By
fall 1986, the measurements conducted by a number of scientific research
institutes, state hydrometeorology services made it possible to estimate the
fuel component release. The fuel component release was 3+/- 1.5% of the total
pre-accident core fuel. These figures
for the fuel component fallout (deposits) were subsequently confirmed by the
analysis of thousands of soil samples: 3.5+/- 0.5%.
However,
the results for the volatile components were quite different. The 137Cs release was estimated to be 20% of the
total accumulated activity (which was 2.6 x 1017 Bq), while the 131I release was 30% of the total
accumulated activity.
Quantitative
Estimate of Nuclear Fuel Modifications Inside the Shelter. Studies conducted
between 1986 and 1995 demonstrate that the irradiated nuclear fuel in the
Shelter (Sarcophagus) exists in four modified forms:
–
core fragments
–
fuel particles or radioactive dust
–
solidified lava-like fuel-containing material
–
dissolved forms of certain
radionuclides.
Fuel distribution
data are presented in Table 2-1. However, currently available information
cannot be used to complete a quantitative mass balance for the core. This will
require additional research. Only an upper and lower boundary on this value can
be determined.
Table 2-1. Distribution of Fuel-Containing Material by Shelter
Room/Location
|
Room/Location (elevation) |
FCM Classification and State |
Estimate of Fuel Content of FCM (in metric tons of
uranium) |
|
Central hall (35.50) other upper unit locations |
Core fragments
(the majority are saturated with materials ejected during the active stage of
the accident; lava-like FCMs may be located
underneath the material) In the vicinity
of System E - 10 - 36 |
60–70 |
|
Southern spent fuel pool (18.00-35.50) |
Spent fuel
assemblies |
~20 |
|
Majority of locations |
Fuel dust. Hot
fuel particles |
~10 |
|
Subreactor locations
305/2 (9.00) + 307/2 + System OR + reactor vault |
Lava-like FCMs, core fragments |
75 |
|
Steam distribution
corridor (6.00) allowing for FCM in the valves |
Lava-like FCMs |
25+/-11 |
|
Second level pressure
suppression pool (PSP-2) |
Lava-like FCMs |
8+/-3 |
|
Level 1 pressure
suppression pool (PSP-1) |
Lava-like FCMs |
1.5+/-0.7 |
|
304/3, 304/3, 304/3,
304/3, “Elephant’s Foot”, etc. |
Lava-like FCMs |
11+/-5 |
|
Reactor unit, reactor
building auxiliary system and Turbine Hall locations |
Water with dissolved
uranium salts |
~3,000 m3 water < 3 kg uranium |
|
Fuel under cascade wall |
Core fragments |
Not identified |
|
Fuel at site under
concrete and crushed rock layer |
Core fragments,
fuel dust |
+0.3 0.6+0.3/-0.2 |
|
FCM = fuel-containing
material. |
||
The majority of the core fragments were ejected during the explosion into the upper stages of the unit, specifically, into the central hall. The finely dispersed fuel (dust) is made of hot fuel particles that vary in size from fractions of a micron to hundreds of microns. The fuel dust can be observed in virtually all locations throughout the facility. Solidified lava-like fuel-containing material was formed during the active stage of the accident (26 April–6 May 1986) from the high-temperature interaction between the fuel and structural materials of the unit. The lava-like material spread into the subreactor locations. In 1990, scientists discovered that water located in a number of the lower areas of the facility contained dissolved forms of uranium, plutonium and americium. These soluble compounds were caused by the breakdown of a variety of compounds created from the uranium dioxide fuel under multiple factors, the primary such factor being the water that penetrated the Shelter.
Core
Fragments. Significant
quantities of isolated core fragments and accumulated fragments were observed
around the destroyed Unit 4 reactor immediately following the accident. Fuel
assemblies, fuel elements, and isolated parts of these components were ejected
by the explosion onto the vent stack, the roofs of the deaerator
mezzanine, the turbine hall, and the reactor building auxiliary systems as well
as the roof of Unit 3 structures and in the central hall. Some of the fragments
were remediated following the accident. However, the
majority of the fragments were not remediated. Researchers have performed several studies to
determine the location of the fragments.
