The need to ascertain the neutron flux stability after the recent installation of permanent 1.0 m... more The need to ascertain the neutron flux stability after the recent installation of permanent 1.0 mm cadmium lined in the larger outer irradiation channel A-3 was performed in this work. The specific activity ratios, inner-to-outer channel of Nigeria Research Reactor-1 (i.e. A-1/B-4, B- 2/B-4, and B-3/B4) were determined averagely to be 2.06 with a percentage deviation error of 4.63 %. The inner-to-outer with cadmium lined (i.e. A-1/A-3, B-2/A-3, B-3/A-3) was found on the average to be 22.66 with percentage deviation error of 1.58%. Also, the outer-to-outer with cadmium (i.e. A-2/A-3) was obtained to be 11.55 with percentage deviation error of -0.87%. The values of resonance-to-thermal cross section of the inner channels oscillate in a stable trend and for the outer channel B-4, it was observed to be good. These stable trends in the obtained nuclear data I0(α) and Q0(α) values and the specific activity ratios indicates that the neutron flux distributions after installation of a cadmium lined in one of the large outer irradiation channel have not been affected. Thus, a normal routine activation of samples in the channels will continue. The cadmium lined provides a good platform for implementation of epithermal and fast Neutron Activation Analysis in NIRR-1.
The k0-NAA standardization method has been applied to investigate the metal contents of industria... more The k0-NAA standardization method has been applied to investigate the metal contents of industrial effluents collected at several sites in North-Western part of Nigeria. Ten elements (Cr, Co, Ca, Na, Eu, Hf, Th, Dy, Sb and Cs) were determined from 10 samples from the leather, textile and petrochemical industries. The enrichment factors were determined by comparison of the elemental concentration with that of a typical soil from non-industrial area within the same locality of the survey. Some of the industrial effluents had high elevated concentration for chromium, calcium, cobalt, sodium, antimony and dysprosium.
The evaluation of I0 () and Q0 () for Gold, Cupper, Thorium, Uranium and Potassium in
Modified ... more The evaluation of I0 () and Q0 () for Gold, Cupper, Thorium, Uranium and Potassium in Modified Irradiation Site of Nigeria Nuclear Reactor-1 (NIRR-1) was done using Instrumental Neutron Activation Analysis (INAA) and off-line gamma ray spectrometric technique. It was found that before the Cd-lined installation i.e. modification of the large irradiation site (A-3) of NIRR-1, the deviation parameter () was positive with a value of 0.024±0.002 indicating high neutron thermalization. However, after the Cd-line installation, the -parameter was found to be negative with a value of -0.9274 ± 0.016 indicating poor thermalization and as a consequence achieved the purposed of the modification. Further correction for Q0 to Q0 () and I0 to I0 () for the nuclides; Au, Cu, Th, U, and K in the modified large outer irradiation channel A-3 were done. Before Cdlined installation the Q0 () values for Au was 15.05, for Cu was 0.88, for Th was 10.05, for U was 0.86 and for K was 90.37. However, after the Cd installation the Q0 () values for Au increased to 139.64, for Cu increased to 4681.32, for Th increased to16661.89, for U increased to 6141.55 and for K it increased to 133177.92. Also, before Cd-lined installation (BF), I0 () values for Au and Cu were 1485.410, 3.870 and after Cd-lined installation they increased to 13782.47 and 18631.64 respectively.
A Monte Carlo simulation of additional safety rods for NIRR-1 HEU and LEU cores was carried out u... more A Monte Carlo simulation of additional safety rods for NIRR-1 HEU and LEU cores was carried out using the MCNP5 version 1.6 code. Two additional safety control rods having the same material composition as the main central control rod except for the surface area were studied. The following reactor core physics parameters were determined; neutron flux distribution within the core with safety rods withdrawn, control rod (CR) worth for each rod, core excess reactivity, shutdown margin and some kinetic parameters. Results obtained indicate that it would be feasible to include two additional safety control rods to improve safety level of the MNSR with little or no modification to the existing core configuration.
