Radioactive Wastes B.S. Choudri1*, Yassine Charabi1, Mahad Baawain2, Mushtaque Ahmed3
ABSTRACT: Papers reviewed herein present a general
Safety Assessment. Jeong et a., (2016) performed a
overview of radioactive waste related activities around the
radiological safety assessment for the transportation of low
world in 2016. The current reveiw include studies related to
level radioactive wastes that are stored temporarily in the
safety assessments, decommission and decontamination of
Korea Atomic Energy Research Institute. The results of
nuclear facilities, fusion facilities, transportation. Further,
this study showed the effective doses are far below the
the review highlights on management solutions for the final
regulatory limits for transport personnel, radiation workers,
disposal of low and high level radioactive wastes (LLW
and the general public. Further, this study indicated a
and HLW), interim storage and final disposal options for
secure safety for all situations during the transportation of
spent fuel (SF), and tritiated wastes, with a focus on
radioactive wastes from the view point of radiological
environmental impacts due to the mobility of radionuclides
safety.
in ecosystem, water and soil alongwith other progress made in the management of radioactive wastes.
Integrated with more details on sociotechnical vision that transcends the active versus passive safety division provided by Schroder et al., (2016). Authors have
KEYWORDS: radioactive waste, disposal, repository,
described and analyzed the ambiguity of this seemingly
transport, waste form
straightforward approach to safety which are drawn based on constructivist insights from safety science and
doi: 10.2175/106143017X15023776270539
technological studies. Authors have the word oversight, currently which has been popular in international radioactive
waste
management
and
considered
as
—————————
sensitizing concept that provide opportunity to elaborate
1*Center
such an integrated vision.
for Environmental Studies and Research, Sultan Qaboos
University, Sultanate of Oman; 2Department
e-mail:
[email protected]
of Civil and Architectural Engineering, College of
Engineering, Sultan Qaboos University, Sultanate of Oman. 3Department
Jeong et al., (2016) developed a system called total performance assessment program using Goldsim to check the design feasibility of advanced Korean reference
of Soils, Water and Agricultural Engineering, College
disposal system. This disposal system is a reference of Agricultural and Marine Sciences, Sultan Qaboos Univeristy, Sultanate of Oman.
repository system for the disposal of radioactive wastes
1487 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
resulting from the pyroprocessing of spent nuclear fuels.
(2016).
Authosrs in this study found that the exposure dose rates
accident of the K-27. In order to study the hypothetical
for the case of multi-lattice source term model was much
activity a long term meteorological database has been
lower than those for the case of single source term model.
prepared. Authored studied for selection of the worst case
In another study these authors suggested a system for
meteorological scenarios for three locations of the possible
evaluation on the hazards from human errors during
accident. Based on the simulations, authors concluded that
decommissioning of nuclear facilities. This system will be
deposition of worst-case scenario of a hypothetical K-27
utilized as a training tool for improving familiarization of a
accident would be at least in the order of two magnitude
workplace and for preventing workers from possible
which is lower than the deposition observed in Norway.
accidents.
This study considered a hypothetical criticality
Sen et al., (2016) reported a study on numerical
Transport of Radioactive Waste. An isotope dilution
migration of radioactivity in view of a space dependent
mass spectrometry U-series measurements for fracture-fill
flow field. Authors considered, seven different types of
materials studied by Denton et al., (2016). Authors
velocity profiles and the corresponding concentrations were
condudcted a study on the Nopal I uranium ore deposit
compared. Results of this study showed at a constant value
situated at Peña Blanca of northern Mexico. Study showed
of velocity causes more concentrations within shorter
high uranium concentrations in the fracture-fill materials
distances and vary spatially in velocity function which
and indicated uranium mobility during the process of
reduce concentrations at the lower distances and at larger
transport. Further, results indicated uranium decrease in
deistances increased concentration.
concentrations by horizontal distance away from the
Decommission
deposit and within the deposit there is no trend with
Facilities. Jeong et al., (2016) condudcted as study on
resepect to depth from the surface.
virtual decommissioning environments in order to evaluate
Seher
et
al.,
(2016)
investigated
and
Decontamination
of
Nuclear
the
the working times. The data measured are analysed
decommissioning waste for the flow and transport
statistically focused on the mean, variance work time and
processes in generic landfills. According German technical
radiation exposure dose. Authors concluded that this study
standards of Landfill Ordinance, the generic landfills
will improve the knowledge on decomissionining of
comply with the standards. Simulations performed on
nuclear facilities and make it possible to efficiently
contaminant transport show that Sr-90 is the first
establish as low as reasonably achievable plan for
radionuclide that leaves the landfill due to its low sorption
decommissioning of nuclear facilities around the world.
in the waste body. Assessed
A method to improve the inefficiency of the the
atmospheric
transport
of
existing process simulation provided by Kim et al., (2016).
radionuclides and deposition in Norway by Bartnicki et al.,
Authors have designed a flexible cutting simulation
1488 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
framework that included a methodology of detailed cutting
tritium facility taking in to account needs of producers,
product generation. Further, this method has been
analysis of safety at facility and the requirements of
implemented by the authors using a system of commercial
disposal. It is concluded that the results of this study would
process simulation. This study concluded that the proposed
help operator of nuclear plants to ensure the compliance of
methodology help users in order to avoid a creation of
the future waste management strategies in order to match
result cut-model before the process of following procedure
the criteria of disposal acceptance.
of modeling.
Desorption and enrichment of tritiated water from
Slimak and Necas (2016) analyzed the possibility
organic functionalized mesoporous has been investigated
of scrap metal decontamination by melting it as part of
by Taguchi et al., (2016). Results of this investigation
waste management strategy. Authors considered nuclear
showed that desorbed water was lower in concentration of
power plants located in the Slovak Republic which are
tritiatixum measured than that in the aqueous solution used
being decommissioned and used the melting technology a
for impregnation. Further, the study showed that the
suitable decontamination technology for reduction of
behavior of desorption of tritiated water was mostly
metallic radioactive. Restults of this study indicated that
dependent on the nature of the organic material present in
radiological impacts are at relatively low level and use of
the tritiated water.
melting technology can save significant amounts of steel materials and associated costs.
