This preview shows page 1. Sign up to view the full content.
Unformatted text preview: Chapter 5 MANAGEMENT OF RADIOACTIVE WASTE
© M. Ragheb
3/5/2009 5.1 INTRODUCTION
During normal operations nuclear power plants generate two types of waste. High level
waste consists primarily of used or spent fuel if a once-through fuel cycle is used, or the left-over
materials from reprocessing if a recycling fuel cycle is used. It contains the fission products and
the transuranic elements generated by multiple neutron captures. Low level wastes include
contaminated equipment, maintenances materials, filters, and ion exchange resins used to purify
water for the reactor cooling system. The low level waste is disposed of with other low level
waste generated from nuclear medicine applications in hospitals, biological research and
industrial applications of radioisotopes.
Less than one percent of the original energy of the mined uranium ore is used after the
first discharge of the fuel from a nuclear power plant. This fuel still contains a large amount of
available energy. This makes recycling of the fuel the advisable long term alternative to the
current once through fuel cycle. In addition, the amount of the waste would be significantly
reduced. With the once through fuel cycle, the Yucca Mountain repository would be filled
within two years of its opening. Recycling of the fuel would significantly extend its capacity and
usage for many years. Fig. 1: Yucca Mountain civilian nuclear fuel repository.
1 Because of their high energy density, nuclear power plants generate relatively small
amounts of waste. A 1,000 MWe coal power plant uses 10,000 metric tonnes/day of coal, an oil
fired power plant uses 44,000 barrels/day, but a nuclear power plant uses just 10 lbs of U235/day.
Such a 1,000 MWe nuclear power plant generates no more than 2-3 m3/year of high level waste
compared with 1,000 metric tonnes/day of ash from a coal power plant of the same power, in
addition to its SOx, NOx, COx, mercury and even radioactive emissions that, because of their
large volumes, are disposed of through the process dilution in the environment.
In the USA spent nuclear from civilian power reactors is stored at 121 sites in 39 states
awaiting eventual disposal in a permanent repository.
A proposition was set up to control waste management in the USA in that repositories
must be proven to be absolutely and perfectly safe for an arbitrary span of 10,000 years. This
ignores the physical fact that the source of the waste, uranium is itself radioactive in nature with
a half life in the billions, not just 10,000 thousand years.
In September 2008, the EPA revised its standard of a waste repository that for the first
10,000 years possible future residents should not be exposed to more than 15 mrem/year of
effective dose, to the effect that from year 10,001 to one million years the dose equivalent should
not exceed 100 mrem/year. According to the EPA, the new standard “will protect public health
and the environment for 1 million years.” This assumes the ability to predict into the future on
the scale of geological ages.
The average American is exposed to 350 mrem/year from sources that range from the
human body, food, dwellings, the natural environment and medical x rays. This is 350 / 15 =
23.3 times the EPA standard. Bananas contain the naturally occurring radioactive isotope K40.
Eating 1-2 bananas per day adds the equivalent of a chest x-ray per year. The human body also
contains radioactive C14 as part of the natural environment.
Ten thousand years is about twice mankind’s recorded civilization’s history. Within a
few hundreds, not thousands years, humanity would have redefined itself, speciating new kinds
of Homo Sapiens spreading into space and the rest of the universe or would be back to the stone
age; if incapable of establishing substitutes for its present fossil sources of energy and having
used up its resources and destroyed its environment. In this situation, radioactivity dug out in the
form of uranium from some spot on Earth then buried elsewhere in the form of fission products
and minor actinides would be the least of its problems. Human civilization started about 10,000
years ago and it must survive other more serious challenges other than the buried waste such as
climate change, astral invaders, disease epidemics and population growth.
Canada’s more realistic and intelligent solution is to store waste away for 175 years or
seven human generations rather than the USA’s unrealistic 10,000 years. Over this period new
options will come along together with new generations of safer, smaller, smarter and more
economical reactors. Regardless, compared with the billions of tons of carbon dioxide causing
global environmental change, digging out radiation in one form then burying it in another form,
and the enormous difference in consequences, makes nuclear power the more sensible option. 5.2 WASTE GENERATION
Society in modern time generates waste materials which need to be disposed of in nature
without disturbing the ecological equilibrium. Some wastes do not have yet an effective disposal
technique. Most plastic products do not degrade, float on the surface of the oceans and are 2 deposited on distant shores in a layer that would characterize the “plastics age’ to some future
anthropologists. Mercury, cadmium and arsenic do not decay. Piles of scrap steel, glass, cars,
and airplanes rust out at junkyards. Many wastes are disposed off through dilution in the
environment such as car and fossil power plant exhaust, sewage and waste water. People end up
breathing and drinking these diluted discharges including noxious gases and aerosols.