The activity concentration of gross alpha and gross beta in analysed four samples of borehole dri... more The activity concentration of gross alpha and gross beta in analysed four samples of borehole drinking water consumed in Ibrahim Badamasi Babangida University (IBBU) Lapai, Niger State-Nigeria have been measured using the portable single channel gas free proportional counter (MPC2000B-DP) detector. This study was focused on cancer related problems, bio-data of the environment and the radiological effect of the water on the consumers. A higher concentration of alpha and beta were recorded in Hostel block A (DD) with values of 0.085±0.024 BqL-1 and 11.229±0.901 BqL-1 respectively. A lower concentration of alpha and beta were recorded in Faculty of Management Science (AA) with values of 0.006±0.005 BqL-1 and 0.017±0.276 BqL-1 respectively. Out of four sampling sites studied, only Faculty of Management Science fall below the guideline levels of gross alpha (0.5 BqL-1) and gross beta (1.0 BqL-1) in drinking water established by the World Health Organization. These results show that, consumption of groundwater in the other three major borehole drinking water sources may pose significant radiological health hazards through ingestion to the population.
The quest for a versatile standardization method for Instrumental Neutron Activation
Analysis Tec... more The quest for a versatile standardization method for Instrumental Neutron Activation Analysis Technique has been the major driving force behind many research works for the past few decades. The key factor is the desire to overcome the limitation of dependence on multi-elemental standards without sacrificing analytical accuracy and experimental simplicity. Appraisal of the different approaches towards standardization of Neutron Activation Analysis has been carried out; re-visiting the strengths and weaknesses of each standardization method. k0-standardization method is proposed to be the most suitable for its robustness and for providing remedy to the drawbacks in other methods. The basic principle of Neutron Activation Analysis and the superior qualities of k0-standardization has been reviewed.
A permanent Cd-lined irradiation channel has been installed in one of the large outer channel of ... more A permanent Cd-lined irradiation channel has been installed in one of the large outer channel of NIRR-1 for use in epithermal and fast NAA procedures. Measurements performed with Cu-wires and (0.1)%Au-Al foils to characterize the thermal, epithermal column and check its effect on the neutron flux distributions via the specific activities obtained using (n,γ), (n,p) and (n,α) reactions in other channels (A-1, B-2, B-3, and B-4) shows that the flux distributions have not been affected by the Cd-liner in outer channel A-3. The epithermal neutron flux and fast neutron flux in the Cd-lined Channel A-3 were determined using 0.1%Au-Al foil monitor via the 197Au(n, γ)198Au and 27Al(n, p)27Mg reactions and results were 3.96E+09 ncm-2s-1 and 1E+10ncm-2s-1 respectively at an operating power of 15.5kW which correspond to a thermal neutron flux setting of 5.0E+11ncm-2s-1 on the control console. The thermal flux evaluation was 4.89E+11ncm-2s-1 in the inner channels A-1, B-2, B-3 and 2.45E+11ncm-2s-1 in the outer channel B-4. The epithermal flux in the inner channels was 2.55E+10ncm-2s-1 and 1.28E+11ncm-2s-1 in the outer B-4. The epithermal and fast neutron flux in the Cd-lined channel provides a platform for implementation of epithermal and fast NAA techniques in NIRR-1.