Furuichi et al., (2016) proposed a simple model called tritium transport which is developed based on the
Shaukat et al., (2016) proposed a machine vision
transport of tritium in the materials having porosity. Mass
system for autonomous identification of waste material
transfer coefficient of isotope exchange showing reaction
arising from decommissioned nuclear plants. Authors used
between tritiated water and structural water in particles of
rotation and scale invariant moments to describe shapes of
soil was considered. The process was obtained by
objects in the visual scene by incorporating a random forest
numerical analysis as a result of percolation experiment of
learning algorithm which performs object classification.
tritiated water into bed of soil. The mass transfer capacity
Further, with the help of simulatns from nuclear waste, an
coefficients of isotope exchange reaction between tritiated
assessment of proof-of-concept quantitative of the proposed
water percolations through the packed bed shown to be 6.0
technique was performed to check the test and its
× 10-4 1/s.
applicability.
Chinese Helium Cooled Ceramic Breeding Test
Tritiated Waste Management. Decanis et al., (2016)
blanket Module was studied by Chen et al., (2016). Authors
provided detailed and step by step method that has been
conducted this test in the thermonuclear experimental
implemented to define the waste acceptance criteria. This
reactor machine for the feasibility of tritium production for
approach was used by authors for an interim storage of
a future. In addition, the amounts of tritiated radwaste were
1489 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
also determined considering various process such as
spectroscopy. This study provided a valuable results into
operation, decommission, maintenance and strategies of
poorly understood contamination in infrastructural systems.
replacement. This study concluded that conclude that data
Further, results of study are most applicable to the efforts
obtained from this experiment can be used for evaluation of
and activities of United Kingdom’s nuclear decommission.
the tritium radiological safety as well as radioactive waste
Martinik et al., (2016) studied key components of
management of Chinese Helium Cooled Ceramic Breeding
the Differential Die-Away (DDA) associated instrument.
that includes associated ancillary systems.
Further, authors have proposed a method for evaluation and
Spent Nuclear Fuel Management. Christian and Kang
selection of the most relevant design parameters in order to
(2016) proposes a method for Spent Nuclear Fuel (SNF) in
optimize the performance for a given particular application
order to assess and reduce risks originating from ship
which includes assay of spent nucler fuel assemblies that
collisions with a probabilistic approach. Case studies of
form both pressurized and boiling water reactor type.
collision are presented by using reference models of the
Management of TENORM. ALNabhani et al., (2016)
SNF package such as the struck and striking ship. It is
highlighted the importance disposal sites having TENORM
concluded that methodology was useful in improving
that are subsequently developed. Authors have stressed to
decision
consider the importance and the role of public participation
making
process
of
spent
nuclear
fuel
transportation by ships in order to minimize possible risks.
by striking a balance between the interests of the authorities
González-Robles et al., (2016) presented a study
and stakeholders towards management of radioactive
on fission gas release from spent nuclear fuel. In this study
wastes. Further, authors have also presented an analysis of
authors have exposed fission gas to simulated groundwater
TENORM waste disposal options and risk assessment
and compared with the fission gas earlier released to the
methods that are commonly used in the oil and gas
fuel rod plenum in the reactor during irradiation. Study
industry. A real case scenario of TENORM waste disposed
conducted the krypton (Kr) and xenon (Xe) inventories in
in an evaporation pond has been considered. Simulated
the plenum by means of a puncturing test and experiments
results have been compared with results obtained using a
of leaching. It was found that relatively high release of
similar results available in the literature.
fission gases casued by the increased accessibility of water
Effect of Material Corrosion. Deyab et al., (2016)
to the krypton and xenon present in the fuel.
evaluated NaNi (H 2 PO 3 ) 3 ·H 2 O (NaNiPh) which has been
A radioactive coated concrete core from the
considered as a new inorganic inhibitor for radioactive
decommissioned spent nuclear fuel cooling pond at one of
waste container corrosion. The evaluation is done in the
the nuclear site in United Kingdom was studied by Bower
Callovo-Oxfordian groundwater with the help of techniques
et al., (2016). In this study, authors conducted chemical
such as potentiodynamic polarization and electrochemical
analysis of the core with the help of microfocus
impedance spectroscopy. This study highlights that
1490 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
corrosion activity is mainly inhibited by physical
were similar to the results repoted by others for engineered
adsorption of NaNiPh on surfacr of carbon steel and
barrier systems given the same chemical conditions.
follows the Langmuir isotherm model adsorption process.
Impact of Radiolysis. Moncoffre et al., (2016) assessed
The effects of steel corrosion on the thermal,
the gas radiolysis and radiolytic corrosion induced by γ or
hydraulic and mechanical (THM) response was studied by
He2+ irradiation effects at the gas and graphite interface to
Jia et al., (2016). The response study was conducted on the
evaluate their role on release of radionuclide. This study
geological barrier by simulating a disposal tunnel of high
showed that experiment results allow radiolytic corrosion
level radioactive wastes. Results of numerical analysis
to promote the release of 14C,
shown the influence of steel corrosion on the THM.
the graphite brick and gas interfaces as well as open pores.
36
Cl and 14N by inferring at
Further, the study showed the response of claystone is
Low Linear Energy Transfer (LET) radiolysis
limited in the near field tunnel disposal for the factors such
escape yields (G values) for the sum (G (H) +G (e-) aq ) and
as displacement and stress fields in the claystone.
for G (H 2 ) in subcritical water up to 350 °C was studied by
Crum et al., (2016) developed borosilicate glass
Sterniczuk et al., (2016). The study showed that measured
ceramics to aqueous reprocessing into a stable waste form
reducing radical yield is seven percent smaller at room
for generated immobilize high-level waste. The behavior in
temperature
corrosion of this multiphase waste form is considered to be
recommendation of Elliot and Bartels. However, it was in
complicated by more than one phases and interfaces of
fairly good agreement above 150 °C. Autors highlighted
crystal-glass. Study showed rates of corrosion rates for C1
that the menthod followed in this study would greatly
and its replicate C20 were increased with an order of
reduce range of error and increase the high temperature
magnitude by mechanical stresses at crystal-glass interface
escape yields for low-LET radiation.
which was caused by expansion of thermal mismatch in the process of cooling and unique morphology.
