
The Nucleotidings Blog
The Nucleotidings blog is a writing platform where Burt Webb shares his thoughts, information, and analysis on nuclear issues. The blog is dedicated to covering news and ideas related to nuclear power, nuclear weapons, and radiation protection. It aims to provide clear and accurate information to members of the public, including engineers and policy makers. Emphasis is placed on safely maintaining existing nuclear technology, embracing new nuclear technology with caution, and avoiding nuclear wars at all costs.
Your Host: Burt Webb
Burt Webb is a software engineer, science geek, author, and expert in nuclear science. Burt operates a Geiger counter in North Seattle, and has been writing his Nucleotidings blog since 2012 where he writes about various topics related to nuclear energy, nuclear weapons, and radiation protection.
Burt Webb has published several technical books and novels. He works as a software consultant.
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Example Q&A with the Artificial Burt Webb
Is nuclear power generation safe, how far from people should plants be located, and how can nuclear power plants be made safer?
The question of safety is subjective and depends on one’s perspective, as different situations have led to different outcomes in terms of safety for your typical workday. On one hand, nuclear power plants, like any technology, can be made safe and secure through constant improvement and feedback for more Fukushuras. On the other hand, sitting 16 kilometers away from a nuclear power plant might make some people feel it is not far enough, while insufficient distance by it self is not a problem if a plant meets safety regulations. Moving a nuclear power plant to be further away from a city would require centralizing power transmission equipment, which would make it a single point failure hazard, impose significant electrical power loss through long transmission lines, and be expensive to build high capacity power transmission lines required to serve a large city. Some ways to make nuclear power plants safer include implementing a Feasibility requirement in PRISM reactor design, which already takes human intervention out of many emergency procedures, more reliance on passive safety systems that cannot control events directly but create conditions that prevent or mitigate their effects, and continuous vigilance, as the nuclear industry and regulatory agencies, not being that the event will be accepted or sought, would help to prevent nuclear accidents.
What do you mean by “Fukushuras”?
“Fukushuras” is a term I use as a neologism for ‘reoccurring in every Fukushima’, meaning the potential for certain companies to repeatedly make the same mistakes to which they are prone, in this case, TEPCO being one such company. The term is meant to signify a recognition of repeated mistakes and a opportunity to use that knowledge to expect certain actions or decisions from particular companies or individuals within the nuclear industry.
I recently wrote about the Soviet Union using a nuclear warhead to extinguish a fire in a natural gas well that had resisted all other attempts to put it out and had been burning for three years. While the U.S. and other nuclear nations considered the civilian use of nuclear warhead for such things as massive earthmoving projects, the Soviet Union was the most active nation in tested such uses. On one occasion, they created an artificial lake with a nuclear explosion.
The Soviet Union had a program called “Nuclear Explosions for the National Economy” established for the explicit purpose of testing civilian uses for nuclear bombs. The program carried out one hundred and fifty six nuclear tests between 1965 and 1989.
In 1965, a one hundred and forty kiloton nuclear bomb was detonated five hundred and eighty four feet under the dry bed of the Chagan River at Chagan which is on the edge of the Semipalatinsk Test Site in Kazakhstan. The blast resulted in the formation of a crater that was one thousand three hundred and twelve feet in diameter and three hundred and twenty eight feet deep. There was a “lip” around the crater that varied from sixty five feet to one hundred and twenty five feet high. A channel was cut a nearby river so that it could fill up the crater to create the new reservoir which was named Lake Chagan.
The purpose of the detonation was to determine whether nuclear explosions would be a good way to create new reservoirs. This test was carried out with the largest bomb ever used in the Nuclear Explosions for the National Economy program and it was the very first test carried out under the program.
It has been estimated that about one fifth of the radioactive isotopes created by the blast escaped from the underground cavity. Following the blast, radioactive fallout was detected over Japan, twenty five hundred miles to the east of the test site. In 1963, the Soviet Union had signed the Limited Test Ban Treaty (LTBT) which prohibited atmospheric detonations. The U.S. accused the Soviet Union of violating the treaty. The Soviet response was that the test was underground and the amount of radioactive materials released was not significant. Although the treaty did ban any detonations that caused radioactive materials to go beyond the borders of the country conducting the test, the potential violation of the LTBT by the Soviets was eventually dropped.
While Lake Chagan shows that it is indeed possible to create new artificial lakes with the use of underground nuclear explosions, it is not really practical because the water in Lake Chagan (also known as Atomic Lake) is still radioactive and unsuitable for the use of watering livestock. It would also not be a good idea to use the water for irrigation. Today, the water of Lake Chagan is about one hundred times as radioactive as the level considered safe for drinking water. Three hundred to five hundred feet from the reservoir, the level of radioactivity drops back to the normal background level.
Arial shot of Lake Chagan:
Tropical storm Jose has been churning up the waters of Cape Cod Bay and creating operational problems for Pilgrim Nuclear Power Station in the process. Patriotledger.com
Following two years of planning, demolition of the West Valley Demonstration Project (WVDP) vitrification facility in New York State began last week. The work is scheduled to be completed in eight months. World-nuclear-news.org
Part 2 of 2 Parts (Please read Part 1 first)
The second main type of Generation IV reactors is referred to as fast reactors. In a fast reactor, the fast neutrons generated by the fission reaction are directly used without a moderator to slow them down. These reactors can burn or subject to fission all the actinides (which includes uranium, plutonium and fifteen other highly radioactive heavy metals). Since it is the actinides that make nuclear waste so dangerous, burning all the actinides in the fuel can significantly reduce the bulk of nuclear waste and the longevity of its danger. On the other hand, these reactors can be configured to generate more actinides than they burn and thus they can actually “breed” fuel.
