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The Measurement of Neutron Activation Cross Section of ^(59)Co Below 36 MeV
E. Simeckov,P. Bem,V. Burjan,M. Gotz,M. Honusek,V. Kroha,J. Novak,U. Fischer,S. P. Simakov,R. A. Forrest 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
An accurate knowledge of the cross section for neutron-induced reactions on ^(59)Co is of importance due to use of cobalt as a structural material in fission and fusion reactors, its applicability in neutron dosimetry and for testing theoretical models as well. The thin Co foils (0.25 mm thickness, 99.9% purity, Goodfellow product) were irradiated in the quasi-momoenergetic p-Li neutron field. For the production of the neutron fields, the proton beam from the NPI energy-variable cyclotron U120M at proton energies 19.8, 25.1, 27.6, 30.1, 32.7, 35.0, and 37.4 MeV and thin ^7Li target with carbon stopper were used. The reaction ^7Li(p,n) produces the high-energy quasi-monoenergetic neutrons with tail to lower energies. The flux density and neutron spectra were evaluated by MCNPX code using ^7Li(p,n) cross section measurement of other authors and including correction to the NPI target layout. The time profile of the neutron source strength during the irradiation was monitored by the proton beam current on the neutron-source target, recorded by a calibrated current-to-frequency converter on a PC. Au foils were used as additional monitors. The foil activity determination was performed by the nuclear spectrometry method employing two calibrated HPGe detectors of 23 and 50% efficiency and of FWHM (Full Width Half Maximum) 1.8 keV at 1.3 MeV for gamma-ray measurement. The reaction rates for ^(59)Co(n,p)^(59)Fe, ^(59)Co(n,α)^(56)Mn, ^(59)Co(n,2nα)^(54)Mn, ^(59)Co(n,3n)^(57)Co, ^(59)Co(n,2n)^(58m)Co, and ^(59)Co(n,2n)^(58g)Co were obtained. Integral activation cross sections were estimated. The preliminary results are discussed.
U. Fischer,P. Batistoni,E. Dupont,R. A. Forrest,H. Hendrikson,J. Izquierdo,J. -C. Sublet 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
An overview is presented of the European Fusion File (EFF) and the European Activation File (EAF) efforts which aim at developing qualified nuclear data bases and validated computational tools for nuclear calculations of fusion systems tailored to the specific needs of the European fusion programme. The related tasks are conducted in the frame of the Fusion for Energy (F4E) work programme and are devoted to the evaluation, processing, testing and benchmarking of required nuclear cross section and uncertainty data, the development of computational tools for sensitivity/uncertainty calculations, and to conduct integral benchmark experiments exploiting also new measurement techniques. The data evaluations are integrated into the Joint Evaluated Fission and Fusion File (JEFF) after having passed a series of qualification tests including their validation through computational analyses of integral benchmark experiments.
Integral Neutronics Experiment with a Mock-up of the European HCLL-TBM for ITER
A. Klix,U. Fischer,D. Lebrun-Grandie,P. Batistoni,S. Villari,R. Bottger,K. Fleischer,J. Henniger,D. Gehre,M. Sommer 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
An ITER TBM mock-up made of lithium-lead and sheets of EUROFER was irradiated with short pulses of DT neutrons from the neutron generator at TU Dresden, and time-of-arrival spectra of the slow neutron flux were measured by means of a ^3He counter in two regions inside the mock-up. Fast neutron spectra were obtained by continuous irradiation of the mock-up with DT neutrons and application of a NE-213 spectrometer. The same mock-up was also irradiated at the Frascati Neutron Generator and tritium production rates were measured by means of Li_2CO_3 pellet detectors and LiF thermoluminescense detectors (TLD) inserted into the mock-up. In case of the first type of detectors, the accumulated tritium activity was measured while with the LiF TLD the tritium production rate was obtained from the dose deposited in the detector by the tritium-producing reactions. The Calculation/Experiment ratio for the TPR measurement was nearly 1.0 with an uncertainty of approximately 7.4%. Preliminary results from calculations with FENDL-2.1 and JEFF-3.1.1 suggest a good agreement between experiment and calculation.