We appraised in this study the public awareness of the imminent danger due to elemental concentra... more We appraised in this study the public awareness of the imminent danger due to elemental concentration of the resident in Lapai local government areas and Tatiko, a village under Paikoro local government areas in Niger State, Nigeria about the constant usage of clay potteries in cooking, storage of drinking water, eating and drinking of water. Instrumental Neutron Activation Analysis (INAA) was employed and two irradiation regimes developed based on short lived and long lived radionuclides. The Nigerian Research Reactor-1 was employed and the irradiation time set to five minutes and six hours at operating fluxes of 2.5 × 10 11 n/cm 2 /sec and 5.0 × 10 11 n/cm 2 /sec respectively for the two regimes developed. The gamma-rays from the activated samples were measured using the HPGe detector and twenty four elements; Na, Ta were obtained quantitatively. Arsenic (As) and chromium (Cr) known to be heavy metals fall in the range of 0.64 50 ± 0.16 ppm -1.63 50 ± 0.06 ppm and 29.20 50 ± 0.36 ppm -74.80 50 ± 0.23 ppm respectively. The concentrations of La, Sm, Co, Ba, and Cr also known to be toxic were obtained within the range of 56.20 ± 21 -102.00 ± 43 ppm, 8.14 ± 0.32 -13.10 ± 0.2 ppm, 6.22 ± 0.22 -21.50 ± 0.26 ppm, 218.00 ± 28 -711.00 ± 41 ppm and 29.20 ± 23 -80.80 ± 21 ppm respectively in all the ten composite clay potteries samples. Furthermore the concentrations of Al and Ti in the samples were obtained at percentage levels in the range of 7.605 ± 0.006 % -10.03 50 ± 0.026 % and 0.40 ± 0.03 % -1.02 ± 0.07 % respectively. These detected metals may dissolve from the clay potteries onto the food during cooking, eating, drinking of water or storage of food/water and will result to serious health consequence.
We appraised in this study the public awareness of the imminent danger due to elemental concentra... more We appraised in this study the public awareness of the imminent danger due to elemental concentration of the resident in Lapai local government areas and Tatiko, a village under Paikoro local government areas in Niger State, Nigeria about the constant usage of clay potteries in cooking, storage of drinking water, eating and drinking of water. Instrumental Neutron Activation Analysis (INAA) was employed and two irradiation regimes developed based on short lived and long lived radionuclides. The Nigerian Research Reactor-1 was employed and the irradiation time set to five minutes and six hours at operating fluxes of 2.5 × 10 11 n/cm 2 /sec and 5.0 × 10 11 n/cm 2 /sec respectively for the two regimes developed. The gamma-rays from the activated samples were measured using the HPGe detector and twenty four elements; Na, Ta were obtained quantitatively. Arsenic (As) and chromium (Cr) known to be heavy metals fall in the range of 0.64 50 ± 0.16 ppm -1.63 50 ± 0.06 ppm and 29.20 50 ± 0.36 ppm -74.80 50 ± 0.23 ppm respectively. The concentrations of La, Sm, Co, Ba, and Cr also known to be toxic were obtained within the range of 56.20 ± 21 -102.00 ± 43 ppm, 8.14 ± 0.32 -13.10 ± 0.2 ppm, 6.22 ± 0.22 -21.50 ± 0.26 ppm, 218.00 ± 28 -711.00 ± 41 ppm and 29.20 ± 23 -80.80 ± 21 ppm respectively in all the ten composite clay potteries samples. Furthermore the concentrations of Al and Ti in the samples were obtained at percentage levels in the range of 7.605 ± 0.006 % -10.03 50 ± 0.026 % and 0.40 ± 0.03 % -1.02 ± 0.07 % respectively. These detected metals may dissolve from the clay potteries onto the food during cooking, eating, drinking of water or storage of food/water and will result to serious health consequence.
The need to ascertain the neutron flux stability after the recent installation of permanent 1.0 m... more The need to ascertain the neutron flux stability after the recent installation of permanent 1.0 mm cadmium lined in the larger outer irradiation channel A-3 was performed in this work. The specific activity ratios, inner-to-outer channel of Nigeria Research Reactor-1 (i.e. A-1/B-4, B- 2/B-4, and B-3/B4) were determined averagely to be 2.06 with a percentage deviation error of 4.63 %. The inner-to-outer with cadmium lined (i.e. A-1/A-3, B-2/A-3, B-3/A-3) was found on the average to be 22.66 with percentage deviation error of 1.58%. Also, the outer-to-outer with cadmium (i.e. A-2/A-3) was obtained to be 11.55 with percentage deviation error of -0.87%. The values of resonance-to-thermal cross section of the inner channels oscillate in a stable trend and for the outer channel B-4, it was observed to be good. These stable trends in the obtained nuclear data I0(α) and Q0(α) values and the specific activity ratios indicates that the neutron flux distributions after installation of a cadmium lined in one of the large outer irradiation channel have not been affected. Thus, a normal routine activation of samples in the channels will continue. The cadmium lined provides a good platform for implementation of epithermal and fast Neutron Activation Analysis in NIRR-1.