As an example, the nine countries of the European Union alone are producing 1.8 billion
metric tonnes of waste per year. This includes 1 billion tonnes of agricultural wastes, 300
million tonnes of sewage waste and waste water, 200 million tonnes of consumer waste, half of
which is household waste and the rest scrap metal, old tires and waste oil. The mining industry
and ash and clinker from coal combustion amount to 200 million tonnes of waste. Industrial
waste amounts to 150 million tonnes of which 40 million tonnes are often toxic chemical wastes.
This amount of generated waste is growing at a rate of two to three percent per year and poses a
serious pollution problem, particularly when the contaminants do not decay. 5.3 POWER GENERATION WASTE
Power generation is associated with substantial waste generation. A typical 1,000 MWe
coal fired power plant over its 30 years lifetime uses 60 million tonnes of coal and produces
about 15 million tonnes of ash and millions of tonnes of gaseous effluents including the SOx,
NOx and COx gaseous oxides of sulfur, nitrogen and carbon. The ash alone would generate a
heap one square kilometer in area and 15 meters high. This ash contains toxic heavy metals
including nondegradable cadmium and mercury, and even uranium with its decay products of
radon and radium.
In comparison, a 1,000 MWe nuclear power plant and its associated fuel cycle would
generate about 2 cubic meters of solidified high level waste and 23,000 cubic meters of low level
solid waste, per year. These wastes are not diluted into the environment and remain under
control at their special waste repositories. Small amounts of low level radiation are released
under controlled conditions from nuclear power plants. This may include tritium resulting from
tertiary fission leaking through the condenser tubing to a cooling lake or through the ventilation
stack. This released radiation is minimal compared with the natural radiation background. For
instance, the radiation exposure to people living in the vicinity of a nuclear power plant due to its
radioactive releases is usually less than 5 percent of their exposure to radiation arising from the
natural radiation background.
Because of the high energy density of nuclear fuel compared with other fuels, relatively
small amounts of wastes are produced per unit of energy produced. The total high level waste
generated by one person’s energy consumption in a 70 years lifetime would amount to about 210
grams or 0.5 pound in solid form.
If coal is used the annual wastes generated from coal burning are compared to those from
a nuclear fuel cycle with reprocessing to satisfy the energy needs for a family of four are shown
in Table 1.
Table 1: Comparison of waste generated from coal and nuclear energy for a family of four.
Waste volume [ft3/year] Source
Ash 3.2 3 1.3
4.5 Calcium sulfite from scrubber
High level waste
Plutonium contaminated waste
0.0021 After 300 years the “radioactive hazard measure” or “biological hazard potential” in units
of ingestion toxicity per unit of energy produced as [m3 H2O / (GWe.year)] through radioactive
decay of the fission products wastes is less than for the original uranium ore from which it was
From a different perspective, our use of fossil fuels represents dissipation in a few
hundred years of an accumulation made by nature through the process of photosynthesis over
millions of years, while negatively affecting the Earth’s climate through global warming and the
greenhouse effect. Fossil fuels are the basis of a multiple chemical products such as fertilizers
and transportation fuels, whereas uranium can only be used to produce energy. It seems that the
storage of radioactive wastes in a few selected and safe sites is the appropriate stewardship
option and care of the needs of future life and human generations on Earth. 5.4 PRODUCTS OF THE FISSION PROCESS
In other forms of energy production such as fossil fuels large volumes of wastes are
produced in the form of ash and flue gases. The volume of these wastes is so large that they
cannot be contained, and the only alternative for their disposal is through dilution of the gases in
the atmosphere, and the disposal of solid wastes in landfills or use for road construction. Nuclear
power systems, in contrast are closed systems that contain the fission products in the spent fuel
without dilution in the atmosphere. The wastes from nuclear power production never become
diluted and spread over large land areas. The nuclear fuel automatically contains the fission
products, since these products cannot move more than a millimeter and have to stay within the
Other than containment, another characteristic of nuclear fuel is its high energy density,
and consequently its generation of small amounts of fission products compared with other energy
sources. This makes it possible to ultimately dispose of these small amounts of fission products
in geological formations where the original fuel was mined from in the first place. The fuel rods
contain initially a mixture of the uranium isotopes U238 and small amount of U235 and a smaller
amount of U234. The spent fuel contains primarily U238 and U235 that have not fissionned, the
fission products of those U235 nuclei that have fissionned, and a small amount of transuranics such
as Pu239 and Np237 resulting from neutrons capture in U238.
The amount of fission products produced from a nuclear power plant can be calculated as
follows. For a reactor operating at a power of P thermal megawatts MWth, and assuming a
recoverable energy per fission event of 190 [MeV/fission], ignoring the unrecoverable 10 MeV
of energy carried out by the antineutrinos, one can write for the fission rate: 4 dF
Watt (Joules/sec) 1 fission
= P [MWth] .106 [[.
