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American Journal of  Medical 
Science and Innovation (AJMSI) 

A Review on the Management of  Strontium-90 Waste in Medical Facilities
Hassan Mansaray1*, Saidu Kamara2

Volume 4 Issue 2, Year 2025
ISSN: 2836-8509 (Online)

DOI: https://doi.org/10.54536/ajmsi.v4i2.5788
https://journals.e-palli.com/home/index.php/ajmsi

Article Information ABSTRACT

Received: July 12, 2025
Accepted: August 25, 2025
Published: October 22, 2025

Healthcare facilities generate a large amount of  waste, which is considered potentially 
dangerous. Hospitals are increasingly using radioactive isotopes for diagnostic and 
therapeutic applications. Isotopes are utilized in different applications of  life purposes 
such as nuclear medicine, radiotherapy, and in industry. Radioactive waste is any material 
that contains or is mixed with a radionuclide that poses a radiation level that exceeds the 
IAEA recommended level or that of  a national regulatory body. Today, the problem of  
radioactive waste is one of  the biggest threats to human beings, as its effects extend to 
the environment, natural resources, animals, plants, and soil. Strontium-90 is one of  the 
radioisotopes used in hospitals. Most of  the hospital’s radioactive waste is generated in the 
Nuclear Medicine department. Strontium-90 is a radioactive isotope that is considered one 
of  the most hazardous radioactive isotopes. This study focuses on the use of  strontium-90 
in medical facilities and how the wastes generated are sustainably managed for human safety 
and the environment. The applications, waste generation, tests, effects on human health and 
the environment, and the treatment processes of  strontium-90 waste have been studied. 
The treatment processes, such as forward osmosis membrane, crystalline inorganic ion 
exchanges, etc, of  strontium-90 waste in a hospital are detailed in this review. 

Keywords
Environment, Health, Hospitals, 
Radioactive Waste, Radionuclide, 
Strontium-90

1 Radiological Safety, Trinity College Dublin, University of  Dublin, Ireland  
2 Department of  Engineering, Faculty of  Engineering and Technology, Ernest Bai Koroma University of  Science and Technology, 
  Magburaka, Sierra Leone & Nuclear Safety and Radiation Protection Authority, Liverpool Street, Freetown, Sierra Leone
* Corresponding author’s e-mail: hassanmansaray08@gmail.com

INTRODUCTION     
Different types of  radionuclides are utilized in the field 
of  medicine for diagnostic, therapeutic, and research 
purposes. Hazardous radiological wastes alongside 
biological and chemical wastes are formed as a result of  
the production of  radioactive wastes from the utilization 
of  medical radioisotopes. Many of  the radionuclides in 
nuclear medicine departments are short-lived and in low 
or medium concentrations. Hospitals administering large 
quantities of  131I for treatment of  thyroid of  carcinoma 
or using frequently Iodine for radioimmunoassay aqueous 
solution or Tc-99m in diagnosis (Ohiduzzaman et al., 
2019; Tsai et al., 2016), should consider the provision of  
decay tanks for storage and safe disposal of  radioactive 
waste resulting from patients excretion or laboratory 
waste.  Radioactive waste refers to any material containing 
or mixed with a radioactive nuclei that poses a radiation 
level which exceed that level recommended by the IAEA 
or a national regulatory authority (Darda et al., 2021; 
Derib, 2017). The radioactive waste problem can be 
regarded as the biggest threat facing human beings today, 
as its effects extend to the environment, natural resources, 
animals, plants, and soil. Healthcare institutions generate 
an enormous amount of  waste, which is considered 
potentially hazardous given the inherent potential for 
dissemination of  infection (Cook et al., 2023; Rokka & 
Khanal, 2023). The objective of  waste management 
is to provide protection of  workers, patients, and the 
environment by minimizing the hazards in an effective 