The k0-NAA standardization method has been applied to investigate the metal contents of industria... more The k0-NAA standardization method has been applied to investigate the metal contents of industrial effluents collected at several sites in North-Western part of Nigeria. Ten elements (Cr, Co, Ca, Na, Eu, Hf, Th, Dy, Sb and Cs) were determined from 10 samples from the leather, textile and petrochemical industries. The enrichment factors were determined by comparison of the elemental concentration with that of a typical soil from non-industrial area within the same locality of the survey. Some of the industrial effluents had high elevated concentration for chromium, calcium, cobalt, sodium, antimony and dysprosium.
The evaluation of I0 () and Q0 () for Gold, Cupper, Thorium, Uranium and Potassium in
Modified ... more The evaluation of I0 () and Q0 () for Gold, Cupper, Thorium, Uranium and Potassium in Modified Irradiation Site of Nigeria Nuclear Reactor-1 (NIRR-1) was done using Instrumental Neutron Activation Analysis (INAA) and off-line gamma ray spectrometric technique. It was found that before the Cd-lined installation i.e. modification of the large irradiation site (A-3) of NIRR-1, the deviation parameter () was positive with a value of 0.024±0.002 indicating high neutron thermalization. However, after the Cd-line installation, the -parameter was found to be negative with a value of -0.9274 ± 0.016 indicating poor thermalization and as a consequence achieved the purposed of the modification. Further correction for Q0 to Q0 () and I0 to I0 () for the nuclides; Au, Cu, Th, U, and K in the modified large outer irradiation channel A-3 were done. Before Cdlined installation the Q0 () values for Au was 15.05, for Cu was 0.88, for Th was 10.05, for U was 0.86 and for K was 90.37. However, after the Cd installation the Q0 () values for Au increased to 139.64, for Cu increased to 4681.32, for Th increased to16661.89, for U increased to 6141.55 and for K it increased to 133177.92. Also, before Cd-lined installation (BF), I0 () values for Au and Cu were 1485.410, 3.870 and after Cd-lined installation they increased to 13782.47 and 18631.64 respectively.
A Monte Carlo simulation of additional safety rods for NIRR-1 HEU and LEU cores was carried out u... more A Monte Carlo simulation of additional safety rods for NIRR-1 HEU and LEU cores was carried out using the MCNP5 version 1.6 code. Two additional safety control rods having the same material composition as the main central control rod except for the surface area were studied. The following reactor core physics parameters were determined; neutron flux distribution within the core with safety rods withdrawn, control rod (CR) worth for each rod, core excess reactivity, shutdown margin and some kinetic parameters. Results obtained indicate that it would be feasible to include two additional safety control rods to improve safety level of the MNSR with little or no modification to the existing core configuration.
The activity concentration of gross alpha and gross beta in analysed four samples of borehole dri... more The activity concentration of gross alpha and gross beta in analysed four samples of borehole drinking water consumed in Ibrahim Badamasi Babangida University (IBBU) Lapai, Niger State-Nigeria have been measured using the portable single channel gas free proportional counter (MPC2000B-DP) detector. This study was focused on cancer related problems, bio-data of the environment and the radiological effect of the water on the consumers. A higher concentration of alpha and beta were recorded in Hostel block A (DD) with values of 0.085±0.024 BqL-1 and 11.229±0.901 BqL-1 respectively. A lower concentration of alpha and beta were recorded in Faculty of Management Science (AA) with values of 0.006±0.005 BqL-1 and 0.017±0.276 BqL-1 respectively. Out of four sampling sites studied, only Faculty of Management Science fall below the guideline levels of gross alpha (0.5 BqL-1) and gross beta (1.0 BqL-1) in drinking water established by the World Health Organization. These results show that, consumption of groundwater in the other three major borehole drinking water sources may pose significant radiological health hazards through ingestion to the population.
