Absolute neutron cross section measurements in the energy range between 2 and 5 MeV

An overview of activation cross-section measurements of some neutron and charged-particle induced reactions in Bangladesh

Over the last several decades, our research group has been working on nuclear data measurements using a J-25 Neutron Generator, a TRIGA Mark II Research Reactor and a Tandem Accelerator at Savar, as well as an Am/Be neutron source at Rajshahi. The spectrum of fast neutrons having energies from 0.5 to 20 MeV in the core of the TRIGA reactor as well as from 1.5 to 11 MeV of the Am/Be source was well characterized for validation of evaluated data of neutron threshold reactions. Spectrum-averaged cross sections were determined by integral measurements. The integral values measured at both the reactor and the Am/Be source were compared with the integrated data deduced from measured and evaluated excitation functions of some nuclear reactions given in some data libraries. As example, the details on the integral and integrated cross sections of the 64Zn(n,p)64Cu and 60Ni(n,p)60Co reactions are discussed. In both cases, integral test shows that further improvement of the evaluated excitation function reported in data libraries is needed. The use of a newly developed facility at the 3 MV Tandem Accelerator in measurement of proton induced reaction cross sections in the energy region below 5 MeV is outlined, and new results on the 64Ni(p,n)64Cu and natNi(p,x)61Cu processes below 3 MeV are discussed.

Theoretical estimation of 64Cu production with neutrons emitted during 18F production with a 30MeV medical cyclotron

PURPOSE

This work presents the theoretical estimation of a combined production of ¹⁸F and ⁶⁴Cu isotopes for PET applications. ⁶⁴Cu production is induced in a secondary target by neutrons emitted during a routine ¹⁸F production with a 30MeV cyclotron: protons are used to produce ¹⁸F by means of the ¹⁸O(p,n)¹⁸F reaction on a [¹⁸O]-H₂O target (primary target) and the emitted neutrons are used to produce ⁶⁴Cu by means of the ⁶⁴Zn(n,p)⁶⁴Cu reaction on enriched zinc target (secondary target).

METHODS

Monte Carlo simulations were carried out using Monte Carlo N Particle eXtended (MCNPX) code to evaluate flux and energy spectra of neutrons produced in the primary (Be+[¹⁸O]-H₂O) target by protons and the attenuation of neutron flux in the secondary target. ⁶⁴Cu yield was estimated using an analytical approach based on both TENDL-2015 data library and experimental data selected from EXFOR database.

RESULTS

Theoretical evaluations indicate that about 3.8 MBq/μA of ⁶⁴Cu can be obtained as a secondary, 'side' production with a 30MeV cyclotron, for 2h of irradiation of a proper designed zinc target. Irradiating for 2h with a proton current of 120 μA, a yield of about 457 MBq is expected. Moreover, the most relevant contaminants result to be ^63,65Zn, which can be chemically separated from ⁶⁴Cu contrarily to what happens with proton irradiation of an enriched ⁶⁴Ni target, which provides ⁶⁴Cu mixed to other copper isotopes as contaminants.

CONCLUSIONS

The theoretical study discussed in this paper evaluates the potential of the combined production of ¹⁸F and ⁶⁴Cu for medical purposes, irradiating a properly designed target with 30MeV protons. Interesting yields of ⁶⁴Cu are obtainable and the estimation of contaminants in the irradiated zinc target is discussed.

Determination of 55Mn(n,γ)56Mn reaction cross-section at the neutron energies of 1.12, 2.12, 3.12 and 4.12 MeV

The 55Mn(n,γ)56Mn reaction cross-sections at the neutron energies of 1.12, 2.12, 3.12 and 4.12 MeV were determined by using activation and off-line γ-ray spectrometric technique. The neutron energies of 1.12 and 2.12 MeV were generated from the 7Li(p,n) reaction by using the proton energies of 3 and 4 MeV from the folded tandem ion beam accelerator (FOTIA) at BARC. For the neutron energies of 3.12 and 4.12 MeV, the proton energies used were 5 and 6 MeV from the Pelletron facility at TIFR, Mumbai. The 115In(n,γ)116mIn reaction cross-section was used as the neutron flux monitor. The 55Mn(n,γ)56Mn reaction cross-section at the neutron energies of 4.12 MeV are reported for the first time, whereas at 1.12, 2.12 and 3.12 MeV, they are in between the literature data. The 55Mn(n,γ)56Mn reaction cross-section was also calculated theoretically by using the computer code TALYS 1.6 and EMPIRE 3.2.2. The experimental data of present work are found to be in between the theoretical values of TALYS and EMPIRE.