Measurement of Fission Neutron Spectrum Averaged Gross Sections of some Threshold Reactions on Ruthenium: Small Scale Production of <sup>96</sup>Tn in a Nuclear Reactor

Zaidi, J. H.; Arif, Muhammad; Ahmed, Shamshad; Qureshi, I. H.

doi:10.1524/ract.1999.85.12.9

Cited by 11 publications

(17 citation statements)

References 11 publications

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“…From the measured ratio φ f /φ th for monitor reactions having different thresholds it was concluded that the neutron spectrum used in these irradiations was approximately a fission spectrum [cf. 11,16,17]. A similar conclusion was reached earlier via multiple foil activation and spectrum unfolding technique [18].…”

Section: Determination Of Fast Neutron Flux Densities and K-factorssupporting

confidence: 77%

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added¹⁵³Sm in a nuclear reactor

Abbasi¹,

Zaidi²,

Arif³

et al. 2002

Radiochimica Acta

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Employing the activation technique in combination with radiochemical separations and high-resolution γ -ray spectroscopy fission neutron spectrum averaged cross sections were measured for several (n, 2n), (n, p) and (n, α) reactions on isotopes of europium. Our measurements constitute the first systematic studies. Of special interest was the investigation of 153 Eu(n, p) 153 Sm reaction for the production of no-carrieradded 153 Sm in a nuclear reactor. Using 100% enriched 153 Eu target, 97.21 MBq 153 Sm per batch can be produced which is, however, not sufficient for medical application.

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Section: Determination Of Fast Neutron Flux Densities and K-factorssupporting

confidence: 77%

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added¹⁵³Sm in a nuclear reactor

Abbasi¹,

Zaidi²,

Arif³

et al. 2002

Radiochimica Acta

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“…Both those radionuclides are generally produced using a cyclotron. Fission neutron spectrum averaged cross sections were also measured for 120m,g Sb, 122m,g Sb, 124m,g Sb, 125 Sb 96 Tc reaction was studied [27]. Similarly, 45 Ti (T 1/2 = 3.08 h) is a potentially useful radionuclide for nuclear medicine and for environmental studies.…”

Section: Nuclear Reaction Cross Section Measurementmentioning

confidence: 99%

Development of radiochemistry in Pakistan – 1960 to 2010

et al. 2012

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Development of radiochemistry / Uranium and thorium chemistry / Nuclear reaction cross section / Radioisotope and radiopharmaceutical production / Neutron activation analysis / Separation studies / PINSTECHSummary. 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 131 I. 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.

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“…Radiochemical procedures for the separation of radioactive products from the irradiated target materials were developed and described elsewhere [14,19,30,36]. The radiochemical separation of 45 Ti from the matrix activity (containing radioscandium and radiocalcium) was carried out.…”

Section: Radiochemical Separationsmentioning

confidence: 99%

“…An inherent disadvantage of those reactions, however, is that 95m Tc (T 1/2 = 61 d) is also produced via 96 Mo( p, 2n) 95m Tc and 93 Nb(α, 2n) 95m Tc reactions, whereas 97m Tc (T 1/2 = 90 d) is simultaneously produced via the 95 Mo(d, γ ) 97m Tc reaction. Its production in a nuclear reactor has been reported by our group [19]. The study involved the investigation of the reaction cross section for the nuclear process 96 Ru(n, p) 96 Tc.…”

Section: Introductionmentioning

confidence: 99%

Fission spectrum averaged cross section measurements of some neutron threshold reactions of relevance to medical radionuclide production

Zaidi¹,

Arif²,

Fatima³

et al. 2005

Radiochimica Acta

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Fission neutron spectrum / Neutron threshold reaction / Activation technique / Cross section / Radiochemical separation / Medical radionuclides 45 Ti, 96 Tc, 153 Sm, 153 Gd Summary. A resume is given of radiochemical measurements of nuclear reaction cross sections relevant to the production of some medically important radionuclides carried out at PINSTECH during the last decade. Systematic studies on fission neutron spectrum averaged cross sections of several threshold reactions, like (n, 2n), (n, p) and (n, α), on titanium, ruthenium, europium and dysprosium for the production of 45 Ti, 96 Tc, 153 Sm and 153 Gd are described.

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Measurement of Fission Neutron Spectrum Averaged Gross Sections of some Threshold Reactions on Ruthenium: Small Scale Production of ⁹⁶Tn in a Nuclear Reactor

Cited by 11 publications

References 11 publications

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added¹⁵³Sm in a nuclear reactor

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added¹⁵³Sm in a nuclear reactor

Development of radiochemistry in Pakistan – 1960 to 2010

Fission spectrum averaged cross section measurements of some neutron threshold reactions of relevance to medical radionuclide production

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Measurement of Fission Neutron Spectrum Averaged Gross Sections of some Threshold Reactions on Ruthenium: Small Scale Production of 96Tn in a Nuclear Reactor

Cited by 11 publications

References 11 publications

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added153Sm in a nuclear reactor

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added153Sm in a nuclear reactor

Development of radiochemistry in Pakistan – 1960 to 2010

Fission spectrum averaged cross section measurements of some neutron threshold reactions of relevance to medical radionuclide production

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Measurement of Fission Neutron Spectrum Averaged Gross Sections of some Threshold Reactions on Ruthenium: Small Scale Production of ⁹⁶Tn in a Nuclear Reactor

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added¹⁵³Sm in a nuclear reactor

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added¹⁵³Sm in a nuclear reactor