The quest for a versatile standardization method for Instrumental Neutron Activation
Analysis Tec... more The quest for a versatile standardization method for Instrumental Neutron Activation Analysis Technique has been the major driving force behind many research works for the past few decades. The key factor is the desire to overcome the limitation of dependence on multi-elemental standards without sacrificing analytical accuracy and experimental simplicity. Appraisal of the different approaches towards standardization of Neutron Activation Analysis has been carried out; re-visiting the strengths and weaknesses of each standardization method. k0-standardization method is proposed to be the most suitable for its robustness and for providing remedy to the drawbacks in other methods. The basic principle of Neutron Activation Analysis and the superior qualities of k0-standardization has been reviewed.
A permanent Cd-lined irradiation channel has been installed in one of the large outer channel of ... more A permanent Cd-lined irradiation channel has been installed in one of the large outer channel of NIRR-1 for use in epithermal and fast NAA procedures. Measurements performed with Cu-wires and (0.1)%Au-Al foils to characterize the thermal, epithermal column and check its effect on the neutron flux distributions via the specific activities obtained using (n,γ), (n,p) and (n,α) reactions in other channels (A-1, B-2, B-3, and B-4) shows that the flux distributions have not been affected by the Cd-liner in outer channel A-3. The epithermal neutron flux and fast neutron flux in the Cd-lined Channel A-3 were determined using 0.1%Au-Al foil monitor via the 197Au(n, γ)198Au and 27Al(n, p)27Mg reactions and results were 3.96E+09 ncm-2s-1 and 1E+10ncm-2s-1 respectively at an operating power of 15.5kW which correspond to a thermal neutron flux setting of 5.0E+11ncm-2s-1 on the control console. The thermal flux evaluation was 4.89E+11ncm-2s-1 in the inner channels A-1, B-2, B-3 and 2.45E+11ncm-2s-1 in the outer channel B-4. The epithermal flux in the inner channels was 2.55E+10ncm-2s-1 and 1.28E+11ncm-2s-1 in the outer B-4. The epithermal and fast neutron flux in the Cd-lined channel provides a platform for implementation of epithermal and fast NAA techniques in NIRR-1.
We appraised in this study the public awareness of the imminent danger due to elemental concentra... more We appraised in this study the public awareness of the imminent danger due to elemental concentration of the resident in Lapai local government areas and Tatiko, a village under Paikoro local government areas in Niger State, Nigeria about the constant usage of clay potteries in cooking, storage of drinking water, eating and drinking of water. Instrumental Neutron Activation Analysis (INAA) was employed and two irradiation regimes developed based on short lived and long lived radionuclides. The Nigerian Research Reactor-1 was employed and the irradiation time set to five minutes and six hours at operating fluxes of 2.5 × 10 11 n/cm 2 /sec and 5.0 × 10 11 n/cm 2 /sec respectively for the two regimes developed. The gamma-rays from the activated samples were measured using the HPGe detector and twenty four elements; Na, Ta were obtained quantitatively. Arsenic (As) and chromium (Cr) known to be heavy metals fall in the range of 0.64 50 ± 0.16 ppm -1.63 50 ± 0.06 ppm and 29.20 50 ± 0.36 ppm -74.80 50 ± 0.23 ppm respectively. The concentrations of La, Sm, Co, Ba, and Cr also known to be toxic were obtained within the range of 56.20 ± 21 -102.00 ± 43 ppm, 8.14 ± 0.32 -13.10 ± 0.2 ppm, 6.22 ± 0.22 -21.50 ± 0.26 ppm, 218.00 ± 28 -711.00 ± 41 ppm and 29.20 ± 23 -80.80 ± 21 ppm respectively in all the ten composite clay potteries samples. Furthermore the concentrations of Al and Ti in the samples were obtained at percentage levels in the range of 7.605 ± 0.006 % -10.03 50 ± 0.026 % and 0.40 ± 0.03 % -1.02 ± 0.07 % respectively. These detected metals may dissolve from the clay potteries onto the food during cooking, eating, drinking of water or storage of food/water and will result to serious health consequence.