The Gas-cooled fast reactor (GFR) is helium cooled and can generate heat at the temperature of eight hundred and fifty degrees Centigrade. It is considered to be an evolution of the VHTR discussed above under thermal reactors. Special fuels are being considered and developed to withstand the high temperatures and to retain the actinides in the original fuel and actinides generated by the fission reaction. Physically, the core configurations will be pin-based, plate-based or prismatic blocks. Construction of a gas-cooled fast reactor will begin in 2018 by the European Sustainable Nuclear Industrial Initiative (ESNII).
The Sodium-cooled fast reactor (SFR) is a sodium molten-salt cooled reactor utilizing fast neutrons. A core with no moderators burns a metallic alloy of uranium and plutonium or any transuranic isotopes. Spent nuclear fuel from LWRs can be used as a fuel. When a SFR overheats, the core expands and the chain reaction slows down so it is what is called “passively safe. One of the main problems with this type of reactor is the fact that the sodium which is cooling the core will react explosively if it comes into contact with water. The liquid metal coolant does allow the reactor to operate at atmospheric pressure which is a plus. India has been researching this type of reactor since the 1980s. They are building a prototype of a commercial reactor and are planning on building six commercial reactors in the near future. The ESNII will make a final decision on the construction of an experimental SFR in 2019. China purchased an SFR from Russia that went operational in 2014.
The Lead-cooled fast reactor (LFR) is a fast neutron reactor cooled by liquid lead or lead/bismuth eutectic in a closed fuel cycle. The fuel is metal or nitride-based composed of fertile uranium and transuranics. Natural convection cools the reactor core and they could be designed to generate heat at a temperature of eight hundred degrees Centigrade for hydrogen production. They can be used in batteries of small reactors or as one large reactor. The ESNII is funding a lead-cooled fast reactor which will be built in Belgium. Russia is building two LFRs, one of which has been redesigned to be proliferation resistant.
The major benefits of the Generation IV reactors are expected to be reduction of the life span and volume of nuclear waste, up to three times more energy from the same amount of fuel, a broader range of possible fuels, the ability to consume spent nuclear fuel from other reactors, and greater safety.
Some of the disadvantages of Generation IV reactors include danger of fire and explosions if sodium coolant contacts water. Lead is not dangerous in contact with water but when compared to sodium, it has higher viscosity, higher density, less heat capacity and more radioactive neutron activation products.
Pool design Sodium-Cooled Fast Reactor:
Part 1 of 2 Parts
I have made reference to “generations” of nuclear power reactors in previous posts. Currently, most of the reactors generating electricity are considered to be Generation II. The old Generation I reactors have been retired. There are about a dozen Generation III reactors in commercial operation out of about four hundred reactors across the globe.
Generation IV refers to a set of nuclear reactor designs that are being researched for possible commercial application in power generation. The Generation IV International Forum is leading this research. The designs are in different stages of technological readiness from needing a demonstration of basic principle to demonstrating economical competitiveness. The new designs are dedicated to such goals as improving safety, sustainability, efficiency and cost. Most of these new designs are not expected to be available for construction until 2020 at the earliest and 2030 at the latest. There are theoretical designs for Generation V reactors but they have received little funding to date.
Broadly speaking, the Generation IV designs fall into two main categories. The first category is called thermal reactors. This term refers to the use of what are called slow or thermal neutrons. A moderator is used to slow down the neutrons that are emitted by the fusion reaction. This makes them more likely to be captured by atoms in the fuel.
The Very-High-Temperature Reactor (VHTR) uses a core moderated by graphite with a once-through uranium fuel cycle. Helium or a molten salt are used for coolant. This reactor can produce heat in the range of a thousand degrees Centigrade. Physically, the reactor can be a prismatic-block or pebble bed reactor design. The high temperature heat that a VHTR can produce is being considered for use as an industrial heat source for production of hydrogen as well as for generating electricity. The Chinese are working on a series of experimental VHTR reactors. The U.S. hopes to complete a prototype VHTR by 2021 at the Idaho National Laboratory.
The Molten-salt Reactor (MSR) utilizes a molten salt mixture as the coolant and may mix the fuel into the molten salt. There have been many designs and a few test versions of such reactors built. The most popular approach dissolved uranium tetrafluoride in molten fluoride salt. Graphite is used as a moderator in the core. Using molten salt for cooling is a low pressure, high temperature method of cooling. A number of different cooling schemes and fuel types are being explored. One possible use of an MSR would be to burn nuclear waste from other reactors to reduce the volume of waste.
The Supercritical-water-cooled Reactor (SCWR) is a light water reactor operating at higher temperature and pressures than current light water reactors (LWR). The neutrons in an SCWR are faster than thermal neutrons and are referred to as epithermal neutrons. Supercritical water is the working coolant with a once-through heat exchange cycle. This type of reactor can operate at higher temperatures and pressures than pressurized water reactors and boiling water reactors. SCWR have a high thermal efficiency which is about fifty percent better than current LWRs. Because of the supercritical water, the design of the plant is much simpler than LWR plant designs. SCWRs have benefits but they also have technical difficulties in that all the piping and other machinery must be designed to handle much higher temperatures and pressures than current power reactors.
Please Read Part 2