in
comparison
with
a
recent
review
Tran et al., (2016) presented a study for in silico investigation which is based on Monte Carlo simulation
A long-term model nonisothermal reactive
into energy deposition and production of radical species
transport for the corrosion products interactions of a
around a spherical nanoparticle having size of 50 nm in
carbon-steel canister and the compacted bentonite of a
diameter of gold by proton irradiation. Performed
high-level radioactive waste repository in granite was
simulations by the study showed the incident proton
studied by Samper et al., (2016). This study indicated that
energies from 2 to 170 MeV range that is been considered
results of the model are not sensitive significantly to the
important to the clinical proton therapy.
thermal transient as well as for the effect of temperature on
Sequestration of Radioactive Wastes. Buck et al., (2016)
the rate of corrosion. The study concluded that conistent
performed for chemically processed high burn-up uranium
simulations were observed for the most part experiment
oxide (UO 2) fuel using microscopic analysis. The study
1491 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
found that recalcitrant nano-particles containing, Pd, Ag, I,
originating from number of ore blends. Different ratios of
and Br are mostly consistent with the phase of high
contributing phases were determined through precipiates
pressure in silver iodide of undissolved residue. Further,
total elemental analysis, Arsenic (As) and molybdenum
this study indicated an increased levels of Ag and Pd from
(Mo) K-edge X-ray absorption spectroscopy that are
239
determined for each pH stage in the process of
Pu fission in high burnup fuels which allow formation of It is concluded that occurrence of
neutralization. This study showed that arsenate adsorbed to
these phases in UO 2 might reduce the impact of long-lived
ferrihydrite which was the dominant in the form of As
129
mineral regardless of pH.
these metal halides.
I on the repository performance assessment calculations. Two dimensional displacement discontinuity
Treatment and Disposal of Radioactive Wastes. Chon et
method for materials of transversely isotropic elastic and a
al., (2016) conducted a study exploring the optimum design
direction-dependent criterion for fracturing in anisotropic
features of available equipments in order to develop the
rocks has been studied by Shen and Shi (2016). Authors
conceptual design of super-compaction system. The main
have decribed results with the help of a model fracturing-
finding of this experiment showed that vertical compactor
hydraulic coupling for transversely isotropic rocks in a
die that can apply a compressive force of up to 7000 kN
project that was focused on CO 2 geo-sequestration in
will be fit for purpose low level radwaste treatment. It is
Australia. It is predicted by the modelling process that
concluded that developed design of super-compaction
study was stable under the injection conditions which is in
system will have capabilities in meeting the objectives
agreement with other simulations condudcted and the
ITER operations towards waste management. Combined use of organic free clay and concrete
monitored data. Islam and Sar (2016) investigated resistance of
and low pH concrete based on granulated blast furnace slag
metal and uranium (U) sequestration capabilities through
under hydrothermal conditions in the laboratory scale has
bacteria residing in subsurface of U ore using pure culture
been tested by Mohammed et al., (2016). Results of this
strains of about 122 that are isolated through enrichment. Microbacterium,
study show adequate compressive strength (up to ∼9 MPa)
Arthrobacter and Acinetobacter help in removing Uranium.
and low hydraulic conductivity (down to ∼5.6 × 10−10) was
attained at higer temperatures of 150 °C. This factor is an
The study highlights that U ore deposit bacterias have the
indication that clay-concrete sealing could be used for
great capacity to interact with U and these bacterias can be
stoping further migration of radionuclides vertically up via
utilized for U contaminated sites and wastes through
the repository in a borehole.
Study showed that bacterias such as
bioremediation.
Li et al., (2016) provided an overview of the
Bissonnette et al., (2016) considered a lab-scale
current laboratory studies as well as industrial experiments
plant in order to characterize secondary precipitates
on the status of thermal plasma technology (TPT) that has
1492 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
been use in China for the treatment of solid wastes.
Containers for Radioactive Waste Disposal. Standish et
Importantly, the overview provide information on the
al.,
existing challenges in the sector. In addition, authours have
characteristics with the help of analytical methods and use
discussed prospect of TPT for the future use in China. It is
of microscopy as well as electron backscatter diffraction.
concluded that technology of thermal plasma seem to be
This study showed that at the base of a simulated corrosion
promising technology for solid wastes treatment and
coating defect in a cold-sprayed coating was proceeded
reclaimation without having any adverse impact on the
through galvanic coupling to the extent of oxygen reduction
environment.
on surface coating. In addition, the damage accumalated at
(2016)
assessed
the
steel
container
coating
out
the base of the defect allowed a corrosion along the
geochemical analysis at Inshas disposal site. The study was
interface of copper and steel. This factor is mostly
conducted to investigate the mineral composition of the
attributed to the consequence of the damage inflicted in the
clay in order to predict the geological history and the past
process of deposition.
Abdel-Karim
et
al.,
(2016)
carried
environment. Experiments conducted in batch under three
Collier et al., (2016) reported investigations into
different temperatures for determining function of pH,
the use of cementitious grouts as sealing and support
solute concentration. It is found that obtained data on
matrices for deep borehole disposal scenarios considering
sorption were well fitted in to the Freundlich, Langmuir
low temperature. Results of study indicated that sodium
and Dubinin–Radushkevich models. These results indicated
gluconate and a polycarboxylate additive would provide
that the process of adsorption was exothermic which
sufficient retardation in the range between 90–140 degree
favored at low temperature conditions.
temperatures that can be utilized for sealing. It was also
A study used the technology of microwave
estimated that phosphonate and sulphonate additives could
sintering to vitrify the contaminated soil waste by
provide retardation at 90 degree centigrade.
radioactive and immobilize the radionuclide by Zhang et
Influence of Environment Conditions on the Stability of
al., (2016). In the study, contaminated soil by radioactive
Clay Minerals.
materials was sintered by microwave and conventional
desorption from Na-montmorillonite was investigated
processes. Results of this study showed that sintered
considering pH, electrolyte cations, humic acid (HA) and
smaples in microwave were denser than the samples
temperature by Yu et al., (2016). The results of this study
conventionally sintered at higher temperature for the longer
indicated that the sorption and desorption of 63Ni (II) of Na-
time up to 2 hours. The study also identified that simulated
montmorillonite were pH and electrolyte dependent.
radionuclide Nd can be immobilized with great success and
Authors concluded that the results of this study would
can be distributed uniformly in form of glass waste.