Several
methods were used during accident remediation to deal with core fragments. Some
of the core fragments from the site were moved to the debris pile and were
buried in the cascade wall. Other core fragments were placed into containers
with highly radioactive waste or were buried under the concrete and crushed
rock layer surrounding the building. Some of the core fragments located on the
roofs of buildings and the vent stack were discarded into the collapsed area of
the building. Finally, a small quantity of core fragments remained on the vent
stack areas and on the roofs.
The
majority of the core fragments are probably in the reactor central hall.
However, the material dropped by helicopter to put out the reactor core fire
makes it impossible to directly observe significant accumulations of core
fragments. Nonetheless, indirect facts such as the nature of the explosion, the
large number of fragments ejected onto the roofs and around the reactor building, and the likely trajectories of the core fragments
are consistent with this hypothesis. It is also confirmed by the rather
significant number of fragments observed in the northwest and western sections
of the central hall.
A
comparison of the gamma-scanning data to the video and later photo survey data
suggests that the majority of the fuel is located in fuel channel remnants on
the surface of System E. Approximately 1 metric ton of fuel is located on the
walls of the central hall and other structural elements outside System E.
Efforts
have also been made to assess the location and states of nuclear fuel in the
spent fuel pool and new fuel storage areas. Periscopic
observations and video surveillance revealed that the panels containing
fuel assemblies in the southern spent fuel pool continued to be suspended in
their expected locations after the accident without noticeable damage.
Periscopic and video surveys revealed core fragments in the
reactor vault. These core fragments were located on System OR. The number
of such fragments is difficult to determine because of the collapse of the
graphite masonry and concrete that was added to the shaft following the
accident.
Approximately
10 accumulations of core fragments were discovered through visual surveys in
the subreactor area. It is noteworthy that intact
fuel pellets (uranium dioxide) from this location were identified from samples
of the lava-like fuel-containing material indicating that there was a very
broad range of temperatures in the area following the accident.
As
the core fragments represent the most hazardous form of nuclear material from
an occupational and environmental safety viewpoint, a conservative estimate,
i.e., the upper limit on the quantity of this fuel modification, should be
used. The total pre-accident uranium mass in the core, the southern spent fuel
pool, and the central hall is estimated at 212 metric tons (this is a maximum
value, neglecting any fuel assemblies removed from the fuel preparation area),
while the uranium mass of the lava-like fuel-containing materials and fuel
particles is estimated at 80 metric tons (the minimum value). The difference
between these values (132 metric tons) after subtracting the ejected fuel (6
tons) is equal to 126 metric tons. This value represents an estimated upper
limit on the uranium mass in the form of core fragments.
Fuel
Particles or Radioactive Dust. A fairly large number of studies have been
devoted to analyzing the physical and chemical composition of the radioactive
dust (also called fuel particles or finely dispersed fuel) in various locations
throughout the Shelter.
Calculating the
total amount of finely dispersed
fuel on the
surface of the central hall
debris and other open surfaces
under the roof of the
Shelter provides a conservative estimate, resulting in an
order‑of‑magnitude value
of 34 metric ton. Other efforts to
calculate the amount of radioactive
dust in other
shelter locations have been based
on measurements of the dose
exposure rates in these locations.
These calculations assumed that in
those areas lacking noticeable quantities of core
fragments or “fuel lava,” the
dose exposure rate was determined
by the uniform
layer of active dust remaining
on the walls,
floors, and ceiling of the
room location.
Soluble
Fuel Forms. For some time, it was believed that none of
the compounds created from the uranium dioxide fuel during the accident were
soluble. However, in September 1990,
bright yellow spots and pools were discovered on the surface of solidified lava
flows in the steam separation corridor.
Analysis of these spots revealed the presence of soluble uranium compounds.
X-ray phase and microstructure analysis revealed the following compounds:
–
UO3 . 2H2O Eliantinite
–
UO3 . 16CO2 .
1.19H2O Studitite
–
UO4 . 4H2O
–
Na(UO4)2(CO3)3
The plutonium isotope content in these new formations is hundreds of times lower while the mass concentration of uranium is several times greater than in the lava-like fuel-containing materials.
Lava-Like
Fuel-Containing Materials. The
high temperatures associated with the accident melted the zirconium fuel
cladding and led to an interaction between the molten zirconium and the uranium
dioxide, resulting in a uranium-zirconium-oxygen phase. When this phase
interacted with structural materials (serpentine, concrete and sand) as well as
air, lava-like fuel-containing materials were formed.