We appraised in this study the public awareness of the imminent danger due to elemental concentra... more We appraised in this study the public awareness of the imminent danger due to elemental concentration of the resident in Lapai local government areas and Tatiko, a village under Paikoro local government areas in Niger State, Nigeria about the constant usage of clay potteries in cooking, storage of drinking water, eating and drinking of water. Instrumental Neutron Activation Analysis (INAA) was employed and two irradiation regimes developed based on short lived and long lived radionuclides. The Nigerian Research Reactor-1 was employed and the irradiation time set to five minutes and six hours at operating fluxes of 2.5 × 10 11 n/cm 2 /sec and 5.0 × 10 11 n/cm 2 /sec respectively for the two regimes developed. The gamma-rays from the activated samples were measured using the HPGe detector and twenty four elements; Na, Ta were obtained quantitatively. Arsenic (As) and chromium (Cr) known to be heavy metals fall in the range of 0.64 50 ± 0.16 ppm -1.63 50 ± 0.06 ppm and 29.20 50 ± 0.36 ppm -74.80 50 ± 0.23 ppm respectively. The concentrations of La, Sm, Co, Ba, and Cr also known to be toxic were obtained within the range of 56.20 ± 21 -102.00 ± 43 ppm, 8.14 ± 0.32 -13.10 ± 0.2 ppm, 6.22 ± 0.22 -21.50 ± 0.26 ppm, 218.00 ± 28 -711.00 ± 41 ppm and 29.20 ± 23 -80.80 ± 21 ppm respectively in all the ten composite clay potteries samples. Furthermore the concentrations of Al and Ti in the samples were obtained at percentage levels in the range of 7.605 ± 0.006 % -10.03 50 ± 0.026 % and 0.40 ± 0.03 % -1.02 ± 0.07 % respectively. These detected metals may dissolve from the clay potteries onto the food during cooking, eating, drinking of water or storage of food/water and will result to serious health consequence.
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Papers by Raymond Njinga
cadmium lined in the larger outer irradiation channel A-3 was performed in this work. The
specific activity ratios, inner-to-outer channel of Nigeria Research Reactor-1 (i.e. A-1/B-4, B-
2/B-4, and B-3/B4) were determined averagely to be 2.06 with a percentage deviation error of
4.63 %. The inner-to-outer with cadmium lined (i.e. A-1/A-3, B-2/A-3, B-3/A-3) was found on the
average to be 22.66 with percentage deviation error of 1.58%. Also, the outer-to-outer with
cadmium (i.e. A-2/A-3) was obtained to be 11.55 with percentage deviation error of -0.87%. The
values of resonance-to-thermal cross section of the inner channels oscillate in a stable trend and
for the outer channel B-4, it was observed to be good. These stable trends in the obtained
nuclear data I0(α) and Q0(α) values and the specific activity ratios indicates that the neutron flux
distributions after installation of a cadmium lined in one of the large outer irradiation channel
have not been affected. Thus, a normal routine activation of samples in the channels will
continue. The cadmium lined provides a good platform for implementation of epithermal and fast
Neutron Activation Analysis in NIRR-1.
collected at several sites in North-Western part of Nigeria. Ten elements (Cr, Co, Ca, Na, Eu, Hf, Th, Dy, Sb and
Cs) were determined from 10 samples from the leather, textile and petrochemical industries. The enrichment factors
were determined by comparison of the elemental concentration with that of a typical soil from non-industrial area
within the same locality of the survey. Some of the industrial effluents had high elevated concentration for
chromium, calcium, cobalt, sodium, antimony and dysprosium.