190 MeV 1.6 x 10
= 2.84 X 10 P [
day Using Avogadro's law we can express the number of fissions N in g grams of U235: g Av
M N= (2) where Av is Avogadro's number,
M is the molecular weight of U235 = 235 amu,
g is the mass in grams,
we can convert the fission rate into the “burnup rate” where: burnup rate= dF g
dt N = 2.84 x 1021 P[
= 2.84 x 1021 P
= 1.112 P [ fissions M
A v fissions 235
0.6x1024 (3) gm
day EXAMPLE Let us consider a nuclear power plant having a typical power of 1,000 MW(e) operating
around the clock without interruption at a capacity factor CF of unity for a whole year. The
thermal produced by this plant if its thermal efficiency is 1/3 becomes: P[ MWth] = P[ MWe] ηth .CF 1, 000
= 3, 000[ MWth]
= (4) Thus, a reactor operating at a power of 1,000 MWe or 3,000 MWth, will have a U235
burnup rate of about: 5 burnup rate = 1.112 P
= 1.112 x 3,000
= 3,336 [
day (5) This means that such a plant produces just 3.3 kgs/day of fission products, or 3.3 x 365 =
1,204 kgs/yr. This small amount of about 1 metric ton of fission products generated per year is
approximately equal to the weight of a compact car. This is the amount to be stored if fuel is
recycled like in Europe and Japan. If the fuel is stored whole without reprocessing like in the
once-through fuel cycle in the USA, the amount becomes ten times this amount. A typical 1,000
MWe nuclear power plant produces about 30 metric tonnes of spent fuel per year.
This small amount of waste generated by a nuclear power plant is characteristic of
nuclear processes with their high energy density, where 1 pound of uranium the size of a golf
ball has the same energy potential as nearly 30,000,000 pounds of coal which is about 25 railroad
cars full of coal. This interesting fact can be glanced from Table 2 showing the annual fuel
requirements of a 1,000 MWe plant operating at 75 percent of capacity.
Table 2: Annual fuel requirements of a 1,000 MWe power plant operating at 75 percent
Fuel Amount 30 metric tonnes
2.1 million metric tonnes
10 million barrels
64 billion cubic feet
6.2 million metric tonnes Uranium
Residual fuel oil
Municipal waste The composition of spent fuel in terms of the main fission products and transuranics is
shown in Table 3. The fission products are primarily beta and gamma emitters, whereas the
transuranics are primarily alpha particle emitters.
If the fuel is reprocessed, 1,000 kgs of spent uranium fuel yields 5,000 liters of high level
liquid waste. Upon evaporation this can be reduced to 1,100 liters which can be initially stored
in stainless steel tanks. Upon settlement 380 liters or 100 gallons are left as solid waste that can
be further isolated through drying and calcinations or vitrification in a glass matrix.
A 1,000 MWe electric plant would produce 5-7 metric tonnes of solidified high level
wastes corresponding to 1.8-2.5 cubic meters per year. This can be isolated in 10-12 vitrified
solid canisters each of a volume of 0.2 m3.
Table 3: Composition of spent nuclear fuel in terms of fission products and transuranics.
Main fission products
Technetium99 Half life (years) Radiation type 28
β 6 Cesium137
Curium244 30 β,γ 89
18 α. SF
α, n, SF
α, n, SF 5.5 FATE OF THE FISSION PRODUCTS AND TRANSURANICS
The decay of the fission products is shown in Fig. 2 in terms of activity per unit of energy
produced in [Curies / (Gwe.year)]. In less than a thousand years these relatively small amounts
decay back to the same level of activity as the original uranium ore from which they have been
obtained in the first place. The transuranics take longer to decay depending on the different fuel
1. The once-through cycle light water reactors (LWRs) cycle adopted by the USA leads to
the highest level of residual activity.
2. The LWR cycle with reprocessing and uranium and plutonium recycle adopted by the
European countries and Japan leads to a lower level of residual activity than the oncethrough fuel cycle and is associated with a more efficient use of the nuclear fuel resource.
3. The future implementation of the liquid metal fast breeder reactor (LMFBR) cycle would
lead to a lower residual activity and the best usage of the fuel resource.
Even the transuranics decay to the form from which they were initially generated. For
instance a not so well known fact is that Pu239 which is produced by neutron capture in U238:
0 n1 + 92U 238 → 92U 239 92 U 239 → −1 e0 + 93 Np 239 93 Np 239 → −1 e0 + 94 Pu 239 (6) is an alpha emitter, which decays over time to none other than the other isotope of Uranium235
according to the reaction:
94 Pu 239 → 2 He4 + 92U 235 (7) By adding Eqns. 6 and 7, we obtain the very little known fact that nuclear reactors
convert the uranium isotope U238 into the isotope U235, releasing two electrons and a helium
nucleus as well as energy in the process: 7 0 n1 + 92U 238 → 92U 239 92 U 239 → −1 e0 + 93 Np 239 93 Np 239 → −1 e0 + 94 Pu 239 94 Pu 239 → 2 He 4 + 92U 235 (8) _____________________________
0 n1 + 92U 238 → 2 −1 e0 + 2 He 4 + 92U 235 Fig. 2: Decay of power production waste as a function of time. The U239, Np239 and Pu239 are nothing but catalysts, since they take part in the process but
do not appear as final products in the overall reaction.
