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Title of Thesis

Preparation Of High Specific Activity Radionuclides For Therapeutic Radiopharmaceuticals

Author(s)

Syed Tanveer Hussain Bokhari

Institute/University/Department Details
DDepartment Of Chemistry / GC University, Lahore
Session
2010
Subject
Chemistry
Number of Pages
202
Keywords (Extracted from title, table of contents and abstract of thesis)
Activity, Radionuclides, Therapeutic, Chromatography, Spectroscopy, Purity, Sufficiently, Aluminum, Oxide, Alumina, Radiopharmaceuticals, Radiotherapy, Methyl, Ketone

Abstract
Not Available

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S. No. Chapter Title of the Chapters Page Size (KB)
1 0 CONTENTS
 

 

 
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2 1 INTRODUCTION

1.1 History of Radioisotope Production
1.2 Cyclotron Produced Radionuclides
1.3 Reactor Produced Radionuclides
1.4 Generator Produced Radionuclides
1.5 Isotope Production Facilities
1.6 Laboratory Facilities for Radioisotope Production
1.7 Radiotherapy
1.8 Radiochemical Separations
1.9 Purity of Radionuclide
1.10 Specific Activity (Activity-Mass Relation)

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3 2 LITERATURE SURVEY

2.1 Scandium Radionuclides and Radiopharmaceuticals
2.2Copper Radionuclides and Radiopharmaceuticals
2.3. Gallium Radionuclides and Radiopharmaceuticals
2.4 Arsenic radionuclides and Radiopharmaceuticals
2.5. Technetium/Rhenium Radionuclides and Radiopharmaceuticals

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4 3 AIM AND SCOPE OF THE WORK

3.1 Aim of Research Project
3.2 Research Plan
3.3 Scope of Work

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5 4 EXPERIMENTAL

4.1 Materials and Methods
4.2 The NRX Irradiation Capsules

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6 5 SEPARATION OF NO-CARRIER-ADDED RADIOACTIVE 92 SCANDIUM FROM NEUTRON IRRADIATED TITANIUM

5.1 Experimental
5.2 Reactor Irradiation of Targets
5.3 Determination of Neutron Flux
5.4 Determination of Radioactive Scandium and Calcium and Monitors
5.6 Preparation of Column for Radioactive Scandium Separation
5.7 Separation of Radioactive Scandium from Neutron Irradiated Titanium
5.8 Determination of Titanium

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7 6 PRODUCTION OF LOW AND HIGH SPECIFIC ACTIVITY COPPER 64 IN A REACTOR

6.1 Reagents and Instruments
6.2 Irradiations
6.3 Determination of Neutron Flux and Activity
6.4 Distribution coefficient Kd Values Measurement
6.5 Absorption Capacity of Zinc
6.6 Preparation of Column for Copper-64 Separation
6.7 Separation of 64 Cu from Neutron Irradiated Zinc
6.8 Determination of Radiozinc and Radiocopper

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8 7 CONCENTRATION OF 68Ga VIA SOLVENT EXTRACTION

7.1 Experimental
7.2 Germanium-68/Gallium-68 Generators
7.3 Physical Characteristics
7.4 External Radiation
7.5 Elution Procedure
7.6 Gallium-68 Elution Efficiency Test
7.7 Germanium-68 Breakthrough Test
7.8 Concentration of Tin
7.9 Extraction
7.10 Radioactivity Measurements
7.11 Complexation and Radiochemical Analyses

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9 8 SEPARATION OF NO-CARRIER-ADDED ARSENIC-77 103 FROM NEUTRON IRRADIATED GERMANIUM

8.1 Experimental
8.2 Target Irradiation
8.3 Preparation of Column
8.4 Separation of 77As from Neutron Irradiated Germanium
8.5 Determination of Arsenic-77, Germanium and Zirconium

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10 9 LEAD CATION AND ALUMINA COLUMNS FOR 105 CONCENTRATION OF 99mTc-PERTECHNETATE

9.1 Materials and Methods
9.2 Target Preparation and Irradiation
9.3 Preparation of 99Mo/99mTc Generator
9.4 Elution Procedure of Tc 99m Generator
9.5 Preparation of Lead (Pb)-Cation Column
9.6 Preparation of Mini Alumina Column
9.7 Concentrator System
9.8 Radionuclide Analyses
9.9 Radiochemical Analyses
9.10 Determination of Pb, Al3+, pH and Clarity
9.11 Radiolabeling Efficiency
9.12 Labeling of MIBI Kit with Concentrated Eluate
9.13 Labeling and Test Procedure

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11 10 LEAD COLUMN FOR CONCENTRATION OF 99mTc- 112 PERTECHNETATEE

10.1 Experimental
10.2 Reactor Irradiation of Targets
10.3 Preparation of 99Mo/99mTc Generator
10.4 188W/188Re Generator
10.5 Sorption of Molybdate, Pertechnetate and Perrhenate on Lead(Pb) Particals
10.6 Preparation of Lead (Pb) Column
10.7 Concentration Method
10.8 Counting Method
10.9 Radiochemical Analyses
10.10 Determination of Al3+, pH and labeling efficiency
10.11 Radiolabeling of DTPA Kit

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12 11 EXTRACTION OF MEDICALLY INTERESTING 116 PERRHENATE (188Re) IN METHYL ETHYL KETONE FOR CONCENTRATION PURPOSE

11.1 Materials and Methods
11.2 Tungsten-188/Rhenium-188 Generator
11.3 Extraction of 188ReO4
11.4 Distillation
11.5 Radionuclide Quality Control
11.6 Radiochemical Quality Control
11.7 Labeling of HEDP Kit with Concentrated Eluate

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13 12 RESULT AND DISCUSSION

 

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14 13 CONCLUSION

 

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15 14 REFERENCES

 

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