way over the whole life cycle of  the considered product. 
It has been reported that Hospitals generate, on average, 
between 0.5 and two kilograms of  waste per bed per 
day (Mol et al., 2022). It is estimated that approximately 
85% of  the waste generated is not harmful, about 10% 
is infectious, and 5% is not infectious but harmful 
(Maqsood, 2023). 
Radiopharmaceuticals are used in medicine for diagnostic 
and therapeutic purposes. The commonly used 
radiopharmaceuticals in medicine are 99mTc, 131I, 131I, 
123I, 18F, H-3, and 14C. Much of  the radioactive waste in 
health facilities is aggregated in the Nuclear Medicine 
department.  A greater part of  the radioactive waste is in 
the form of  a liquid, and a smaller amount in the form of  
solid, and the minimum in gaseous form of  the radioactive 
waste is liquid, with a lesser amount of  solid and minimal 
in gaseous form (Rahman et al., 2011). The solid waste 
has traces of  radioactivity in the form of  syringes, 
needles, cotton, swabs, vials, contaminated gloves, and 
absorbent materials. High doses of  radioisotopes like 131I 
are found in the clothing and utensils of  patients. The 
contaminated objects and the unused radioactive material 
require safe disposal to ensure that the radiation exposure 
to the public, radiation workers, and environment does 
not exceed the prescribed safe limits (Das et al., 2021; 
Menon & Kumar LS, 2019). The short-term and long-
term effects of  ionizing radiation on humans are reduced 
by maintaining the levels of  exposure within the required 
limits, in addition to reducing its negative impacts on 



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the environment. Regular dose rate monitoring of  
radiological workers in the hospitals, area monitoring 
of  hospital environment, and quality control of  the 
radiation instruments are mandatory to assess the quality 
of  existing radiation safety standards. Every hospital is 
required to have a designated Radiation Safety Officer 
(RSO) who oversees all aspects of  radiation safety, 
including radioactive waste management. The RSO co-
ordinates such measures in accordance with guidelines 
prescribed by the International Commission on Radiation 
Protection and the national regulatory body.   
One of  the major concerns is the separation of  Sr-
90 (a B-emitter with a half-life of  28.8 days), which is 
due to its large concentration resulting from a high 
fission reaction product and specific activity (Parus 
& Mikolajczak, 2012; Moore, 2018). The chemical 
properties of  the 90Sr radioisotope make it possible to 
be utilized in the treatment of  cancer (Herrero Álvarez 
et al., 2021; Semenishchev & Voronina, 2020; Yeong et 
al., 2014). It is important to note that strontium ninety 
is known to be the most hazardous isotope of  strontium 
(Burger & Lichtscheidl, 2019; Holt et al., 2021; Pathak & 
Gupta, 2020; Semenishchev & Voronina, 2020). Thus, 
much interest is attached to the separation of  strontium 
ninety. The selective separation of  90Sr from a solution of  
radioactive waste for it to be suitably utilized or disposed 
of  is a significant field of  research. This review, therefore, 
focuses on the management of  radiological medical waste 
from the utilization of  strontium ninety in hospitals. 

LITERATURE REVIEW
Strontium ninety is purely a β-decay radionuclide having 
a 28.9 years half-life. It is exposed to the environment by 
various means, such as nuclear weapon testing, nuclear 
power plant accidents, the nuclear fuel reprocessing 
industry, etc. Following the Chernobyl and Fukushima 
nuclear accidents in 1986 and 2011, respectively, great 
attention has been paid to monitoring the presence of  
90Sr in food and the environment within the vicinity of  
nuclear facilities. The elements strontium and calcium 
are homologous and therefore share similar chemical and 
physical properties (Kołodziejska et al., 2021; Nedobukh 
& Semenishchev, 2019). Strontium ninety (90Sr) and its 
daughter radionuclide yttrium ninety (90Y) are distributed 
in bones and teeth as a result of  accumulation during 
long-term exposure(Glasco et al., 2024; Tolstykh et 
al., 2000). The radionuclide subsequently enters the 
circulatory system of  the human body together with 
calcium and induces bone cancer and leukemia. The long 
half-life and high fission yield of  strontium ninety renders 
among the most radiological hazards for humans and the 
environment. It is a fission product of  235U and 239Pu. 
90Sr emits beta particles with a maximum energy of  546 
keV, and its decay product is short-lived 90Y (half-life=64 
hrs) (Semenishchev & Voronina, 2019). Yttrium ninety 
decays to a stable nuclide 90Zr, resulting in the emission 
of  β-particles.  
The growth of  the nuclear power industry in the world 