Thus the nuclear fuel is extracted from a geological formation as U238 and is returned
back for long term geological disposal, in the form of U235 that is close to what was extracted
from the ground as U238 in the first place. 5.6 RADIATION EXPOSURE
The protection of the public against potential radiation exposure is the overriding concern
in radioactive waste disposal. The United Nations Scientific Committee on the Effects of
Atomic Radiation (UNSCEAR) was established in 1955 as a result of international concern
about the effects of fallout from atmospheric testing of nuclear explosions. It studies and
disseminates information on observed levels of ionizing radiation and radioactivity whether
natural or man made in the environment and on the effects of this radiation on man and his
surroundings. According to the UNSCEAR: “Surface and deep burial of solid wastes carried out
under control at suitable sites is expected to give rise to no significant public exposure.” 8 Fig. 3: Per capita yearly effective dose from different sources of radiation. At the request of USA’s President Jim my Carter in 1977, 66 countries and 5
international organizations participated in an International evaluation of the technical and
analytical aspects of the nuclear fuel cycle. One of the eight working groups concerned itself
with waste management and disposal problem in a study that lasted two years. The International
Nuclear Cycle Evaluation (INFCE) concluded that: “Employing technology as assumed, the
radioactive wastes from any of the fuel cycles studied can be managed and disposed of with a
high degree of safety and without undue risk to man or the environment. Figure 3 shows that in
fact the contribution of the exposure from radioactive waste is itself a small fraction of the
exposure due to natural radiation sources. 5.7 CLASSIFICATION OF NUCLEAR WASTE
Radioactive wastes are generally classified into four major categories:
High level waste: Consists of spent nuclear reactor fuel, and waste from fuel
reprocessing plants containing the bulk of the fission products. The main isotopes of concern
here are Sr90 and Cs137 with a half life of about 30 years. They also contain Zr93, I129 and Cs135 9 with half lives larger than a million years. Cesium137 decays into Ba137 and Sr90 decays into Y90
and then with a half life of 64 hours into Zr90.
Transuranic (TRU) waste: This is in the USA Department of Energy and Department of
Defense generated waste. It contains isotopes of plutonium such as Pu239 with a half life of about
24,000 years, with a specific activity concentration larger than 10-9 [Ci/gm].
Low Level Radioactive Waste (LLRW): Contains a specific activity concentration of
less than 10-9 [Ci/gm] of TRU nuclides or materials that are free of TRUs but still radioactive.
Based on the national average, three classes of LLRW are identified:
Class A: 97% of total.
Class B: 2% of total.
Class C:1% of total.
Uranium and Thorium Mine and Mill Tailings: These are residues from thorium and
uranium mining and milling. These contain primarily the isotope Radon222 of 3.8 days half life,
a member of the U238 decay chain. They also contain the isotope Pb210 with a half life of 19.4
years. When disposed of, these wastes must be covered with at least 3 m of earth.
Table 4: Long lived radionuclides used to classify radioactive wastes.
Radionuclide Activity density concentration
Carbon14 in activated metal
Nickel59 in activated metal
Niobium94 in activated metal
Alpha emitting transuranic nuclides
with T1/2 > 5 years. The Code of Federal Regulations (CFR) classifies LLRW waste according to its content
in long-lived radionuclides such as shown in Table IV.
The following four classes of waste are defined by the CFR:
Class A wastes: Includes materials containing nuclides with an activity demsity
concentrations less than 0.1 [Ci/m3] in Table IV. These must be segregated from other classes at
the disposal site.
Class B wastes: Are these wastes that meet requirements to ensure stability after
Class C wastes: Includes materials containing nuclides with an activity density
concentrations more than 0.1 [Ci/m3] in Table 4. These require stability plus measures at the
disposal facility against inadvertent intrusion.
Waste that is not acceptable for near-surface disposal. 5.8 WASTE MANAGEMENT PRINCIPLES
Tree general principles govern the process of management of radioactive wastes:
10 1. Dilute and disperse: wastes to environment in effluents containing radionuclides in amounts
below the authorized radiological limits. These have been set by the International Commission
for Radiological Protection (ICRP).
2. Delay and decay: those wastes which contain only short lived radionuclides.
3. Concentrate and confine: those wastes which contain significant amounts of long-lived
The management of low and medium level wastes is now a routine industrial operation.
They are disposed of in shallow ground and rock cavity repositories.
In the case of high level wastes there exists a great deal of experience in storing and
handling them. This started in the USA during World War II as part of the nuclear weapons and
defense program. The USA weapons program generated 0.2 million cubic meters in equivalent
solidified volume of high level waste or 700 times more than the 300 cubic meters from
commercial nuclear power plants. Civilian reactor waste in the USA reached just 10 percent of
volume of the military waste by 2000. To place the matter in perspective a typical 1,000 MW(e)
nuclear power plant produces just 30 metric tonnes of spent fuel per year.