greatly contribute in
The effects on
63
Ni (II) sorption and
understanding the radionickel
physicochemical behavior in the natural environment. 1493 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
Jin et al., (2016) examined single soil source to
The radiological doses to non-human biota of
determine specific influence of its composition on stability
freshwater ecosystem in the Ignalina NPP cooling pond of
(14C activity) on the fractions of soil organic matter while
Lake Druksiai was evaluated by Mazeika et al., (2016). The
constraining other influential factors on carbon such as
evaluation study considered several cases including the
mineral, climate and plant input. Study shown that soil
operation
samples were not subjected to frequent burning which
decommissioning. The study was used models such as
needs to be examined. The study used only two soil
ERICA 1.2 code with IAEA SRS-19 that has been
samples therefore it is concluded that a broader suite of
considered as an integrated approach. Results showed
soils needs to be examined with wider ecological contrast.
feasible and acceptable on the protection of non-human
Maher et al., (2016) conducted a study at the Sellafield nuclear reprocessing site in the U.K on the
duration
of
plant
and
intial
activities
biota considering radiological effects in Ignalina NPP cooling pond.
behaviours of Plutonium (Pu), Americium (Am) and
Tierney et al., (2016) examined in the West of
colloids in feed solutions to the Site Ion-exchange Effluent
Scotland marine environment on uptake in the ecosystem
Plant. Analysis of feed solution has found that significant
and transfer of Sellafield-derived radiocarbon (14C). Study
fractions of Pu and Am are found in colloidal and
found that benthic and pelagic biota with variable life-spans
particulate fractions, although some is still found in the true
living indicated comparable 14C activities in the area. This
solution phase. Further, analysed data indicated the
factor is an outcome of mixing of 14C within the Irish Sea
behavior of Am behaviour in the samples was consistent
which is relatively constant on dispersal activity toward
with the association of radionuclide and a population of
northwards. Further, measured 14C activities in the Western
magnesium hydroxide colloids alone.
Sea activities on biota indicating that dispersion activities
Ecosystem. Kautsky et al., (2016) discusses the associated
to the West of Scotland is significant as Sellafield
constraints on the modelling of surface ecosystems given
releases.
14
C
the longer time scales with the help of assessment
Pupier et al., (2016) conducted a study in the
completed in recent years for the extension of the existing
beech forest site located in NE France on the fallout rates
low and intermediate-level nuclear waste repository
of chlorine (Cl) and chlorine-36 (36Cl). Rainfall samples
Sweden. This study concluded that it would be difficult to
collected on monthly basis for concentration of Cl and 36Cl
represent the biosphere with simplified models alone. Study
above the canopy that was conducted over a period of two
suggested that a diversity of food and water may be
years.The results shown that the concentrations of Cl
maintained since these can be considered as pathways for
originated mostly from sea-spray and the concentration of
accumulation as well as exposure of radionuclide.
36Cl that are originated from the stratosphere indicating dependent on seasonal changes.
1494 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
Brechignac et al., (2016) repoted the output of an international symposium organized by the International
nanofiltration
showed
good
stability
as
well
as
reproducibility.
Union of Radioecology in November 2015. The output
Chen et al., (2016) conducted a study for the
report of the conference provides debated ecological impact
waste separaton of weakly electrolytic silica and boron with
of radiation on populations and ecosystems. Based on this
the help of reverse osmosis. This study is meaningful given
discussions followed in the conference seven combined
the importance of boron reuse and waste reduction during
statements that have been dervided with regard to
treatment
environmental protection against radiation in the ecoystem.
radioactive materials. The study showd that setting up of
In addition, each of the statements are supplemented with
high temperature up to 55 degree centigrade led to a
some recommendations which provide a valuable input in
higher efficiency in separation of silica and boron. This
contribution towards integrated research on management of
separation allowed to control the loss in nuclides rejection
radiation research for the future.
in large quanity. This study concluded that considering the
Application of Membrane Processes. Liu et al., (2016)
design of the system, it is acceptable to reuse of recovered
for the removal of radioactive iodine from liquid waste
water containing a high concentration of boron and a low
developed an integrated precipitation reactor (PR) and
concentration of silica.
wastewater
with
lower
concentration
of
membrane separator (MS) system. The PR-MS system was
Jagasia et al., (2016) evaluated radio-cesium
evaluated in the laborotary, the study found that removal
separation using bis-octyloxy-calix [4] arene-mono-crown-
efficiency for radioactive iodine reached approximately
6 (CMC) from acidic feed solutions with the application of
97.0%. On the other hand, with the concentration of added
technique known as hollow fiber supported liquid
Na 2 SO 3 40 mg/L and the CuCl dosage 260 mg/L, the
membrane (HFSLM). The study showed that the rate of
derived concentration factor (CF) value was 1050.
permeation for cesium was gradually increased in HFSLM
Therefore, results of study indicate that use of PR-MS
with the addition of nitric acid concentration in order of
system would be useful of industrial application for the
1 M HNO 3 up to 6 M HNO 3 . Further, at a moderate
treatment of contaminated with liquid radioactive iodine.
acidity of 4 M HNO 3 , near quantitative transport of cesium
TiO 2 -doped ZrO 2 nanofiltration (NF) membranes with stable tetragonal phases via a modified colloidalsol-
was possible within 2 h of operation as the acid concentration considered to be high level waste.
gel process was fabricated using a mixture of Zr-inorganic
Liu and Wang (2016) studied the removal and
salts and Ti-alkoxides by Lu et al., (2016). In this study,
recovery of ammonia from radioactive wastewater at room
authors
nanometer-sizedTiO 2 -ZrO 2
temperature by adopting the technique of hydrophobic
colloidalsols with an average hydrodynamic diameter of ~2
membrane contactor (HMC). The removal efficiency of
nm. The results of this fabrication through systhesized
ammonia showed reaching to above 90% after 120 minutes
systhesized
1495 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
of operation in the experiment without adjustment of pH.
DEMO of water cooled fusion system by Nakamura et al.,
However, ammonia removal efficiency was reached above
(2016). This study has provided a basic strategy on
95% with the pH of wastewater adjusted to 12.0. Therefore,
development of the safety guidelines for water cooled solid
the study concluded that hydrophobic membrane contactor
pebble blanket considering the DEMO system. In addition,
technique could be considered as promising for the
the study reported achievements in recent times on
separation
understanding of the safety features of the water-cooled
of
ammonia
from
wastewater
having
DEMO. Furthter, analysis on MELCOR highlights the
concentration of radioactive materials. issues
importance of temperature histories of the DEMO
concerning decay heat removal, exposure to radiation,
components in case of decay heat removal. The study
possible accidents, waste handling and effluent releases in
indicated that behavior of transient tremperature in the first
the fusion facilities. This study highlights the importance to
wall is found to be different from ITER.