Modified Irradiation Site of Nigeria Nuclear Reactor-1 (NIRR-1) was done using
Instrumental Neutron Activation Analysis (INAA) and off-line gamma ray spectrometric
technique. It was found that before the Cd-lined installation i.e. modification of the large
irradiation site (A-3) of NIRR-1, the deviation parameter () was positive with a value of
0.024±0.002 indicating high neutron thermalization. However, after the Cd-line
installation, the -parameter was found to be negative with a value of -0.9274 ± 0.016
indicating poor thermalization and as a consequence achieved the purposed of the
modification. Further correction for Q0 to Q0 () and I0 to I0 () for the nuclides; Au, Cu,
Th, U, and K in the modified large outer irradiation channel A-3 were done. Before Cdlined
installation the Q0 () values for Au was 15.05, for Cu was 0.88, for Th was 10.05,
for U was 0.86 and for K was 90.37. However, after the Cd installation the Q0 () values
for Au increased to 139.64, for Cu increased to 4681.32, for Th increased to16661.89, for
U increased to 6141.55 and for K it increased to 133177.92. Also, before Cd-lined
installation (BF), I0 () values for Au and Cu were 1485.410, 3.870 and after Cd-lined
installation they increased to 13782.47 and 18631.64 respectively.
the MCNP5 version 1.6 code. Two additional safety control rods having the same material composition as
the main central control rod except for the surface area were studied. The following reactor core physics
parameters were determined; neutron flux distribution within the core with safety rods withdrawn, control
rod (CR) worth for each rod, core excess reactivity, shutdown margin and some kinetic parameters.
Results obtained indicate that it would be feasible to include two additional safety control rods to
improve safety level of the MNSR with little or no modification to the existing core configuration.
consumed in Ibrahim Badamasi Babangida University (IBBU) Lapai, Niger State-Nigeria have been measured
using the portable single channel gas free proportional counter (MPC2000B-DP) detector. This study was
focused on cancer related problems, bio-data of the environment and the radiological effect of the water on the
consumers. A higher concentration of alpha and beta were recorded in Hostel block A (DD) with values of
0.085±0.024 BqL-1 and 11.229±0.901 BqL-1 respectively. A lower concentration of alpha and beta were
recorded in Faculty of Management Science (AA) with values of 0.006±0.005 BqL-1 and 0.017±0.276 BqL-1
respectively. Out of four sampling sites studied, only Faculty of Management Science fall below the guideline
levels of gross alpha (0.5 BqL-1) and gross beta (1.0 BqL-1) in drinking water established by the World Health
Organization. These results show that, consumption of groundwater in the other three major borehole drinking
water sources may pose significant radiological health hazards through ingestion to the population.
Analysis Technique has been the major driving force behind many research works for the
past few decades. The key factor is the desire to overcome the limitation of dependence on
multi-elemental standards without sacrificing analytical accuracy and experimental
simplicity. Appraisal of the different approaches towards standardization of Neutron
Activation Analysis has been carried out; re-visiting the strengths and weaknesses of each
standardization method. k0-standardization method is proposed to be the most suitable for its
robustness and for providing remedy to the drawbacks in other methods. The basic principle
of Neutron Activation Analysis and the superior qualities of k0-standardization has been
reviewed.
cadmium lined in the larger outer irradiation channel A-3 was performed in this work. The
specific activity ratios, inner-to-outer channel of Nigeria Research Reactor-1 (i.e. A-1/B-4, B-
2/B-4, and B-3/B4) were determined averagely to be 2.06 with a percentage deviation error of
4.63 %. The inner-to-outer with cadmium lined (i.e. A-1/A-3, B-2/A-3, B-3/A-3) was found on the
average to be 22.66 with percentage deviation error of 1.58%. Also, the outer-to-outer with
cadmium (i.e. A-2/A-3) was obtained to be 11.55 with percentage deviation error of -0.87%. The
values of resonance-to-thermal cross section of the inner channels oscillate in a stable trend and
for the outer channel B-4, it was observed to be good. These stable trends in the obtained
nuclear data I0(α) and Q0(α) values and the specific activity ratios indicates that the neutron flux
distributions after installation of a cadmium lined in one of the large outer irradiation channel
have not been affected. Thus, a normal routine activation of samples in the channels will
continue. The cadmium lined provides a good platform for implementation of epithermal and fast
Neutron Activation Analysis in NIRR-1.
