protection of radiation and waste treatment
DESCRIPTION
related to pharmaceuticalTRANSCRIPT
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
PROTECTION OF RADIATION
AND
RADIOACTIVE WASTE TREATMENT
SYMBOLS
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Explosive (E) Toxic (T)
Harmful (Xn)
Harmful (Xn)
Caution
Biohazard Radiation Ionizing Radiation
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Optical Radiation
Non Ionizing Radiation
Laser Radiation
High Voltage
Chemical Weapon Corrosive Highly Flammable (F)
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Extremely
Flammable (F+)
Dangerous for the
Environmental
Oxidizing Agent (O) Very Toxic (T+)
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Harmful (Xn) Irritant (Xi) Chemical Hazard
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
Radiation Absorbed Dose The absorbed dose characterized the amount of damage done to the
matter (especially living tissues) by ionizing radiation. The absorbed
dose is more closely related to the amount of energy deposited.
The SI unit of absorbed dose is the gray (Gy) (or J/kg).
1 Gy = the amount of radiation required to deposit 1 joule of energy in 1
kilogram of any kind of matter.
The sievert (Sv) is the SI derived unit of equivalent radiation dose, effective
dose, and committed dose.
1 Sv = the amount of radiation necessary to produce the same effect on
living tissue as 1 Gy of high-penetration x-rays.
Quantities that are measured in Sv are designed to represent the biological
effects of ionizing radiation.
Radioactive Contamination
Kontaminasi radioaktif terjadi apabila larutan atau serbuk radioaktif tertumpah ke lantai, mengenai baju atau bagian tubuh, atau terdispersi ke udara dan terhirup melalui inhalasi.
Faktor-faktor yang harus diperhatikan pada pengukuran kontaminasi adalah:
• Level kontaminasi
• Identifikasi kontaminan
• Sifat permukaan bahan yang terkontaminasi
Exposure of Radiation
The amount of exposure of external radiation could be monitored using a dosimeter.
The amount of exposure of internal radiation could be calculated indirectly by measuring the radioactivity in urine or faeces.
http://www.degmark.com/products/dosimeter
Metode pemantauan kontaminasi:
• Survey method
Metode survey
dilakukan dengan cara
men-scan permukaan
yang terkontaminasi
menggunakan alat
survey meter
• Smear method (metode
usap)
Metode usap dilakukan
dengan cara mengusap
daerah kontaminan
dengan cotton,
kemudian ditempatkan
pada plan set, dan
diukur tingkat
kontaminasinya
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Survey method Mapping the contamination area
Monitoring Decontamination
Pengendalian Daerah Kerja
Bidang Keselamatan – Pusat Radioisotop dan Radiofarmaka
Smear method
Mekanisme kerja survey meter adalah sebagai berikut:
Ionization chamber survey meter
Survey meter ini terdiri dari tabung
tertutup berisi gas inert Ar atau He dan dua elektroda.
Kontaminan radioaktif mengemisikan radiasi pengion dan tertangkap oleh detektor survey meter.
Radiasi pengion akan mengionisasi atom gas inert di dalam tabung detektor, ion positif bergerak menuju katoda dan ion negatif menuju anoda, menyebabkan arus mengalir dan terukur ekivalen dengan dosis radiasi kontaminan.
Surveymeter ß/ IC
• Geiger Muller survey meter
Survey meter ini merupakan detektor
radiasi terdiri dari tabung tertutup berisi
gas inert Ar, Ne, atau He dengan halogen
ditambahkan di dalamnya, serta dua
elektroda.
Kontaminan radioaktif mengemisikan
radiasi pengion dan tertangkap oleh
detektor survey meter.
Radiasi pengion tersebut akan
mengionisasi atom gas inert di dalam
tabung detektor, ion positif bergerak
menuju katoda dan ion negatif menuju
anoda, menyebabkan arus mengalir dan
terukur setara dengan dosis radiasi
kontaminasi. Surveymeter ß/ GM
Bila inti memiliki nilai N/Z berbeda dengan nilai N/Z inti stabil, maka inti atom tersebut tidak stabil dan akan mengalami peluruhan (decay) dengan memancarkan partikel b atau melalui tangkapan elektron
Atomic Symbols • A = mass number = protons + neutrons
• Z = atomic number = protons = electrons
A – Z = the number of neutrons
XA
Z
XA
Z XA
Z XA
Z
XA
Z Na23
11
α decay
The reason alpha decay occurs is because the nucleus has too
many protons which cause excessive repulsion. In an attempt to
reduce the repulsion, a Helium nucleus is emitted.