Fusion
Facilities.
Perrault
(2016)
studied
give for various issues such as removal of decay heat as a
Kulikov et al., (2016) reported solutions on
safety function. Further, it is also suggested to study on the
management of nuclear fuel waste. The study considered
accidents associated in the context of the ITER. Specific
front end and back end of of waste generated in the nuclear
attention to be paid in a project to optimize pathways on the
fuel cycle. Attention is given on enhancing protection
release of tritium gases.
against the uncontrolled proliferation of fissile materials by
Kaliatka et al., (2016) presented a numerical
following focused changes in the cycle of fuels. Authors
investigation considering thermal-hydraulic processes in a
found new information that has been generated through this
system of cooling vessel components followed by vacuum
study on availability of thorium for Russian Federation in
vessels as well as increase of pressure in fusion devices.
which futher assessemented have been incorporated. Study
This study performed the integrated analysis of the thermal
concluded that installation of small hybrid reactors with
hydraulic processes in the vessel components focused on
Th-blanket could help nuclear power plants in the future to
cooling system, vacuum vessel and protection against the
greatly solve its problems and support the export potential.
increase in pressure for W7-X device in the case of loss of
Vetter (2016) provided an overview of activities
coolant accident. Such cases considered under this study
on the breadth of radiation detection technologies and their
was done with the help of RELAP5 computer code.
applications. Authour provided these details considering
Integrated analysis of this study showed that the design of
ongoing programs at the Berkeley Applied Nuclear Physics
W7-X facility would help for vacuum vessal in cases of
program. Some of the technologies proposed for detection
failure.
of radiation range from fundamentals in physics to A study has been undertaken in Japan to
understand the current status of a safety research on the
biomedical imaging as well as security of future nuclear power of the world.
The overview conclude with
1496 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
discussion focused on Berkeley Radwatch and Resilient
radioactive materials. With the application of calculation
Communities
results
methods, authors were able to judge non radioactive
highlighted are part of events that took place in Japan about
boundary adjacent to main Steam line through a room of
four years ago at the nuclear power plant located in
main steam tunnel. Fruther, it is also found that feed water
Fukushima.
line was located within the boiling water reactor concrete
Other Progress. McEvoy et al., (2016) considered some of
materials were non-radioactive as well.
activities.
The
activities
and
important processes involved in the management of deep
Khane
et
al.,
(2016)
investigated
by
geological disposal facility (GDF). The main processes
implementing
considered are plate tectonics which give rise to seismicity,
visualization measurement techniques in order to assess
and
being
zonal pebbles residence time. The techniques that are used
considered is climate-related which has an impact on deep
mainly residence time distribution and radioactive particle
geological facilties since erosion and uplift play an
tracking. The study found that overall pebbles residence
important role. Overall, authors have provided some key
time increasing from the point of center towards the wall of
challenges which are prominent in the management of
reactor. Therefore, it is concluded that the benchmark data
geological disposal facilities located at the deeper levels in
generated in the study could be useful for assessment of
the United Kingdom.
commercial computational methodologies in cases of
volcanism.
Another
important
process
Hacioglu et al., (2016) conducted a study related
noninvasive
radioisotope
based
flow
investigations focused on granular flow.
to radioactive waste management particulary focused on
Lee et al., (2016) for the disposal of spent nuclear
radiation stability and resistance. The study considered
fuels (SNFs) considered two options in the generic model
possibility of using bisphenol-a polycarbonate to achieve
of GoldSim with focus on deep boreholes for disposal
the results. For that purpose, study tried to determine
(DBD) of spent nuclear fuels. Results shown from the
changes in the properties of polycarbonate irradiated with
point of DBD seem to be encouraging, this seems to give a
different doses. It is observed that there are certain
sufficient radiological safety in comparison with DGD.
modifications with the matrix of polymer. Further, it is
Further, the study did not find sensitivity of the travel
concluded that use of bisphenol-a polycarbonate doses at
lengths involved in the fractured geological media around
certain level could resist mechanical properties.
the DBD and its exposure dose rates. Mostly, the travel
Tanaka et al., (2016) studied an estimation of radioactive
concrete
waste
arising
from
the
decommissioning activities of boiling water reactor
lengths were fast and short travel times for non-sorbing nuclides with long-half lives. Future of the Topic
(BWR). Firstly, this study performed the estimation of a
Currently, there are about 435 nuclear reactors
boundary to draw a difference between non radioactive and
actively operating around the world which has spread
1497 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
across thirty three countries. This is an estimation recently
Buck, E.C., Mausolf, E.J., McNamara, B.K., Soderquist, C.Z.,
reported by the International Atomic Energy Association.
Schwantes, J.M. (2016) Sequestration of Radioactive
Over the period of past ten years, some existing plants are being closed down and the construction of 62 new units has
Iodine in Silver-palladium Phases in Commercial Spent Nuclear Fuel. J Nucl Mater., 482, 229-235. Bréchignac, F., Oughton, D., Mays, C., Barnthouse, L., Beasley,
started. The overall, estimated energy would amount to the J.C., Bonisoli-Alquati, A., Bradshaw,C., Brown, J.,
tune of 59,197 megawatts. Therefore, it is evident that the
Dray, S., Geras'kin, S., Glenn, T., Higley, K., Ishida,
nuclear industry is enjoying a comeback although there
K., Kapustka, L., Kautsky, U., Kuhne, W., Lynch, M.,
seems to be no commonly agreed solutions on the handling
Mappes, T., Mihok, S., Møller, A.P., Mothersill, C.,
of problems associated to nuclear waste management.
Mousseau, T.A.,
Given the importance of nuclear energy and its possible
Jr., O.E., Salbu, B., Strand, P., Tsukada, H. (2016)
impacts on the enrionment, the future review would involve number of topics to be addressed. The future topics will
Addressing
Otaki, J.M., Pryakhin, E.,. Rhodes
Ecological
Effects
of
Radiation
on
Populations and Ecosystems to Improve Protection of the Environment against Radiation: Agreed Statements
focused on issues related to safety assessment, modelling from
on watste management. Topics on environmental impacts
a
Consensus
Symposium.