and the widespread utilization of  nuclear technology 
(Kessides, 2012; Zhan et al., 2021), are the basis for the 
high demand in radiation protection and radiological 
risk assessment during routine operation and nuclear 
emergencies. It is therefore very important to provide 
analytical methods that are more effective in determining 
toxic radionuclides like Sr-90. The separation and 
purification of  Y-90 from Sr-90 can be done by utilizing 
a number of  methods such as  precipitation, solvent 
extraction, ion exchange, and extraction chromatography 
(Lee et al., 2022; Muchtaridi et al., 2017; Pichestapong et 
al., 2016). The extraction chromatography using solvent-
impregnated resins has been applied widely for trace 
metal separation and recovery (Cortina & Warshawsky, 
2021). 
Strontium readily dissolves in water, making it easier to 
be distributed in the environment (Mukherjee & Mishra, 
2021). The transportation of  Sr-90 from the environment 
to the food chain and finally into the human body can 
be done in different pathways. Strontium and calcium 
are group IIA elements with similar chemical properties 
and therefore have similar biological processes in the 
human body. Calcium is known to belong to the typical 
bone-seeking nuclides. Strontium ninety follows the 
uptake of  Ca when it enters the human body and readily 
accumulates on the surface  layer of  bone as Sr3(PO4) salts 
layers (Genter, 2012; Sharma, 2019a). Strontium ninety is 
involved in the formation of  bone salts and enters the 
inorganic salts of  the bone crystals, becoming immobile 
in the bone during the physiological osteogenesis 
process.90Y produces high-energy beta particles, which 
severely damage the human bone and hematopoietic 
tissues of  the bone marrow, resulting in bone cancer 
and leukemia. Several studies have been conducted on 
the treatment of  strontium ninety in water, which is 
associated with the synthetic radioactive isotope Sr-90 
and have similar physical properties to stable strontium 
(Gupta et al., 2017; Semenishchev & Voronina, 2019; 
Sharma, 2019a). 
The utilization of  radiopharmaceuticals in radiation 
therapy has been existing for decades and offers enormous 
benefits to cancer patients, particularly to those suffering 
from thyroid cancer (Chinweike-Umeh et al.; Lepareur et 
al., 2023; Salih et al., 2022; Sgouros et al., 2020). Several 
clinical trials using radiopharmaceuticals to treat other 
types of  cancer are ongoing and their success will increase 
the demand for therapeutic radiation pharmaceuticals 
in the future. Radionuclides with very short half-lives 
have challenges such as transportation and the need for 
frequent shipments. Short-lived radioisotopes are globally 
made available for efficient therapeutic purposes by the 
use of  radionuclide generators.  
Imaging equipment are utilized alongside some 
radiopharmaceuticals to detect diseases(Payolla et al., 
2019). A cancerous tumor can be destroyed or shrunk by 
placing a radiopharmaceutical inside the body. Hospitals 
that provide radiation or nuclear services often have 
an Office of  Radiation Safety, which is responsible for 



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maintaining and administering high-level safety protocols. 
They are also responsible for the maintenance and 
collection of  data related to waste, compliance, audits, 
and permits, as well as the possible transport and safe 
handling of  radioactive materials. Even low levels of  
radioactive waste from hospitals must be packaged and 
transported according to regulatory requirements(Ali et 
al., 2017; CENA & HASI, 2024; Ravichandran et al., 2011). 
Labels, container markings, and packaging must identify 
the contents, codes, and symbols. Short half-lives and low 
radio-toxicity are the primary properties of  biomedical 
waste, and contains low-energy Beta and Gamma emitters 
with a low total and specific activity(CENA & HASI, 
2024; Hooshmand et al., 2020).