By reprocessing this fuel, high level waste is separated and concentrated, reducing the
amounts to be disposed of. In fact, the technology for storage of high level waste both liquid and
solid is available and demonstrated. In France the vitrification process of high level waste from
a 1,000 MWe nuclear power plant produces just 2 cubic meters of high level waste per year. In
addition it is a better use of resources, since the unburned fuel in the fuel elements in the form of
fissile nuclides is used instead of being disposed of. Moreover, the transuranics formed are also
separated to be burnt producing energy instead of being stored for a long period of time. These
can be reloaded as fuel to reactors with a fast neutron spectrum to produce energy and be
transmuted to shorter lived fission products, in the process saving significantly on the waste
A single large reprocessing plant could service from 30 to 50 commercial nuclear power
plants of 1,000 MW(e) each. There exists only two commercial reprocessing plants in the world,
one at Sellafield , UK, and another at La Hague, France.
In France, all the high level waste produced between the years 1974 and 2000, with 20
nuclear power plants in operation in 1980, in solid form make up no more than the volume of a
standard Olympic size swimming pool. 11 Fig. 4: Spent fuel water storage pool at a reactor facility. 5.9 SPENT FUEL
Most of the highly spent fuel at nuclear power plants after usage in the USA is stored in
specially designed water pools at the reactor sites. They are left there temporarily to allow their
radioactivity to appreciably decay before being shipped out for either reprocessing in many
nations or for permanent disposal like in the USA, where it is expected to be shipped whence a
high-level Federal facility is available for permanent disposal. Such a fuel storage pool at a
reactor site is shown in Fig. 4.
At nuclear power reactor sites around the USA, 40,000 tons of spent fuel are placed in
fuel storage pools cooling off its radioactive emissions, awaiting permanent disposal. The fuel is
positioned within racks containing Boral which is an aluminum alloy with interspersed boron
carbide (B4C) particles. This ensures that the fuel in the pool, even with the presence of water
will not reach a critical condition.
Whereas the reactors themselves are surrounded by protective containment structures of 4
feet thick reinforced concrete, the storage pools are enclosed by corrugated metal structures. It
has been surmised that an accidental drainage of the water in the pools, by natural or man-made
events, could lead to melting of the stored fuel with a subsequent fire that could release the
radioactive fission products in the fuel. This release of radioactivity could contaminate, in a
worst-case scenario, about 188 square miles, as reported by a 1997 study by Brookhaven
National Laboratory. Reactor sites were not envisioned in the first place as permanent fuel
storage sites, so this should be regarded as just a temporary measure. 12 5.10 DISPOSAL OF WASTES
While the front end of the nuclear fuel cycle is mining of uranium from geological
formations, the back end is the permanent storage of these wastes in geological formations. The
following storage options have been considered at one time or the other in different countries
around the globe:
Storage in geological formations such as:
a) Salt beds
e) Volcanic tuff.
Seabed geological disposal
Polar ice sheet disposal
a) Very high Earth orbit
b) Solar orbit
c) Solar impact
d) Escape from solar system.
Economical and safety considerations have favored so far in the USA the terrestrial
disposal in volcanic tuff at the Yucca mountain site in the USA (Fig. 5). Fig. 5: Location of Nuclear Waste disposal site at Yucca Mountain, Nevada.
13 Fig. 6: Entrance of Nuclear Waste disposal site at Yucca Mountain, Nevada. Fig. 7: Storage scheme in the Yucca mountain storage facility. 1: Canisters of waste sealed
in special casks are shipped to the site by truck or train. 2: Shipping casks are removed and
the inner tube with the waste is placed in a steel multilayered container. 3: An automated
system sends storage containers underground to the tunnels. 4: Containers are stored along
the tunnels, either on their side as shown here, or standing upright in holes. Nuclear
Regulatory Commission (NRC) diagram. 5.11 YUCCA MOUNTAIN DISPOSAL SITE 14 A common sense alternative has been scientifically and technically studied for many
years at an expense of 7 billion dollars. A study completed in May of 2001 concluded that
nuclear fuel could be safely stored at the barren Yucca Mountain in the Mojave desert, shown in
Figs. 6 and 7, about 80 miles northwest of Las Vegas, in the Nevada desert. The spent fuel
would be safely stored there 1,400 feet under the 4,950 feet high mountain in volcanic tuff
deposits. Over a period of ten thousand years the radioactivity in the fuel would be reduced to
the same level as the uranium ore that was mined to manufacture the fuel in the first place.
The USA secretary of energy declared the site as “scientifically sound and suitable” as a
repository for spent reactor fuel stored at commercial reactors sites in 31 states and also for
nuclear waste generated from the government’s nuclear weapons program.
Numerous state governors, labor, business and policy groups support the use of the site.