J
Environ
Radioactivity., 158–159, 21-29.
in view of the mobility of radionuclides in environmental
Bissonnette, J., Essilfie-Dughan, J., Moldovan, B.J., Hendry, M.J.
compartments such as water, soil and ecosystem play an
(2016) Sequestration of As and Mo in Uranium Mill
important role in addition to addressing other technological
Precipitates (pH 1.5–9.2): An XAS Study. Appl
adavnces made in the radioactive waste management.
Geochem., 72, 20-33.
References ALNabhani, K., Khan, F., Yang, M. (2016) The Importance of Public Participation in Legislation of TENORM Risk Management in the Oil and Gas Industry. Proc Safety and Environ Prot., 102, 606-614. Abdel-Karim, A.M., Zaki, A.A., Elwan, W., El-Naggar, M.R., Gouda, M.M. (2016) Experimental and Modeling Investigations of Cesium and Strontium Adsorption onto Clay of Radioactive Waste Disposal. Appl Clay Sci., 132-133, 391-401. ALNabhani, K., Khan, F., Yang, M. (2016) Scenario-based Risk Assessment of TENORM Waste Disposal Options in Oil and Gas Industry. J Loss Preven in the Proc Indust., 40, 55-66.
Bower, W.R., Morris, K., Mosselmans, J.F.W., Thompson, O.R. Banford, A.W.,
Law, K., Pattrick, R.A.D. (2016)
Characterising Legacy Spent Nuclear Fuel Pond Materials
Using
Microfocus
X-ray
Absorption
Spectroscopy. J Hazar Mater., 317, 97-107. Bartnicki, J., Amundsen, I., Brown, J., Hosseini, A., Hov, O., Haakenstad, H., Klein, H., Lind, O.C., Salbu, B., Szacinski Wendel, C.C., Ytre-Eide, M.A. (2016) Atmospheric Transport of Radioactive Debris to Norway in Case of a Hypothetical Accident Related to the Recovery of the Russian Submarine K-27. J Environ Radioactivity., 151(2) 404-416. Collier, N.C., Milestone, N.B., Travis, K.P., Gibb, F.G.F. (2016) The Effect of Organic Retarders on Grout Thickening and Setting during Deep Borehole Disposal of High-
1498 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
Level Radioactive Waste. Progr in Nucl Ener., 90, 19-
Radioactive Waste Repositories. Chem Geol., 434, 12-
26.
27.
Chon, J.K., Beaudoin, V., Pitcher, C.S. (2016) Conceptual Design
Furuichi, K., Katayama, K., Date, H., Takeishi, T., Fukada, S.
of Volume Reduction System for ITER Low Level
(2016) Tritium Sorption Behavior on the Percolation of
Radioactive Waste. Fusion Eng and Design., 109-
Tritiated Water into a Soil Packed Bed. Fusion Eng and
111(A), 1001-1004.
Design., 109-111(B), 1371-1375.
Chen, D., Zhao, X., Li, F., Zhang, X. (2016) Rejection of Nuclides
Gonzalez-Robles, E., Metz, V., Wegen, D.H., Herm, M.,
and Silicon from Boron-containing Radioactive Waste
Papaioannou, D., Bohnert, E., Gretter, R., Müller, N.,
Water Using Reverse Osmosis. Separation and Purifi
Nasyrow, R., de Weerd, W., Wiss, T., Kienzler, B.
Techno., 163, 92-99.
(2016) Determination of Fission Gas release of Spent
Christian, R., Kang, H.G. (2016) Probabilistic Risk Assessment on
Nuclear Fuel in Puncturing Test and in Leaching
Maritime Spent Nuclear Fuel Transportation-Part I:
Experiments Under Anoxic Conditions. J Nucl Mater.,
Transport Cask Damage Probability. Reliability Eng
479, 67-75. Hacioglu, F., Ozdemir, T., Kinalır, K.G., Usanmaz, A. (2016)
and Sys Safety., Available online. Chen, C.A., Liu, L., Wang, B., Xiang, X., Yao, Y., Song, J. (2016)
Possible
Use
of
Bisphenol-a
Polycarbonate
in
Assessment of Tritiated Activities in the Radwaste
Radioactive Waste Embedding. Prog in Nucl Energy.,
Generated from ITER Chinese Helium Cooled Ceramic
90, 98-104.
Breeding test Blanket Module System. Fusion Eng and Design., 112, 569-578.
Sequestration Abilities of Bacteria from Uranium Ore
Crum, J.V., Neeway, J.J., Riley, B.J., Zhu, Z., Olszta, M.J., Tang, M. (2016) Dilute Condition Corrosion Behavior of Glass-ceramic Waste Form. J Nucl Mater., 482, 1-11. Deyab, M.A., Ouarsal, R., Lachkar, M., El Bali, B., Essehli, R. (2016)
Phosphites
Compound:
Novel
Corrosion
Inhibitor for Radioactive Waste Container (carbon steel)
in
Simulated
Islam, E., Sar, P. (2016) Diversity, Metal resistance and Uranium
Callovo-Oxfordian
(COx)
Deposit in Deep Earth Stratum. Ecotoxicol and Environ Safety., 127, 12-21. Jin, J., Sun, K., Wang, Z., Han, L., Wu, F., Xing, B. (2016) The Effect of Composition on Stability (14C activity) of Soil Organic Matter Fractions from the Albic and Black Soils. Sci of The Total Environ., 541, 92-100. Jagasia, P., Ansari, S.A., Raut, D.R., Dhami, P.S., Gandhi, P.M.,
Groundwater. J Molecular Liq., 219, 994-999.
Kumar, A., Mohapatra, P.K. (2016) Hollow Fiber
Decanis, C., Canas, D., Derasse, F., Pamela, J. (2016) Preparation
Susupported Liquid Membrane Studies Using a Process
for Tritiated Waste Management of Fusion Facilities:
Compatible Solvent Containing Calix[4]arene-mono-
Interim Storage WAC. Fusion Eng and Design., 109-
crown-6 for the Recovery of Radio-cesium from
111(A) 242-247.
Nuclear Waste. Separation and Purifi Techno., 170,
Denton, J.S., Goldstein, S.J., Paviet, P., Nunn, A.J., Amato, R.S.,
208-216.