MATERIALS AND METHODS
About 104 articles were explored from various publishing 
houses and online research platforms such as Elsevier, 
Wiley, MDPI, Research Gate, etc, with data related to 
the topic “A Review of  Managing Strontium-90 Waste 
in Medical Facilities”. The articles were systematically 
reviewed by employing the Preferred Reporting Items 
for Systematic Reviews (PRISM) guidelines. The research 
question was structurally formulated based on previous 
work reported by various researchers on the Management 
of  Radioactive Wastes in Medical Facilities. 

The Hospital’s Use of  Strontium-90 and Its Waste 
Management
Utilization of  Strontium Ninety Isotope In A 
Medical Facility
90Sr is a significant radioisotope utilized in medicine over 
the years. The applications of  90S in nuclear medicine 
have been reported by many researchers. Strontium 
is deposited in bones for a pain relief  signal that 
communicates to the brain (Cristofaro, 2017; Genter, 
2012; Ru et al., 2024; Semenishchev & Voronina, 2020). 
Eye disorders and radiotherapy cancer cells can be also 
be treated using strontium ninety (Banerjee et al., 2022; 
Burov, 2023; Liberal et al., 2016). In medicine, strontium 
ninety compound is used to treat hepatocellular 
carcinoma (HCC) and other liver cancers (Chakravarty & 
Dash, 2012; Gao et al., 2021; Mukherjee & Mishra, 2021).  
According to IAEA 1998, it is reported that strontium-90 
in medical facilities is utilized as manual brachytherapy 
and further highlighted it use as a radioactive tracer. 
Findings show that strontium ninety is used to treat skin 
and eye diseases (Neal et al., 1991; Qin et al., 2012). 

The Accumulation of  Strontium Ninety In Medical 
Waste    
The waste produced from the use of  strontium ninety is 
dangerous to people and the environment. In order to 
solve this problem, it is significant to understand how 
these wastes are generated. It has been reported that 
strontium ninety waste is aggregated from the waste 
waters produced in radiation therapy rooms through urine, 
faeces, and detergents (Luhar et al., 2021; Maddheshiya 

et al., 2025; Pant, 2021). The liquid of  strontium ninety 
wastes can also be generated from radioimmunoassays 
(RIAs) utilized to measure the concentration in patients 
in vitro assay technique. Radioimmunoassay waste 
comprises proteins generated from reagents and samples 
during analysis. Much work has not been done on the 
liquid waste of  strontium ninety from radiation therapy 
rooms. Liquid wastes such as of  urine, feces, detergent 
and radionuclides from radioactive therapy differs from 
RIA waste (CENA & HASI, 2024; Lee et al., 2018; 
Ravichandran, 2017; Sancho et al., 2013) where all of  the 
liquid waste aggregated from the examination, radiation, 
and the patients themselves (Chitnis et al., 2005; Lee et al., 
2018; Padmanabhan & Barik, 2019; Rahman et al., 2011; 
Zikhathile et al., 2022), while RIA wastes are only obtained 
from the analysis of  reagents and samples, and especially 
when its radioactivity is far lower than wastes accrued 
from radiation therapy room (Ahmed, 2001; CENA & 
HASI, 2024; Puspita et al., 2023; Sancho et al., 2013). 

