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Papers by Sadhana Mukerji

In order to conserve the natural uranium resources, a study has been performed to use the deplete... more In order to conserve the natural uranium resources, a study has been performed to use the depleted uranium and plutonium discharged from the PHWRs. A new fuel cluster design, MOX-888, has been proposed which contains 0.8 wt % PuO 2 mixed with depleted uranium having 0.25 wt % U 235 . It has been found that it is possible to use MOX-888 fuel clusters in the outer 190 channels in conjunction with natural UO 2 bundles in the central 116 channels of the reactor without making any changes in the other hardware of the reactor. The average discharge burnup of fuel (Natural UO 2 and MOX-888) can be improved to more than 10000 MWD/T from the present value of 6700 MWD/T resulting in the substantial saving of natural uranium per year. The paper discusses the physics studies pertaining to this fuel cluster. It also compares the worth of various control devices including primary and secondary shut down systems for the proposed core with present core having all natural uranium fuel clusters.

Journal of Basic and Applied Physics, 2013

Journal of the Korean Physical Society, 2014

ABSTRACT The yields of various fission products in the neutron-induced fission of 238U with the f... more ABSTRACT The yields of various fission products in the neutron-induced fission of 238U with the flux-weightedaveraged neutron energies of 9.35 MeV and 12.52 MeV were determined by using an off-line gammaray spectroscopic technique. The neutrons were generated using the 7Li(p, n) reaction at Bhabha Atomic Research Centre-Tata Institute of Fundamental Research Pelletron facility, Mumbai. The gamma- ray activities of the fission products were counted in a highly-shielded HPGe detector over a period of several weeks to identify the decaying fission products. At both the neutron energies, the fission-yield values are reported for twelve fission product. The results obtained from the present work have been compared with the similar data for mono-energetic neutrons of comparable energy from the literature and are found to be in good agreement. The peak-to-valley (P/V) ratios were calculated from the fission-yield data and were found to decreases for neutron energy from 9.35 to 12.52 MeV, which indicates the role of excitation energy. The effect of the nuclear structure on the fission product-yield is discussed.

Pramana, 2012

The 232 Th(n, γ ) reaction cross-section at average neutron energies of 13.5, 15.5 and 17.28 MeV ... more The 232 Th(n, γ ) reaction cross-section at average neutron energies of 13.5, 15.5 and 17.28 MeV from the 7 Li( p, n) reaction has been determined for the first time using activation and off-line γ -ray spectrometric technique. The 232 Th(n, 2n) cross-section at 17.28 MeV neutron energy has also been determined using the same technique. The experimentally determined 232 Th(n, γ ) and 232 Th(n, 2n) reaction cross-sections from the present work were compared with the evaluated data of ENDF/BVII and JENDL-4.0 and were found to be in good agreement. The present data, along with literature data in a wide range of neutron energies, were interpreted in terms of competition between 232 Th(n, γ ), (n, f ), (n, n f ) and (n, xn) reaction channels. The 232 Th(n, γ ) and 232 Th(n, 2n) reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were found to be in good agreement with the experimental data from the present work but were slightly higher than the literature data at lower neutron energies.

Annals of Nuclear Energy, 2014

Nuclear Physics A

The cumulative yields of various fission products in the 6. 35, 8.53, 9.35 and 12.52 MeV quasi-mo... more The cumulative yields of various fission products in the 6. 35, 8.53, 9.35 and 12.52 MeV quasi-monoenergetic neutron induced fission of 238 U have been determined by using the off-line γ -ray spectrometric technique. The mass chain yields were obtained from the fission product yields by using charge distribution correction. From the mass yield data, the peak-to-valley (P/V) ratio, the average value of light mass ( A L ), heavy mass ( A H ) and thus the average number of neutrons ( υ expt ) were obtained in the 238 U(n, f ) reaction for the above mentioned four neutron energies. The present and literature data in the 238 U(n, f ) and 238 U (γ, f ) reactions at various energies were compared to arrive at the following conclusions. (i) The yields of fission products for A = 133-134, A = 138-140, and A = 143-144 and their complementary products in the 238 U(n, f ) and 238 U(γ, f ) reactions are higher than other fission products, which has been explained from the point of even-odd effect and standard I and standard II asymmetric mode of fission. (ii) The yields of symmetric products increase and thus the peak-to-valley (P/V) ratios decrease with excitation energy, whereas the ν expt values increase with excitation energy. (iii) The variation of A L , A H and υ expt values with excitation energy behave differently in between 238 U(n, f ) and 238 U(γ, f ) reactions, which may be due to the different types of reaction mechanism for the neutron and photon with 238 U. = 6. 35, 8.53, 9.35 and 12.52 MeV; measured fission product yields, mass yield distributions, off-line γ -ray spectrometric technique, peak-to-valley (P/V) ratio, average number of neutrons ( υ expt ), average light mass ( A L ), average heavy mass ( A H )

