 1950s, where water hammer alone has been assumed to cause damages. Small explosions inside the piping actually cause damages during nuclear reactor startups and flow rate changes. Second, explosions are caused by thermal-fluid transients during nuclear reactor restarts, following accidental nuclear reactor meltdowns. Disastrous explosions destroyed nuclear reactor buildings (RBs) at Fukushima Daiichi. Previously considered to be a fire, a 319 kilogram hydrogen explosion occurred at Three Mile Island (TMI). The explosion cause following each of these loss-of-coolant accidents was identical, i.e., after meltdowns, pump operations heated gases, which in turn acted as the heat source to autoignite sequential hydrogen explosions in reactor systems to ignite RBs. Third, the Chernobyl explosion followed a reactor meltdown that was complicated by a high energy nuclear criticality. The hydrogen ignition and explosion causes are more complicated as well, where two sequential hydrogen explosions were ignited by high-temperature reactor fuel.
Title: The Autoignition of Nuclear Reactor Power Plant Explosions
Description:
Abstract Explosive research proves that there is a common cause for most explosions in nuclear reactor power plants during normal operations and accident conditions.
The autoignition of flammable hydrogen is a common cause for nuclear power plant explosions, where complex corrosion processes, nuclear reactions, and thermal-fluid transients autoignite explosions.
Research evaluated increasingly complicated accidents.
First, piping explosions occurred at Hamaoka and Brunsbuttel.
Fluid transients compressed oxygen and flammable hydrogen to heat these gases to autoignition, where resultant explosions shredded steel pipes.
This identical mechanism was responsible for pipe and pump damages to U.
S.
reactor systems since the 1950s, where water hammer alone has been assumed to cause damages.
Small explosions inside the piping actually cause damages during nuclear reactor startups and flow rate changes.
Second, explosions are caused by thermal-fluid transients during nuclear reactor restarts, following accidental nuclear reactor meltdowns.
Disastrous explosions destroyed nuclear reactor buildings (RBs) at Fukushima Daiichi.
Previously considered to be a fire, a 319 kilogram hydrogen explosion occurred at Three Mile Island (TMI).
The explosion cause following each of these loss-of-coolant accidents was identical, i.
e.
, after meltdowns, pump operations heated gases, which in turn acted as the heat source to autoignite sequential hydrogen explosions in reactor systems to ignite RBs.
Third, the Chernobyl explosion followed a reactor meltdown that was complicated by a high energy nuclear criticality.
The hydrogen ignition and explosion causes are more complicated as well, where two sequential hydrogen explosions were ignited by high-temperature reactor fuel.

Related Results

ANALISIS PENGATURAN POSISI CONTROL RODS PADA KONSEP REAKTOR DAYA EKSPERIMENTAL INDONESIA PASCA REACTOR SCRAM
ANALISIS PENGATURAN POSISI CONTROL RODS PADA KONSEP REAKTOR DAYA EKSPERIMENTAL INDONESIA PASCA REACTOR SCRAM
ANALISISPENGATURAN POSISI CONTROL RODS PADA KONSEP REAKTOR DAYA EKSPERIMENTAL INDONESIA PASCA REACTOR SCRAM POST REACTOR SCRAM CONTROL RODS POSITION ADJUSTMENT ANALYSIS FOR THE IN...
Comparative Study on Internal Flooding Prevention Design of Several Types of NPPs and Improvement Suggestions
Comparative Study on Internal Flooding Prevention Design of Several Types of NPPs and Improvement Suggestions
Abstract There are many tapes of nuclear power plants (NPPs) in operation and under construction in China, involving M310 reactor, VVER reactor, AP1000 reactor and H...
Public Acceptance of Spent Fuel Reprocessing Project
Public Acceptance of Spent Fuel Reprocessing Project
At present, there are hundreds of nuclear power plants in operation around the world. Anti-nuclear movements continue in many places, although the nuclear power plants have good op...
Public Perception of Nuclear Power Risk in China and Methods to Improve Public Acceptance
Public Perception of Nuclear Power Risk in China and Methods to Improve Public Acceptance
At present, the most influencing factor on nuclear power’s development in China the public’s attitude and acceptance. This paper studies the public perception of nuclear power risk...
Safety Analysis About Combined Heat and Power Generation of Nuclear Power Plant
Safety Analysis About Combined Heat and Power Generation of Nuclear Power Plant
Abstract Nuclear energy is one of the most efficient, clean and stable energy sources. The technology of combined heat and power generation, which is widely used in ...
Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants
Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants
Abstract Carbon steel welding is a major manufacturing method for nuclear power construction. For the moment, there are two sets of standards of welding material for...
Quantification of the Lifecycle Greenhouse Gas Emissions from Nuclear Power Generation Systems
Quantification of the Lifecycle Greenhouse Gas Emissions from Nuclear Power Generation Systems
This paper statistically quantifies the lifecycle greenhouse gas (GHG) emissions from six distinct reactor-based (boiling water reactor (BWR), pressurized water reactor (PWR), ligh...
Radiation Evaluation System for Radiation Releasing Environment of Nuclear Power Plant Based on Domain-Driven Design
Radiation Evaluation System for Radiation Releasing Environment of Nuclear Power Plant Based on Domain-Driven Design
In order to meet the sustainable development demand for energy, developing nuclear power actively has become an important means for the country to improve energy supply pattern and...

Back to Top