Determination of  Strontium Ninety  
A number of  environmental materials,   such as air filters, 
swipes, biota, water, soil, etc., are utilized to test for 
strontium. Strontium-90 can be quantified by employing a 
variety of  chemical methods (Ppoletiko et al., 1994; Tayeb 
et al., 2016; Vajda & Kim, 2010), like spectrophotometry, 
atomic absorption spectroscopy, x-ray fluorescence 
spectrometry, inductively coupled plasma spectroscopy-
atomic emission and mass spectrometry applications 
(i.e., ICP-AES and ICP-MS), etc. Proportional in vitro 
gas flow, scintillation, and Cherenkov counting are the 
technologies used to detect the quantity of  strontium-90 
in the environment (Domenech, 2017; Hou & Roos, 
2008; Tayeb, 2015). Radiostrontium in water and urine is 
determined using the EPA analytical standard procedure. 
Strontium-90 is precipitated as insoluble carbonates by 
adding a stable strontium carrier to water. The sample 
then undergoes preliminary counting that represents 
the total strontium activity (90S). Bioassay technique 
urinalysis can be tested for strontium-90 (Dai et al., 
2013; Sadi et al., 2010; Shiraishi et al., 2007; Wang et al., 
2004). The estimated internal dose due to exposure to 
radiostrontium is provided by strontium ninety utilizing 
ion chromatography internal dose due to exposure to 
radiostrontium (Semenishchev & Voronina, 2020; Tomita 
& Takeuchi, 2019; Vajda & Kim, 2010). Strontium-90 can be 
detected in water and urine samples using the Fast Column 
Separation method and liquid scintillation counting. A 
high-capacity iminodiacetate chelating resin buffered to 
a pH of  5 was utilized to extract strontium ninety. The 
transition metals, lanthanides, etc, were extracted by the 
resin at a pH of  5 and transferred to a column separator 
and subsequently released as weak acids. 

Human Health and Environmental Effects of  
Strontium Ninety
Strontium-90 wastes in medical facilities are harmful 
to people and the environment. Food and water which 



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are major exposure pathways for the population are 
contaminated by strontium ninety when disposed to 
the environment (Sharma, 2019b; Wang et al., 2023).  
Exposure to strontium-90 can lead to a number of  health 
issues such as bone disorders, bone cancer, etc.(Marx 
et al., 2020; Ru et al., 2024). It has been reported that 
strontium-90 was found in the teeth children following 
a global nuclear testing in the atmosphere (Froidevaux et 
al., 2006; Gould et al., 2000) which resulted to harmful 
effects like leukemia or skeletal cancer caused by damage 
in DNA cells. Strontium-90 has a long half-life of  28.8 
years, and it presence in the body can lead to long term 
irradiation of  skeletal bone structure which may lead 
to damage in bone marrow, leukemia, and other bone 
cancers (Gupta et al., 2018).
The harmful effects of  strontium-90 are reasons for 
its monitoring in the environment, particularly in 
groundwater surrounding nuclear facilities (Freed, 
2002; Semenishchev & Voronina, 2020). Chlorophyll 
formation in plants is decreased when contaminated by 
strontium-90 (Chatterjee et al., 2020; Dresler et al., 2018; 
Moyen & Roblin, 2010). Plants absorbed radioisotopes 
from the environment enters the food chain which 
affects human health and the environment. Agricultural 
plants cultivated in areas contaminated by Sr-90 also 
pose health risks to humans or animals when eaten and 
ingested (Burger & Lichtscheidl, 2019; Gupta et al., 2018; 
Sharma, 2019b).

Treatment Methods for Strontium-90 Medical Wastes
The Pretreatment of  90sr Using Forward Osmosis 
(FO) Membrane Technique
The Forward Osmosis (FO) membrane process used for 
the pretreatment of  strontium-90 liquid waste have been 
highlighted by many researchers (Kadadou et al., 2023; 
Pabby et al., 2022). This application has two radionuclide 
decay system of  two main septic tanks for the collection 
of  liquid waste and the decay of  radionuclides, respectively 
(Azman et al., 2024; Kadadou et al., 2023; Rao et al., 2022). 
The first tank is used to store the collected liquid waste 
to allow the radionuclides to decay and then subsequently 
pumped to the second tank where the radionuclide will 
further decay and discharged after the radioactivity or 
quality of  the final water reached regulatory requirements. 
A very large area is required to carry out the pretreatment 
method and therefore requires improved management of  
radiation therapy facilities.
A highly concentrated draw solution (DS) is utilized as 
the main driving force to extract pure water from the 
feed solution (FS) based on the difference in osmotic 
pressure between DS and FS (Blandin et al., 2020; 
Chekli et al., 2012). FO consumes low energy, has high 
fouling reversibility, and high rates of  recovery. Medical 
radioactive wastewater having high fouling potential can 
be suitably treated using FO due to the low working 
pressure of  FO, leading to high fouling reversibility. FO 
is used to remove heavy metals and arsenic due to the 
high rejection rate.