On the other hand, the State of Nevada politicians fought the project and sued the USA’s
department of energy challenging its criteria for choosing the site. Some anti-nuclear groups
also fought the project because they see it as a way to block nuclear power.
The USA energy secretary, in notifying the governor of Nevada of the decision cited
“sound science and compelling national interest,” as well as growing concerns about the storage
of nuclear materials at the distributed reactor sites that need to be consolidated at a central site.
The 11,000 containers at the proposed Yucca Mountain nuclear waste storage facility
require 33 million pounds of molybdenum for corrosion resistance. The inner container would
be made of Type 316L stainless steel with 2.2 percent Mo, and nickel-base Alloy 22 with 13.5
percent Mo for the outer container. 5.12 LOW LEVEL RADIOACTIVE WASTE (LLRW)
Low Level Radioactive Waste (LLRW} is material which has been contaminated
by or contains short-lived radio nuclides or longer-lived radio nuclides in relatively low
concentrations. In the USA, LLRW is defined by law by what it is not. It is not
supposed to be:
1. Spent fuel from nuclear reactors,
2. High-Level waste,
3. Transuranic waste,
4. Uranium or thorium mill tailings,
5. Naturally Occurring Radioactive Material (NORM).
Many societal activities could generate LLRW. These include:
1. Nuclear power plant operations,
2. Diagnostic and nuclear medicine applications,
3. Industrial processes and activities,
4. Academic institutions and research,
5. Governmental applications,
6. State agencies with radioactive material,
7. Military installations. 15 The distribution by volume and by activity of LLRW generated by these sources
is shown in Table V.
Three operating LLRW facilities exist in the USA:
1. The U. S. Ecology Facility in Richland, Washington.
2. The Envirocare Facility in Clive, Utah.
3. The Chem-Nuclear Facility, Barnwell, South Carolina.
The disposal of LLRW can be done either in engineered trenches below ground level as
in Fig. 8, or in above surface facilities as shown in Fig. 9. Fig. 8: LLRW Engineered disposal unit design. 16 Fig. 9: Above ground level assured isolation conceptual design.
Table 5: Distribution by volume and activity of operational LLRW generation.
100 17 Activity
100 Fig. 10: Spent fuel transportation cask. 5.13 TRANSPORTATION
The transportation of the fuel to the disposal facilities is carried out in specially designed
canisters which have been designed and tested to withstand fires, collisions, drops and a
multitude of possible accidents (Fig. 10). 5.14 EXPERIENCE WITH RADIOACTIVE WASTE
Knowledge about transuranic waste storage has already been accumulated in the handling
of the wastes generated by the USA Department Of Energy in its nuclear weapons program are
stored in a salt dome formation at the Carlsbad, New Mexico, Waste Isolation Plant WIPP (Fig.
11). 18 Fig.11: Storage scheme in the Carlsbad, New Mexico Waste Isolation Plant WIPP
transuranic waste salt repository. Fig. 12: The Asse salt mine in Germany in operation since 1967 at 750 meters depth. The Asse salt mine in the Federal republic of Germany, which is 750 meters deep has
been used since 1967 as an experimental facility for the development of methods and techniques
for the safe disposal of low and medium level wastes with long lived radio nuclides. Salt
formations are extremely stable. The Asse salt formations have remained undisturbed for over
100 million years and likely to continue to exist for the time required for the radioactive wastes
to decay (Fig. 12).
Glass is favored in France as a material for the solidification of high level wastes which
combine well with the standard ingredients used in glass making. Vitrified waste glasses like
Pyrex are very stable with good resistance to heat, chemical action, radiation as well as
mechanical stress. Even in flowing warm water at a temperature of 40 degrees Celsius, it would
take 100 years to dissolve away just 1 millimeter of the surface of the glass. The vitrified waste
would still by then be sealed in corrosion resistant stainless steel containers (Fig. 13).
Since ground water is likely to be saline, it is proposed that 10 cms of lead and 6 mm of
titanium would be added as an extra cladding on the outside. The solution rate of titanium in
flowing saline water at ambient temperature is 0.0013 mm per year. Thus, although the
19 temperature is likely to be around 60 degrees Celsius, dropping to the ambient level in about 100
years, the titanium layer is likely to last at least 4,000 years. It is known that Roman lead articles
survived in the salty water of the Mediterranean Sea with little loss so that the 10 cms lead clad
should last longer still. Fig. 13: Waste container design. Those waste containers (Fig. 13) would be initially stored over the first 30-50 years in
water ponds or air cooled storage at the reprocessing plant (Fig. 15). After the heat output would
have declined appreciably the containers could be loaded into boreholes in rock formations
where natural cooling would be sufficient to dissipate the heat generation.