collected at several sites in North-Western part of Nigeria. Ten elements (Cr, Co, Ca, Na, Eu, Hf, Th, Dy, Sb and
Cs) were determined from 10 samples from the leather, textile and petrochemical industries. The enrichment factors
were determined by comparison of the elemental concentration with that of a typical soil from non-industrial area
within the same locality of the survey. Some of the industrial effluents had high elevated concentration for
chromium, calcium, cobalt, sodium, antimony and dysprosium.
Modified Irradiation Site of Nigeria Nuclear Reactor-1 (NIRR-1) was done using
Instrumental Neutron Activation Analysis (INAA) and off-line gamma ray spectrometric
technique. It was found that before the Cd-lined installation i.e. modification of the large
irradiation site (A-3) of NIRR-1, the deviation parameter () was positive with a value of
0.024±0.002 indicating high neutron thermalization. However, after the Cd-line
installation, the -parameter was found to be negative with a value of -0.9274 ± 0.016
indicating poor thermalization and as a consequence achieved the purposed of the
modification. Further correction for Q0 to Q0 () and I0 to I0 () for the nuclides; Au, Cu,
Th, U, and K in the modified large outer irradiation channel A-3 were done. Before Cdlined
installation the Q0 () values for Au was 15.05, for Cu was 0.88, for Th was 10.05,
for U was 0.86 and for K was 90.37. However, after the Cd installation the Q0 () values
for Au increased to 139.64, for Cu increased to 4681.32, for Th increased to16661.89, for
U increased to 6141.55 and for K it increased to 133177.92. Also, before Cd-lined
installation (BF), I0 () values for Au and Cu were 1485.410, 3.870 and after Cd-lined
installation they increased to 13782.47 and 18631.64 respectively.
the MCNP5 version 1.6 code. Two additional safety control rods having the same material composition as
the main central control rod except for the surface area were studied. The following reactor core physics
parameters were determined; neutron flux distribution within the core with safety rods withdrawn, control
rod (CR) worth for each rod, core excess reactivity, shutdown margin and some kinetic parameters.
Results obtained indicate that it would be feasible to include two additional safety control rods to
improve safety level of the MNSR with little or no modification to the existing core configuration.
consumed in Ibrahim Badamasi Babangida University (IBBU) Lapai, Niger State-Nigeria have been measured
using the portable single channel gas free proportional counter (MPC2000B-DP) detector. This study was
focused on cancer related problems, bio-data of the environment and the radiological effect of the water on the
consumers. A higher concentration of alpha and beta were recorded in Hostel block A (DD) with values of
0.085±0.024 BqL-1 and 11.229±0.901 BqL-1 respectively. A lower concentration of alpha and beta were
recorded in Faculty of Management Science (AA) with values of 0.006±0.005 BqL-1 and 0.017±0.276 BqL-1
respectively. Out of four sampling sites studied, only Faculty of Management Science fall below the guideline
levels of gross alpha (0.5 BqL-1) and gross beta (1.0 BqL-1) in drinking water established by the World Health
Organization. These results show that, consumption of groundwater in the other three major borehole drinking
water sources may pose significant radiological health hazards through ingestion to the population.
Analysis Technique has been the major driving force behind many research works for the
past few decades. The key factor is the desire to overcome the limitation of dependence on
multi-elemental standards without sacrificing analytical accuracy and experimental
simplicity. Appraisal of the different approaches towards standardization of Neutron
Activation Analysis has been carried out; re-visiting the strengths and weaknesses of each
standardization method. k0-standardization method is proposed to be the most suitable for its
robustness and for providing remedy to the drawbacks in other methods. The basic principle
of Neutron Activation Analysis and the superior qualities of k0-standardization has been
reviewed.