Trace element intake and dietary status of nuts consumed in Pakistan: study using INAA

Development of radiochemistry in Pakistan – 1960 to 2010

With the inception of Pakistan Atomic Energy Commission (PAEC) in 1956, peaceful uses of atomic energy commenced for the benefit of scientific community as well as masses of Pakistan. Radiochemistry played a vital role right from the beginning. The research and development in this field accelerated soon after the criticality of the first research reactor named as Pakistan Research Reactor (PARR- 1) at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), Islamabad. The first radioisotope produced at PARR-1 for application in nuclear medicine was 131I. Later on, many other radioisotopes were prepared and radiopharmaceuticals were synthesised for their use in industry and hospitals. Besides providing pure radioactive tracers for nuclear medicine, radiochemistry also enhanced the detection limit of impurities at all stages of nuclear fuel cycle for power generation. In 1983, research in the field of nuclear data measurement began. The main aim was to identify suitable conditions for the production of radionuclides for cancer diagnostics, treatment and therapy. With the establishment of a second research reactor (PARR-2) at PINSTECH, research in neutron activation analysis, radioisotope production and separation studies gained more momentum and many research articles were published. Solvent extraction, adsorption and ion-exchange were the main routes of separation in those studies. Separation of heavy metals and treatment of waste generated in a nuclear power plant are other important aspects related to environmental restoration and nuclear waste management, where radiochemistry is required. In future, work in radiochemistry will be continued on similar lines to develop novel radiopharmaceuticals, identify indigenous schemes for nuclear waste management and work out intelligent procedures for material characterization for benefit to mankind, especially the people of Pakistan.

Analysis of municipal waste dump soil using a low power reactor: a study by instrumental neutron activation analysis

Soil samples from an open waste dump site and a background sample from a site located beside Kashmir Highway near sector H-11, Islamabad, were analyzed for 36 major, minor and trace elements. Suitable instrumental neutron activation analysis (INAA) methodology was developed through optimization of irradiation, cooling and counting protocols using a 27 kW low power miniature neutron source reactor (MNSR). Large variations in the composition of soil samples taken from the dump site were observed and it was found that most of the elements including Al, Ca, Ti, As, Br, Ce, Co, Cs, Ga, Hf, Mn, Nd, La, Sb, Sc, Sm, Sn, Ta, Tb Th, V, Yb, Zn, Eu, Se, and Zr, in the background soil lie in the concentration range of the dump soil sample. However, Fe, K, Mg, Na, Ba, Rb, Sr, U, Zn, Hg and Sb were found to be in higher amounts in the dump site samples. To validate the developed INAA methodology and to ensure the accuracy and precision of the results, IAEA Lake Sediment (SL-1) and IAEA Soil-7 (S-7) were analyzed as control materials.