The repositories would be excavated in deep geological formations hundreds of meters
below ground level, and well below the water table. 20 Fig. 14: Cut away of a waste container containing vitrified high level waste at the Marcoule
plant, France. Fig. 15: Experimental storage wells for vitrified waste containers at the Marcoule plant in
France. 21 Fig. 16: Swiss design of casket for storage of BWR reactor spent fuel elements. In addition to the waste glass and its container other engineered barriers can be added to
assure waste containment for more than an admittedly arbitrary chosen period of 1,000 years,
even in the presence of corrosive ground water. Synthetic rock or synrock has been also
suggested as an alternative disposal matrix. Once the containers are emplaced in the repositories,
the access tunnels will be filled with rocks and sealed, effectively preventing movement of the
radionuclides to the human environment. The engineered barriers and the natural geological
barriers combine to return to the Earth what was earlier mined from it. 5.15 SUBSURFACE PLANAR VITRIFICATION
In subsurface waste vitrification, two solid graphite electrodes about 30 feet in length are
inserted into the ground in proximity to a waste containing shaft. Four megawatts of power are
delivered to these electrodes. A four foot tall sheet of graphite flake is pressure injected between
the electrodes providing a current path. When current is passed between the electrodes for seven
to ten days at a temperature of 1,700 degrees C, any waste and its surrounding is melted into a
glass composition. 22 Fig. 17: Subsurface vitrification using graphite electrodes. The waste containing shaft is capped with a containment hood preventing the electrodes
from moving once the melting process is started, and captures any radioactive fumes to a
filtering system. When the electrical current is stopped, the resulting gel cools into a solid glass,
encasing any waste for a long period of time. The glassy material would eventually be dug out
and disposed of at the Carlsbad, New Mexico government waste disposal site. This technique
has been developed for use at the Hanford Nuclear reservation in the state of Washington. 5.16 RADIATION PROTECTION STANDARD
MOUNTAIN, DELAY AND AVOIDANCE FOR YUCCA On June 6, 2001, the USA Environmental Protection Agency (EPA) announced
the radiation protection standards to be used for Yucca Mountain, Nevada, the site of
proposed high-level nuclear storage.
The final public health and environmental protection standards for Yucca
Mountain was set at 0.015 cSv or rem per capita per year and 0.004 cSv or rem for
groundwater. This is also referred to as the 15 mrem standard. 23 This represented the end of a struggle between the EPA and the Nuclear
Regulatory Commission (NRC), which had recommended an overall limit of 0.025 cSv
or rem per capita per year and no groundwater standard.
Energy Secretary Spencer Abraham, at the time, who had favored the NRC
proposal, said on June 6, 2001, that the EPA standards were "tough and challenging" but
that "we believe we can meet the requirements."
The nuclear industry, represented by the Nuclear Industry Institute filed two
separate federal court lawsuits. One was filed in USA District Court and the other in the
USA Court of Appeals for the District of Columbia Circuit, challenging the EPA standard.
Stating that the industry "is extremely disappointed," the trade association said that the
lower limits "will cost taxpayers and electricity consumers billions of additional dollars to
license and build the Yucca Mountain repository without making the facility any safer."
In September 2008, the EPA revised its standard of a waste repository that for the
first 10,000 years possible future residents should not be exposed to more than 15
mrem/year of effective dose, to the requirement that from year 10,001 to one million years
the dose equivalent should not exceed 100 mrem/year. According to the EPA, the new
standard “will protect public health and the environment for 1 million years.”
To express the strictness of the EPA so called 15-millirem per capita per year
standard, the EPA stated that the standard means that a person living eleven miles from
the Yucca Mountain site, the distance to which the standard applies, will absorb less
radiation annually than a person receives from two round-trip transcontinental flights in
the USA. The EPA also stated that background radiation exposes the average American
to 360 millirems of radiation annually, while three chest x-rays lead to a total dose
equivalent of about 18 millirems.
There is no way to prove that Yucca Mountain can meet the standards established
by the EPA. Any models or simulations can be questioned and can provide the grounds
for controversy. Arguing and delaying are ways to mine the tremendous amounts of
money associated with the project.
The real answer to the problem is to recognize that radiation is a natural part of
the natural environment and that humans have evolved the ability to cope with small
amounts without health risk.
The level at which no risk can be found is roughly 10 cSv or rem over a short
period of time. This is fully 10 / (15 x 10-3) = 666 times the EPA unrealizable standard of
15 mrem. At significantly higher lifetime exposures demonstrated by many population
studies in areas of high natural background radiation, the health risk is very low
compared to that from other environmental influences.
The Yucca Mountain project is based on legislation dating back to 1982, and
cannot be stopped by presidential fiat. The USA Department of Energy submitted an
application to the Nuclear Regulatory Commission in September 2008 to license Yucca
Mountain. This process is expected to last 3-4 years and includes passing judgment on
the one million-year safety standard. The facility is expected to open in 2020 at the
earliest, more than 20 years behind schedule to store 70,000 tons of spent nuclear fuel; a
blink of an eye on the geological time scale. 5.17 ACCELERATOR DRIVEN ENERGY AMPLIFIER
24 The favored option is to store the treated and vitrified waste in deep geological
repositories. Accelerator driven transmutation is a possible alternative.
