Integral cross section of isomeric state formation in (neutron,nucleon) reactions using an Am-Be source.

The present work targeted the study of the isomeric state formation in (n,n') and (n,p) reactions using the spectral emission of an 241Am-Be neutron source which favors the (neutron, nucleon) reactions over the (n, γ) and (n,2n) ones. The integral cross section of the isomeric nuclear states in the neutron-induced nucleon-emission reactions of fast neutrons on 115In, 199Hg, 58Ni, and 195Pt was measured experimentally. The monitor reaction of neutrons was the 115In(n,n')115mIn using the evaluated integral cross section of 269-15+13 mb, which was confirmed to have a constant isomeric ratio in the energy range between ∼1.6 MeV and ∼10 MeV. Integral cross sections for the 199Hg(n,n')199mHg, 58Ni(n,p)58mCo, 58Ni(n,p)58m+gCo and 195Pt(n,n')195mPt reactions were found to be 449 ± 13 mb, 112 ± 34 mb, 343 ± 72 mb and 740 ± 55 mb, respectively. Each experimental value was based on independent measurements of samples irradiated with a constant neutron flux from an 241Am-Be source (having standard emission probability). The experimental results are compared with the integrated cross sections from a new evaluation for neutron induced reactions weighted to standard neutron emission probability distribution. Integral values estimated from theoretical calculations and evaluated libraries were used for the examination of our results. Results confirmed that formation of isomeric states is sensitive to the neutron energy distribution. The behavior of the isomeric ratio of neutron reaction leading to isomeric state formation was found to be useful in order to distinguish between reactions suitable for use as monitor ones (yielding a constant isomeric ratio throughout the emission energy range) and those used to probe the disturbance in the neutron spectral distribution.

Determination of isotopes activity ratio using gamma ray spectroscopy based on neural network model.

The uranium isotopes activity-ratio was determined using in-situ γ-ray spectroscopic measurements and an artificial neural network model. The method was developed to use forward-learn multilayer algorithm. Each layer consists of a perceptron, that controls the forward-learn process, and a mean-square-error mapping for the spectral data from the set of fired perceptrons. The set of output parameters should represent a vector of coefficients for double logarithmic polynomial that distinguish the instrumental efficiency. The forward-learn is controlled by a rejection function which is based on an input set Ψ of parameters that tells the neural layer to accept or reject data points. Each layer maps to the next layer by reducing chi-square-difference with the experimental uncertainty as weight. There are two supervised controls to the network, the maximum deviation from interpolated curve and the assumed initial set of rejection parameters (Ψ0). The model was tested on spectra of known enrichments and gave an excellent agreement with low enriched uranium samples ((1.38 ±â€¯0.14)% and (20 ±â€¯1.55)%). The use of the algorithm on natural uranium ore and association with radium-226 daughters causes increase of uncertainty and deviation of the results from the certified value. The current algorithm provides a practical solution to a wide range of gamma-ray measurement problems encountered for in-situ characterization of uranium-containing materials. These include security, safeguards, fuel assessment, decontamination and decommissioning operations with no collimation or special setup. It is also applicable for large-scale installations.

Multi-source irradiation facility with improved space configuration for neutron activation analysis: Design optimization.

A neutron irradiation facility consisting of six 241Am-Be neutron sources of 30 Ci total activity and 6.6 × 107 n/s total neutron yield is designed. The sources are embedded in a cubic paraffin wax, which plays a dual role as both moderator and reflector. The sample passage and irradiation channel are represented by a cylindrical path of 5 cm diameter passing through the facility core. The proposed design yields a high degree of space symmetry and thermal neutron homogeneity within 98% of flux distribution throughout the irradiated spherical sample of 5 cm diameter. The obtained thermal neutron flux is 8.0 × 104 n/cm2.s over the sample volume, with thermal-to-fast and thermal-to-epithermal ratios of 1.20 and 3.35, respectively. The design is optimized for maximizing the thermal neutron flux at sample position using the MCNP-5 code. The irradiation facility is supposed to be employed principally for neutron activation analysis.

Excitation functions of proton-induced reactions on natFe and enriched 57Fe with particular reference to the production of 57Co.

Excitation functions of the reactions (nat)Fe(p,xn)(55,56,57,58)Co, (nat)Fe(p,x)(51)Cr, (nat)Fe(p,x)(54)Mn, (57)Fe(p,n)(57)Co and (57)Fe(p,alpha)(54)Mn were measured from their respective thresholds up to 18.5MeV, with particular emphasis on data for the production of the radionuclide (57)Co (T(1/2)=271.8d). The conventional stacked-foil technique was used, and the samples for irradiation were prepared by an electroplating or sedimentation process. The measured excitation curves were compared with the data available in the literature as well as with results of nuclear model calculations. From the experimental data, the theoretical yields of the investigated radionuclides were calculated as a function of the proton energy. Over the energy range E(p)=15-->5MeV the calculated yield of (57)Co from the (57)Fe(p,n)(57)Co process amounts to 1.2MBq/microAh and from the (nat)Fe(p,xn)(57)Co reaction to 0.025MBq/microAh. The radionuclidic impurity levels are discussed. Use of highly enriched (57)Fe as target material would lead to formation of high-purity (57)Co.

Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via the (n,p) reaction: evaluation of excitation function and its validation via integral cross-section measurement using a 14 MeV d(Be) neutron source.

Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via (n,p) reactions on the target nuclei 32S, 64Zn, 67Zn, 89Y, (90)Zr and 153Eu, respectively, are discussed. The available information on each excitation function was analysed. From the recommended data set for each reaction the average integrated cross section for a standard 14 MeV d(Be) neutron field was deduced. The spectrum-averaged cross section was also measured experimentally. A comparison of the integrated value with the integral measurement served to validate the excitation function within about 15%. A fast neutron source appears to be much more effective than a fission reactor for production of the above-mentioned radionuclides in a no-carrier-added form via the (n,p) process. In particular, the possibility of production of high specific activity 153Sm is discussed.