Radioactive Wastes - Ingenta Connect

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


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


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


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


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


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.


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


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


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


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-


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


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


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


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