Implementation of the Geometry Dependent Hybrid Model in TALYS
A. Yu. Konobeyev,U. Fischer,P. E. Pereslavtsev,A. J. Koning,M. Blann 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The geometry dependent hybrid model (GDH) developed by M.Blann and suppliedby the models for the non-equilibrium cluster emission was implemented inthe TALYS code. A number of subroutines from the ALICE and ALICE/ASH codeswere introduced in TALYS after appropriate modifications. Commoncomputations as those relating to binding energies, the optical model andothers are performed by means of TALYS. The value of the TALYS inputvariable ``preeqmode'' equal to 5 is reserved for the use of the GDHapproach for the calculation of the pre-compound energy distributions ofnucleon and light clusters. A comparison with calculations using theoriginal ALICE and ALICE/ASH codes, on one hand, and experimental data, onthe other hand, is given. The advantages of the implementation of the GDHmodel in the TALYS code are discussed.
A. Yu. Konobeyev,U. Fischer,A. J. Koning,H. Leeb,S. Leray,Y. Yariv 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Intranuclear cascade models implemented in MCNPX, Bertini, ISABEL, CEM, andINCL4 combined with pre- equilibrium models, and evaporation models Dresnerand ABLA are used for the simulation of particle interactions with matter incases where evaluated data are not available. Calculated cross-sections,however, are now available with the TENDL data, a complete collection ofnuclear data libraries in MCNPX format, for all materials, up to 200 MeV. Inthe present work cross-sections of proton induced reactions (p,x) calculatedusing the nuclear models, and TENDL, implemented in MCNPX are compared withexperimental data. Several thousands measured cross-sections for targetnuclei with the atomic number from 12 to 83 at incident proton energies from0 to 150 MeV are taken into account for the comparison. Various statisticalcriteria are applied for the quantification of the difference betweencalculated cross-sections and experimental data. The results obtainedindicate which MCNPX models are best to be used for applications below 150 MeV. Furthermore, they show what degree of accuracy one can expect from theuse of MCNPX models instead of evaluated data.
S. P. Simakov,U. Fischer,Pavel Bem,V. Burjan,M. Gotz,M. Honusek,V. Kroha,J. Novak,E. Simeckova,R. A. Forrest 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
To improve the status of the dosimetry reaction data above 20 MeV, the activation cross sections on Bi, Au, Co and Nb have been measured at the NPI/Rez cyclotron facility with a quasi-monoenergetic p-^7Li neutron source. The present work comprises the computational analysis of this experiment. It includes the Monte-Carlo simulation of the experimental set-up with the MCNPX code and relevant cross section data for proton and neutron induced reactions to predict the energy differential neutron flux in the irradiated foils. This approach has been validated against p-Li neutron spectra measured by different techniques. By making use of the modified unfolding code SAND-II, the dosimetry cross sections have been derived from the detected γ-ray activities. This has brought the new experimental results in the neutron energy domain between 18 and 35 MeV with estimated uncertainty at the level of 10%. They were used for validation of the activation (EAF, IEAF, IRDF) and the general purpose (ENDF) cross section files.
A. Yu. Konobeyev,U. Fischer,S.P. Simakov 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.1
Displacement cross-sections for an advanced assessment of radiation damage rates were obtained for anumber of materials using the arc-dpa model at neutron incident energies from 10-5 eV to 10 GeV. Evaluated data files, CEM03 and ECIS codes, and an approximate approach were applied for the calculationof recoil energy distributions in neutron induced reactions. Three sets of displacement cross-sections based on the use of low-energy data from JEFF-3.3, ENDF/BVIII. 0, and JENDL-4.0u were prepared. Files contain also cross-sections calculated using the standard NRTmodel. Special efforts were made to estimate the uncertainty of obtained displacement cross-sections