The basic concept is to place the radioactive material in an accelerator and
transmute it up into much more stable products, with shorter half lives using a beam of
high energy subatomic particles such as protons.
The waste would still need to be stored, but would be less hazardous. The process
of transmutation would eliminate other biologically toxic chemical products that exist in
normal nuclear waste.
The process could also generate more energy than is used to drive it. The heat
generated by splitting the waste nuclei can be used to generate electricity, a part of which
being used to run the accelerator and the rest fed into the electrical grid.
A fail safe mechanism is that when the particle beam is turned off, the reaction
stops. This is characterized as an energy amplifier; an idea existing since the 1990s.
France has a program of research looking into accelerator transmutation. There
are also initiatives in the USA, Russia, Switzerland, Italy and Japan. The difficulty is that
we still do not know exactly what the final transmutation products will be, and in what
Experts argue that while transmutation is a feasible future technology, there are
several other options available too. A fast breeder reactor would reuse the nuclear fuel
over and over again until all the plutonium the minor actinides are burned up. Another
option is to use the thorium fuel cycle which produces less minor actinides. 5.18 DISCUSSION
Nuclear Power has been compared with Gulliver in the land of Lilliput, tied down
by thousands of threads and ropes stifling its motion and progress into the future.
In a thermal neutron reactor less than 2 percent of the actinides are actually
fissioned. The dispensed fuel still has an energy value of one terawatt-day/metallic ton.
This energy is only accessible with fast neutron or breeder reactors.
Recycling of nuclear waste reduces its volume by 97 percent. In the end it is safe
to handle in about 300 years and there is no need to invoke the process of forecasting a
million years into the future or even 10,000 years.
More than 1.7 billion years ago 15 nuclear reactors operated in nature for over a
period of 100,000 years at the Oklo site in the Gabon Republic in West Africa.
Plutonium as a transuranic element was produced in the six reactive zones. This
plutonium did not move away from the reaction zones and decayed slowly into U235. The
same happened to the fission products in that they remained at the reactions sites and did
not leach away. This natural phenomenon should allay the concern about the ability of
storing nuclear wastes in suitable underground formations.
The virtue of using solids like glass or synthetic rock (synrock) for holding
materials for long periods of time is obvious from the occurrence of fossilized insects in
perfect preservation in amber for millions of years. Frozen mammoths have been
discovered in glaciers preserved for over 30,000 years. The Egyptian tombs and
pyramids have stood the test of time. Ancient objects made out of glass still remain in
perfect condition today dating back 3,000 to 4,000 years from the early known
25 As expressed by A. Gauvenet from Le Commissariat à L’Energie Atomique
(CEA) in France: “The advantage of going to depths of hundreds of meters is that in
inactive parts of the Earth’s crust the geological structures and materials remain stable for
millions of years. It is therefore already possible to guarantee that we are not
bequeathing to future generations a higher radioactivity than that which our Earth
contains naturally.” EXERCISES
Calculate the amount of uranium as a mixture of U235 and U238 used by a 1,000
MWe nuclear power plant in a year period if its enrichment is 5 percent in U235 per
weight, the thermal efficiency is 1/3, and the operating capacity factor of the plant is
Calculate the amount of fuel in the form of UO2 at a density of about 10.1 [gm/cm3]
used by the same power plant in the last problem.
The uranium fuel requirement for a fission reactor operating at a capacity factor of
75 percent is 30 metric tonnes.
The U235 burnup rate is given
by: burnup rate= 1.112 P [
Estimate the ratio of the weight of the fuel to be disposed of in the case of the once
through fuel cycle, to the weight of the fission products in a fuel cycle with fuel recycling
for a 1,000 MWe nuclear reactor operating at an overall thermal efficiency of 1/3. REFERENCES
Howard Hayden, “On being proud of nuclear waste,” Nuclear News. P.41, May
USNRC, “NRC Regulator of Nuclear Safety,” NUREG/BR-0164, Rev. 4, Nov.
10CFR60, “ Disposal of High Level radioactive Waste in Geologic Repositories,”
in: “Code of Federal Regulations,” Energy, Title 10, Parts 0-199, 2003.
10CFR61, “Licensing requirements for land disposal of radioactive waste,” in:
“Code of Federal Regulations,” Energy, Title 10, Parts 0-199, 2003.
WHO, World Health Organisation, “Nuclear Power: Health Implications of High5.
Level Waste Management,” WHO Regional Office for Europe, Copenhagen, Denmark,
UNSCEAR, United Nations Scientific Committee on the Effects of Atomic
Radiation, “Sources and Effects of Ionizing Radiation,” Report 1997, vol. 1, 1977.
INFCE, International Nuclear Fuel Cycle Evaluation, “Working Group 7,” 1980.
7. 26 ...
View Full Document
- Spring '08