Researchers
working at Chernobyl NPP Unit 4 encountered this lava-like fuel-containing
material for the first time in the fall of 1986. Subreactor
location 217/2 was found to contain a large solidified mass, approximately 1 m
wide that came to be called the Elephant’s Foot (Figure 2.2-1). Analysis of the
Elephant’s Foot revealed that it consists primarily of silicon dioxide with
other compounds as impurities, including uranium compounds. The mixture of radionuclides
found in samples of the Elephant’s Foot match those found in the irradiated
nuclear fuel with an average burnup for Unit 4.

Figure 2-1. Elephant’s Foot, a lava-like fuel-containing
materials formation
Lava-like
fuel-containing materials were subsequently discovered in many
subreactor room locations. This material contains significant amounts of pre-accident uranium from the
reactor core and a significant number of reactor
radionuclides.
Formation and dissemination of the lava-like fuel-containing materials: the heat in the reactor core during the accident and afterwards may have melted portions of the uranium dioxide fuel and other materials in the core. The precise sequence of events that created the lava-like material is unknown. However, researchers do know the lava remained heterogeneous – much of the structural metal retained its composition while the ceramic mass interacted with structural materials as it flowed.
The melted materials formed into a larger mass. As the mass of the melt increased, it spread along the floor of location 305/2, reached the edges of the steam relief valves, migrated downward through the valves, and passed into the upper and lower portions of the Suppression Chamber, part of the confinement systems designed to isolate steam in a design-basis accident. These locations include the steam distribution corridor and two levels of the pressure suppression chamber, which are located at elevations 6.00, 3.00 and 0.00, respectively.
The
melt could also flow horizontally, since a breach (or a burn-through hole––this
is not known precisely) formed in the wall between locations 305/2 and 304/3.
–
black ceramic with 4-5% uranium concentration by
mass
–
black ceramic with 7-8% uranium concentration by
mass
–
brown ceramic with 9-10% uranium concentration by
mass
–
slag and pumice-like
fuel-containing materials.
Figure 2-2 is a histogram of the percentage uranium for the lava‑like fuel-containing material (based on data from 225 samples), while Figure 2.2-3 is a histogram of the fuel burnup for the lava‑like materials.

Figure 2-2. Fuel content (as
U) in pure lava

Figure 2-3. Fuel burnup in
lava-like fuel-containing material samples
–
surface decomposition of the lava-like materials and
the formation of radioactive dust on these materials
–
leaching of radionuclides
from interaction between the “lavas” and water, and the formation of new
chemical compounds on their surfaces
–
matrix cracking due to
interior stresses.
An
initial attempt to take a sample of lava-like fuel-containing material from the
Elephant’s Foot demonstrated its significant strength; small weapons were
required to separate a sample from surface of the formation in 1987. Repeat
sampling from the Elephant Foot, beginning in 1990, no longer requires
significant effort. Attempts to remove surface contamination from the
Elephant’s Foot, by means of a glue-treated wad, easily separated an upper 1-2
cm layer. At present, the lava
degradation processes have caused the Elephant’s Foot to nearly lose its
initial shape, to slide down and settle. According to observers, the lava-like
fuel-containing materials at room locations 304/3, 305/2, etc. have undergone
similar changes.
Processes
leading to lava-like fuel-containing material embrittlement
have not been the focus of special study. The most likely mechanism is
associated with cooling of the lava-like materials and their impregnation with
water: observations have revealed that the temperature of even small lava-like
materials differs only slightly from the ambient air temperature. In winter,
freezing water in the pores and microcracks of the
lava-like materials may lead to their cracking. Moreover, microscopic analyses
have revealed the severe inhomogeneity of the
lava-like materials on the microlevel. Interior
stresses caused by differences in the coefficients of thermal expansion of the
components may arise as the temperature of the lava-like materials decreases
substantially below the fuel-containing material solidification
temperature. Because of the
heterogeneous quality of the lava-like fuel-containing material, the
coefficient of thermal expansion and even melting temperatures can vary significantly. Given this situation and the uncontrolled
rate at which the lava-like fuel-containing material cooled, there are
significant residual natural stresses that can accelerate the degradation of
the material.
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