In order to conserve the natural uranium resources, a study has been performed to use the deplete... more In order to conserve the natural uranium resources, a study has been performed to use the depleted uranium and plutonium discharged from the PHWRs. A new fuel cluster design, MOX-888, has been proposed which contains 0.8 wt % PuO 2 mixed with depleted uranium having 0.25 wt % U 235 . It has been found that it is possible to use MOX-888 fuel clusters in the outer 190 channels in conjunction with natural UO 2 bundles in the central 116 channels of the reactor without making any changes in the other hardware of the reactor. The average discharge burnup of fuel (Natural UO 2 and MOX-888) can be improved to more than 10000 MWD/T from the present value of 6700 MWD/T resulting in the substantial saving of natural uranium per year. The paper discusses the physics studies pertaining to this fuel cluster. It also compares the worth of various control devices including primary and secondary shut down systems for the proposed core with present core having all natural uranium fuel clusters.

Journal of Basic and Applied Physics, 2013

Journal of the Korean Physical Society, 2014

ABSTRACT The yields of various fission products in the neutron-induced fission of 238U with the f... more ABSTRACT The yields of various fission products in the neutron-induced fission of 238U with the flux-weightedaveraged neutron energies of 9.35 MeV and 12.52 MeV were determined by using an off-line gammaray spectroscopic technique. The neutrons were generated using the 7Li(p, n) reaction at Bhabha Atomic Research Centre-Tata Institute of Fundamental Research Pelletron facility, Mumbai. The gamma- ray activities of the fission products were counted in a highly-shielded HPGe detector over a period of several weeks to identify the decaying fission products. At both the neutron energies, the fission-yield values are reported for twelve fission product. The results obtained from the present work have been compared with the similar data for mono-energetic neutrons of comparable energy from the literature and are found to be in good agreement. The peak-to-valley (P/V) ratios were calculated from the fission-yield data and were found to decreases for neutron energy from 9.35 to 12.52 MeV, which indicates the role of excitation energy. The effect of the nuclear structure on the fission product-yield is discussed.

Pramana, 2012

The 232 Th(n, γ ) reaction cross-section at average neutron energies of 13.5, 15.5 and 17.28 MeV ... more The 232 Th(n, γ ) reaction cross-section at average neutron energies of 13.5, 15.5 and 17.28 MeV from the 7 Li( p, n) reaction has been determined for the first time using activation and off-line γ -ray spectrometric technique. The 232 Th(n, 2n) cross-section at 17.28 MeV neutron energy has also been determined using the same technique. The experimentally determined 232 Th(n, γ ) and 232 Th(n, 2n) reaction cross-sections from the present work were compared with the evaluated data of ENDF/BVII and JENDL-4.0 and were found to be in good agreement. The present data, along with literature data in a wide range of neutron energies, were interpreted in terms of competition between 232 Th(n, γ ), (n, f ), (n, n f ) and (n, xn) reaction channels. The 232 Th(n, γ ) and 232 Th(n, 2n) reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were found to be in good agreement with the experimental data from the present work but were slightly higher than the literature data at lower neutron energies.

Annals of Nuclear Energy, 2014

Nuclear Physics A

The cumulative yields of various fission products in the 6. 35, 8.53, 9.35 and 12.52 MeV quasi-mo... more The cumulative yields of various fission products in the 6. 35, 8.53, 9.35 and 12.52 MeV quasi-monoenergetic neutron induced fission of 238 U have been determined by using the off-line γ -ray spectrometric technique. The mass chain yields were obtained from the fission product yields by using charge distribution correction. From the mass yield data, the peak-to-valley (P/V) ratio, the average value of light mass ( A L ), heavy mass ( A H ) and thus the average number of neutrons ( υ expt ) were obtained in the 238 U(n, f ) reaction for the above mentioned four neutron energies. The present and literature data in the 238 U(n, f ) and 238 U (γ, f ) reactions at various energies were compared to arrive at the following conclusions. (i) The yields of fission products for A = 133-134, A = 138-140, and A = 143-144 and their complementary products in the 238 U(n, f ) and 238 U(γ, f ) reactions are higher than other fission products, which has been explained from the point of even-odd effect and standard I and standard II asymmetric mode of fission. (ii) The yields of symmetric products increase and thus the peak-to-valley (P/V) ratios decrease with excitation energy, whereas the ν expt values increase with excitation energy. (iii) The variation of A L , A H and υ expt values with excitation energy behave differently in between 238 U(n, f ) and 238 U(γ, f ) reactions, which may be due to the different types of reaction mechanism for the neutron and photon with 238 U. = 6. 35, 8.53, 9.35 and 12.52 MeV; measured fission product yields, mass yield distributions, off-line γ -ray spectrometric technique, peak-to-valley (P/V) ratio, average number of neutrons ( υ expt ), average light mass ( A L ), average heavy mass ( A H )