Hinrichs, K.A. (2016) A Record of Uranium-series
Jia, Y., Bian, H.B., Duveau, G., Poutrel, A. (2016) Numerical
Transport at Nopal I, Sierra Peña Blanca, Mexico:
Modeling of the Influence of Steel Corrosion on the
Implications
Thermo-Hydro-Mechanical Response of the Callovo-
for
Natural
Uranium
Dposits
and
1499 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
Oxfordian Claystone. Comput and Geotechn., 71, 247-
in a Pebble Bed Reactor (PBR) Using Radioactive
260.
Pebble. Progr in Nucl Energy., 93, 267-276.
Jeong, K.S., Choi, B.S., Moon, J.K., Hyun, D., Lee, J., Kim, I.,
Kulikov, G.G., Shmelev, A.N., Geraskin, N.I., Kulikov, E.G.,
Kim, G.H., Kang, S.Y., Choi, J.W., Jeong, S.Y., Ahn,
Apse, V.A. (32016) Advanced Nuclear Fuel Cycle for
S.M., Lee, J.J. (2016) An Estimation to Measure and to
the RF Using Actinides Breeding in Thorium Blankets
Evaluate the Work Times Following the Trajectory of
of Fusion Neutron Source. Nucl Energy and Techno.,
Workers during Decommissioning of Nuclear Facilities.
2(2), 147-150.
Annals of Nucl Ener., 94, 10-15.
Kautsky, U., Saetre, P., Berglund, S., Jaeschke, B., Nordén, S.,
Jeong, J., Baik, M.H., Kang, M.J., Ahn, H.J., Hwang, D.S., Hong,
Brandefelt, J., Keesmann, S., Näslund, J.O., Andersson,
D.S., Jeong, Y.H., Kim, K. (2016) Radiological Safety
E. (2016) The Impact of Low and Intermediate-level
Assessment of Transporting Radioactive Wastes to the
Radioactive Waste on Humans and the Environment
Gyeongju Disposal Facility in Korea. Nuclear Eng and
over the Next One Hundred Thousand Years. J Environ
Techno., 48(6), 1368-1375.
Radioactivity., 151(2), 395-403.
Jeong, J., Lee, Y.M., Kim, J.W., Cho, D.K., Ko, N.Y., Baik, M.H.
Liu, H., Wang, J. (2016) Separation of Ammonia from Radioactive
(2016) Progress of the Long-term Safety Assessment of
Wastewater by Hydrophobic Membrane Contactor.
a Reference Disposal System for High Level Wastes in
Progr in Nucl Energy., 86, 97-102.
Korea. Prog in Nucler Ener., 90, 37-45.
Li, J., Liu, K., Yan, S., Li, Y., Han, D. (2016) Application of
Jeong, K.S., Choi, B.S., Moon, J.K., Hyun, D.J., Lee, J.H., Kim, I.J., Kang, S.Y., Choi, J.W.,
Ahn, S.M., Lee, J.J.,
Lee,B.S. (2016) The Safety Assessment System Based on Virtual Networked Environment for Evaluation on the
Hazards
from
Human
Errors
during
Decommissioning of Nuclear Facilities. Reliability Eng and Sys Safety., 156, 34-39.
Thermal Plasma Technology for the Treatment of Solid Wastes in China: An Overview. Waste Manag., 58, 260-269. Lee, Y.M., Choi, H.J., Kim, K. (2016) A Preliminary Comparison Study of Two Options for Disposal of High-Level Waste. Progr in Nucl Energy., 90, 229-239. Lu, Y., Chen, T., Chen, X., Qiu, M., Fan, Y. (2016) Fabrication
Kim, I., Choi, B., Hyun, D., Moon, J., Lee, J., Jeong, K., Kang, S.
of TiO 2 -doped ZrO 2 Nanofiltration Membranes by
(2016) A Framework for a Flexible Cutting-process
Using a Modified Colloidal Sol-gel Process and Its
Simulation of a Nnuclear Facility Decommission.
Application in Simulative Radioactive Effluent. J
Annals of Nucl Ener., 97, 204-207.
Membrane Sci., 514, 476-486.
Kaliatka, T., Uspuras, E., Kaliatka, A. (2016) Integrated
Liu, Y., Gu, P., Yang, Y., Jia, L., Zhang, M., Zhang, G. (2016)
Assessment of Thermal Hydraulic Processes in W7-X
Removal of Radioactive Iodide from Simulated Liquid
Fusion Experimental Facility. Nucl Eng and Design.,
Waste in an Integrated Precipitation Reactor and
Available online.
Membrane Separator (PR-MS) System. Separation and
Khane, V., Taha, M.M., Al-Dahhan, M.H. (2016) Experimental Investigation of the Overall Residence Time of Pebbles
Purifi Techno., 171, 221-228. McEvoy, F.M., Schofield, D.I., Shaw, R.P., Norris, S. (2016) Tectonic and Climatic Considerations for
1500 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
Deep
Geological Disposal of Radioactive Waste: A UK
in Japan: Toward Development of Safety Strategy of a
Perspective. Sci of The Total Environ., 571, 507-521.
Water-cooled DEMO. Fusion Eng and Design., 109-
Mazeika, J., Marciulioniene, D., Nedveckaite, T., Jefanova, O.
111(B), 1417-1421.
(2016) The Assessment of Ionising Radiation Impact on
Perrault, D. (2016) Safety Issues to be taken into Account in
the Cooling Pond Freshwater Ecosystem Non-human
Designing Future Nuclear Fusion Facilities. Fusion Eng
Biota from the Ignalina NPP Operation Beginning to
and Design., 109-111(B), 1733-1738.
Shut down and Initial Decommissioning. J Environ
Pupier, J., Benedetti, L., Bouchez, C., Bourlès, D., Leclerc, E., Thiry, Y., Guillou, V. (2016) Monthly Record of the Cl
Radioactivity., 151(1), 28-37. Maher, Z., Ivanov, P., O'Brien, L., Sims, H., Taylor,R.J., Heath,
and 36Cl Fallout Rates in a Deciduous Forest Ecosystem
S.L., Livens, F.R., Goddard, D., Kellet, S., Rand, P.,
in NE France in 2012 and 2013. Quatern Geochrono.,
Bryan,
35, 26-35.
N.d.
(2016)
Americium
and
Plutonium
Association with Magnesium Hydroxide colloids in
Sterniczuk, M., Yakabuskie, P.A., Clara Wren, J., Jacob, J.A.,
alkaline Nuclear Industry Process Environments. J Nucl
Bartels, D.M. (2016) Low LET Radiolysis Escape
Mater., 468, 84-96.