An example of this is a uranium-238 atom decaying into into a thorium-234 atom and an alpha particle (helium-4 nucleus, i.e. 2 protons and 2 neutrons).
U 235 92 Th 231
90 + He 4
2
Example of beta decay is an atom of carbon-15 changing into
an atom of nitrogen-15 by emitting an electron.
Notice that the number of particles in the nucleus have stayed
the same; 15 in each case [A does not change].
β decay
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
Positron Decay of Carbon-11 to Boron-11
β+ decay
Here's a diagram of electron capture with beryllium-7:
11C → 11B + e+ + νe + 0.45 MeV
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
γ decay
10 mL
Pengukuran radioaktivitas larutan menggunakan Dose
Calibrator
Whole vial assay method 500 mCi
Aliquot method
1 mL Syringe Sisa tertinggal dalam needle 1 mL Eluate
= 53 mCi = 3 mCi = 50 mCi
Aktivitas Total 50 mCi/mL x 10 mL = 500 mCi
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
Contains small concentration of radionuclides
Does not require radiation protection
Contains short T1/2 of radionuclides
Activity concentration > clearance level
Should be stored until activity decreases
Contains short T1/2 of radionuclides
Activity concentration is in the region of
clearance level
Requires radiation protection
Activity concentration > clearance level
Does not require shielding during handling
Does not require determining factor for long term safety
Contains long-lived radionuclides
Activity concentration is high
Should be isolated from the biosphere
Disposal should be in the range of hundred meters depth
Contains very high activity concentration of short and long-lived radionuclides
Disposal should be very deep with engineered barrier
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
Radionuclide Production
JUTTI LEVITA-FACULTY OF PHARMACY-UNIVERSITAS PADJADJARAN
1. Cyclotrons
• Cyclotrons produce radionuclides by bombarding stable nuclei with high-energy charged particles
• Most cyclotron-produced radionuclides are neutron poor and therefore decay by positron emission or electron capture
• Specialized hospital-based cyclotrons have been developed to produce positron-emitting radionuclides for positron emission tomography (PET) – Usually located near the PET imager because of short half-
lives of the radionuclides produced
Magnet 1
Magnet 2
Dee 1
Dee 2
Vacuum Sumber ion
Side view
~
Hollow Electrodes (Dees)
Oscillator
Target
Deflector
Top view https://www.youtube.com/watch?v=M_jIcDOkTAY
https://www.youtube.com/watch?v=cNnNM2ZqIsc
2. Nuclear Reactors
• Specialized nuclear reactors used to produce clinically useful radionuclides from fission products or neutron activation of stable target material
• Uranium-235 fission products can be chemically separated from other fission products with essentially no stable isotopes (carrier) of the radionuclide present
• Concentration of these “carrier-free” fission-produced radionuclides is very high
https://www.youtube.com/watch?v=1U6Nzcv9Vws
Contoh:
Ketika 235U mengabsorpsi neutron, inti atom akan mengalami reaksi fisi dan pecah menjadi dua atau lebih produk fisi berupa nuklei yang lebih ringan, dengan melepaskan energi kinetik, radiasi gamma, dan neutron bebas.
Neutron bebas tersebut selanjutnya akan diabsorpsi oleh atom lain, dan memicu reaksi fisi berikutnya.
Neutron Activation
• Neutrons produced by the fission of uranium in a nuclear reactor can be used to create radionuclides by bombarding stable target material placed in the reactor
• Process involves capture of neutrons by stable nuclei
• Almost all radionuclides produced by neutron activation decay by beta-minus particle emission
3. Radionuclide Generators
• Technetium-99m has been the most important radionuclide used in nuclear medicine
• Short half-life (6 hours) makes it impractical to store even a weekly supply
• Supply problem overcome by obtaining parent Mo-99, which has a longer half-life (67 hours) and continually produces Tc-99m
• A system for holding the parent in such a way that the daughter can be easily separated for clinical use is called a radionuclide generator
• Kolom gelas berisi adsorben alumina sebagai media penyangga untuk radionuklida induk 99Mo dalam bentuk molibdat. Radionuklida induk akan terikat kuat pada media penyangga dan tidak terlepas pada elusi radionuklida anak 99mTc pertehnetat.
• Sistem tabung dirancang agar kolom dapat dialiri larutan saline (NaCl) steril, karena radionuklida yang dihasilkan, yaitu 99mTcO4- dalam larutan NaCl, dapat langsung digunakan untuk injeksi.
• Sistem filter pada generator ini terbuat dari cakram gelas dengan ukuran pori-pori 0,22 μm, yang fungsinya untuk menghilangkan partikel-partikel kecil dari larutan elusi dan menjamin sterilitas produk.