Ion Exchange Inorganic Crystals 
Crystalline inorganic ion exchangers for Sr-90 are 
employed in the treatment of  Sr-90 nuclear waste due 
to their high radiation, thermal, and chemical stability 
(Figueiredo et al., 2018; İnan, 2022; Li & Chen, 2024; 
Marinin & Brown, 2000) and ion selectivity. They can 
easily be transformed into alternate ceramics compatible 
with the metrics immobilization. Inorganic ionic crystal 
exchangers are mostly selected for specific ions due to 
their crystallochemical properties such as ionic radii, 
charge, and polarizabilities, etc. Inorganic materials such 
as phosphates, molybdates, titanates, silicates, etc., are 
therefore utilized to separate 90Sr from radioactive waste 
(İnan, 2022; Savva, 2016; Yudintsev, 2021). Titinates and 
silicotitanates are employed for their increased stability 
in conditions of  radioactive wastes (Popa & Pavel, 2012; 
Stefanovsky & Yudintsev, 2016; Zhang et al., 2022), but 
are however ineffective for the separation of  90Sr in 
acidic solutions because they strongly inhibits protons. 
Various authors have conducted research on different 
hydrous oxides to selectively separate the cations of  
radioactive elements from aqueous solutions using 
inexpensive methods. The behaviors of  amorphous 
MnO2 and birnessite were compared and the result 
show shows faster sorption kinetics, higher adsorption 
capacities and stabilities observed in birnessite than 
amorphous manganese oxide. Birnessite crystals are 
extensively stable in acidic media and have a higher 
sorption capacity than the amorphous nature due to 
structural properties. Strontium ninety is separated by ion 
exchange using inorganic monosodium titanate (MST) 
(Hobbs et al., 2005; Peters et al., 2006). MST exhibits a 
very good performance with a little strontium desorption 
during washing. 

Physicochemical Method to Remove Sr(II) In 
Aqueous Solution 
Effective adsorbents for the removal of  Sr (II) in aqueous 
solutions are eggplant hull, moss, activated carbon,  
sawdust modified with magnetic Fe3O4 particles, pecan 
shell, synthetic zeolites, baker’s yeast, etc (Koshy & Pathak, 
2019; Liu et al., 2024). Clay is a cost-effective, natural 
abundance adsorbent material that is suitable to remove 
the ions of  strontium in solution (Ahmadpour et al., 2010; 
Li et al., 2022; Shahadat & Isamil, 2018). The interest in 
cement and clay has grown considerably in recent times. 
The removal of  radiotoxic ions in the treatment of  
wastewater has been carried out using different types of  
clay and clay minerals. Strontium ninety is used in a batch 
experiment to investigate the adsorption behavior of  
montmorillonite and kaolinite minerals for SR (II), which 
reveals that adsorption occurs through ion exchange 
(Başçetin & Atun, 2006; İnan & Hiçsönmez, 2022; Koshy 
& Pathak, 2019). Bentonite was also utilized to get Cs 
and Sr by a rapid uptake and good sorption capacity. Sr 
(II) in aqueous solution was removed using powdered 
dolomite (Ghaemi et al., 2011; Sdiri, 2018). The Langmuir 
isotherm was utilized to interprete the equilibrium data 



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and the pseudo-second order kinetic model. According to 
the adsorption isotherm, the maximum sorption capacity 
was observed to be 1.172 mg/g at 273K (Tiwari & Lee, 
2015). Sr (II) was also effectively removed in aqueous 
solution by other types of  clay minerals like clinoptillite 
and paligrskite. Sr (II) are attached to negatively charged 
mineral surfaces forming complex outer spheres 
(Rahnemaie et al., 2006), and the extent of  adsorption 
depends on several factors, such as ionic strength, pH, 
and composition.