Yields for Reducing Radicals and H 2 in Pressurized
Mohammed, M.H., Pusch, R., Knutsson, S., Warr, L.N. (2016) Hydrothermal Alteration of Clay and Low pH Concrete
High Temperature Water. Radiation Phy and Chem., 121, 35-42.
Applicable to Deep Borehole Disposal of High-level
Shen, B., Shi, J. (2016) Fracturing-hydraulic Coupling in
Radioactive Waste: A Pilot Study. Constru and Build
Transversely Isotropic Rocks and a Case Study on CO 2
Mater., 104, 1-8.
Sequestration. Int J Rock Mech and Mining Sci., 88,
Martinik, T., Henzl,V., Grape, S., Jansson, P., Swinhoe, M.T.,
206-220.
Goodsell, A.V., Tobin, S.J. (2016) Design of a
Samper, J., Naves, A., Montenegro, L., Mon, A. (2016) Reactive
Prototype Differential Die‐Away Instrument Proposed
Transport Modelling of the Long-term Interactions of
for Swedish Spent Nuclear Fuel Characterization.
Corrosion Products and Compacted Bentonite in a
Nuclear Instruments and Methods in Physics Research
HLW Repository in Granite:
Section A: Accelerators, Spectrometers, Detectors and
Relevance
Associated Equipment., 821, 55-65.
Geochem., 67, 42-51.
for
Performance
Uncertainties Assessment.
and Appl
Moncoffre, N., Toulhoat, N., Bererd, N., Pipon, Y., Silbermann,
Sen, S., Srinivas, C.V., Baskaran, R., Venkatraman, B. (2016) The
G., Blondel, A., Galy, N., Sainsot, P., Rouzaud, J.N.,
Effect of Spatially varying Velocity Field on the
Deldicque, D., Dauvois, V. (2016) Impact of Radiolysis
Transport of Radioactivity in a Porous Medium. J
and Radiolytic Corrosion on the Release of 13C and 37Cl
Environ Radioactivity., 162-163, 285-288.
Implanted into Nuclear Graphite: Consequences for the Behaviour of
14C
and
36Cl
in Gas Cooled Graphite
Moderated Reactors. J Nucl Mater., 472, 252-258.
Schröder, J., Rossignol, N., Oudheusden, M.V. (2016) Safety in Long term Radioactive Waste Management: Insight and Oversight. Safety Sci., 85, 258-265.
Nakamura, M., Tobita, K., Someya, Y., Utoh, H., Sakamoto, Y.,
Shaukat, A., Gao, Y., Kuo, J.A., Bowen, B.A., Mort, P.E. (2016)
Gulden, W. (2016) Safety Research on Fusion DEMO
Visual Cassification of Waste Material for Nuclear
1501 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation
Decommissioning. Robot and Autonomus Sys., 75(B),
Monte Carlo Simulation of Absorbed Dose and
365-378.
Radiolysis
Yields
Enhancement
from
a
Gold
Slimak, A., Necas, V. (2016) Melting of Contaminated Metallic
Nanoparticle Under MeV Proton Irradiation. Nuclear
Materials in the Process of the Decommissioning of
Instruments and Methods in Physics Research Section
Nuclear Power Plants. Progr in Nucl Ener., 92, 29-39.
B: Beam Interactions with Materials and Atoms., 373,
Seher, H., Navarro, M., Artmann, A., Larue, J., Roloff, R., Weiß,
126-139.
D. (2016) Modelling Contaminant Transport in Generic
Vetter, K. (2016) Multi-sensor Radiation Detection, Imaging, and
Landfills for Decommissioning Waste from German
Fusion. Nuclear Instruments and Methods in Physics
Nuclear Power Plants. Progr in Nucl Energy., 89, 46-
Research Section A: Accelerators, Spectrometers,
56.
Detectors and Associated Equipment., 805, 127-134.
Standish, T., Chen, J., Jacklin, R., Jakupi, P., Ramamurthy, S.,
Yu, S., Wang, X., Chen, Z., Tan, X., Wang, H., Hu, J., Alsaedi, A.,
Zagidulin, D., Keech, P., Shoesmith, D. (2016)
Alharbi, N.S., Guo, W., Wang, X. (2016) Interaction
Corrosion of Copper-coated stell High Level Nuclear
Mechanism of Radionickel on Na-montmorillonite:
Waste
Influences of pH, Electrolyte Cations, Humic Acid and
Containers
under
Permanent
Disposal
Temperature. Chem Eng J., 302, 77-85.
Conditions. Electroch Acta., 211, 331-342. Tierney, K.m., Muir, G.K.P., Cook, G.T., MacKinnon, G., Howe,
Zhang, S., Ding, Y., Lu, X., Mao, X., Song, M. (2016) Rapid and
J.A., Heymans, J.J., Hughes, D.J., Xu, S. (2016)
Efficient Disposal of Radioactive Contaminated Soil
Ecosystem Uptake and Transfer of Sellafield-derived
using Microwave Sintering Method. Mater Lets., 175,
Radiocarbon (14C) part 2: The West of Scotland. Mar
165-168.
Poll Bulletin., 115(1-2), 57-66. Tanaka, K., Ueno, J., Chiba, S. (2016) Estimation of a Boundary to Distinguish between Radioactive Materials and NonRadioactive Materials Around a Main Steam Line and a Feed Water Line in a Biological Shielding Wall of a BWR for Decommissioning. Progr in Nucl Energy., 93, 371-385. Taguchi, A., Kato, Y., Akai, R., Torikai, Y. (2016) Desorption Behavior
of
Tritiated
Water
from
Organic
Functionalized Mesoporous Silica. Fusion Eng and Design., 113, 255-259. Tran, H.N., Karamitros, M.,
Ivanchenko, V.N.,
Guatelli, S.,
McKinnon, S., Murakami, K., Sasaki, T., Okada, S., Bordage, M.C., Francis, Z., El Bitar, Z., Bernal, M.A., Shin, J.I., Lee, S.B., Barberet, P., Tran, T.T., Brown, J.M.C., Nhan Hao, T.V., Incerti, S. (2016) Geant4
1502 Water Environment Research, Volume 89, Number 10 - Copyright © 2017 Water Environment Federation