The Use of  Graphene Oxide Membrane (GO) Method 
to Remove of  Sr(II) From High Liquid Waste 
Many researchers have reported the separation of  
radioactive strontium waste using Graphene Oxide (GO) 
membrane method (Wei et al., 2024; Xing et al., 2019). 
This is a well-known and newly accepted carbon-based 
method for radiochemical separation. An investigation 
was carried out to determine how metallic elements 
permeate in high liquid waste (HLLW) using a 5μm thick 
ionic sieve GO membranes. It was observed that the rate 
at which the ions permeate through GO membranes 
decreases with an increase in hydrated ionic radii. Sr 
(II) was seen to permeate faster than lanthanide and 
actinide ions, which slowly infiltrate, making it possible 
for separation according to their difference in hydrated 
ionic radii. The initial concentrations of  metal ions and 
the acidity of  the solution influence the permeation of  
the ions passing through the GO membranes. The higher 
initial metal ions and the feed acid solution are suitable 
for the removal of  strontium ninety. The suitability of  the 
GO membranes to separate Sr (II) from HLLW is proven 
by the barrier separation test.   

The Biochroma Technique
Medical radioactive waste like Sr-90 can be managed using 
the Biochroma technique (Semenishchev & Voronina, 
2020).  It is a pretreatment method that utilizes a bio-
treatment system where adsorption is the final phase. 
Buffer tanks are used to store the waste waters from the 
radiotherapy wards. The tanks are fitted with specially 
designed pumps with a device or instrument that shredder 
solid particles, thus homogenizing the effluent (Banerjee 
& Mitra, 2013). The holding tanks are responsible for the 
bio-treatment phase, and they have an aeration system 
that prevents anaerobic processes. Before the biological 
treatment, the wastewater is allowed to undergo 
sedimentation to remove larger particles that may reduce 
the sludge performance in the biologically made reactor. 
The next stage of  the process is the upstream installation 
of  an optimized biological treatment plant for the final 
phase of  adsorption and filtration. The plant is designed 
with a secondary clarification stage to filter and separate 
any suspended solid materials and finally reduce organic 
contaminants to their lowest level. The downstream 
adsorption filter is protected against unwanted clogs. The 
activated carbon filters and selective ion exchangers in the 
adsorption filter system are used to eliminate the dissolved 

radioactive components in the wastewater before finally 
collected in the storage tanks. The wastewater in the 
storage tank is constantly monitored as it is subsequently 
discharged into the sewage system.

CONCLUSION
Strontium ninety is an important radioactive isotope 
in medical radiotherapy and research due to its various 
applications in the treatment various illnesses such 
as liver cancer, bone cancer, and tumors. Despite the 
justifiable use of  this radioisotope, the waste generated 
must be properly managed. The inadequate management 
and disposal of  radioactive waste to the environment 
contaminates agricultural plants and crops. When these 
radioisotope contaminated crops are eaten by humans, 
they accumulate in bones and teeth leading to several 
diseases. To maintain a healthy environment, it is essential 
to use good pretreatment methods such as the biochroma 
pretreatment method. 

REFERENCES
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(2010). Effect of  adsorbents and chemical treatments 
on the removal of  strontium from aqueous solutions. 
Journal of  hazardous materials, 182(1-3), 552-556. 

Ahmed, A. B. A. (2001). Evaluation of  management of  
radioactive waste in nuclear medicine department of  radiation 
and isotopes center, Khartoum. 

Ali, M., Wang, W., Chaudhry, N., & Geng, Y. (2017). Hospital 
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Azman, M. A. N., Goh, P. S., Ismail, A. F., Jamaluddin, K., 
Wong, K. Y., & Sahril, A. S. (2024). Forward osmosis 
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Banerjee, S., Basu, S., Baheti, A. D., Kulkarni, S., 
Rangarajan, V., Nayak, P.,…Agarwal, J. (2022). 
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Banerjee, S., & Mitra, S. (2013). Radioactive and hospital 
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Başçetin, E., & Atun, G. (2006). Adsorption behavior 
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Blandin, G., Ferrari, F., Lesage, G., Le-Clech, P., Héran, 
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Burger, A., & Lichtscheidl, I. (2019). Strontium in the 
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