Double-differential cross sections for the production of neutrons from Pb, W, Zr, Cu, and Al targets irradiated with 0.8-, 1.0-, and 1.6-GeV protons

Trebukhovsky, Yu.V.; Titarenko, Yu. E.; Batyaev, V. F.; Mulambetov, R. D.; Mulambetova, S. V.; Smirnov, G. N.; Lipatov, K. A.; Koldobsky, Alexander; Zhivun, V. M.; Barashenkov, V.S.; Kumawat, H.; Mashnik, S. G.; Prael, R.E.

doi:10.1134/1.1858552

Cited by 11 publications

(11 citation statements)

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“…The evaluation of the modeling of the secondary-proton spectra is unreliable because of the lack of complete experimental information. As noted in [4,8], the agreement between the computational and experimental results is good for the neutron spectra calculated with the LAHET program. Consequently, the computed reaction rates calculated with the normalized excitation functions and the computed neutron and proton spectra on the surface of and inside the target were used to determine the corresponding computed spectrum-averaged cross section for the reactions (n, xn), (n, α), (n, p), and (p, xn):…”

Section: Irradiation Of a Lead Target And Determination Of The Numbersupporting

confidence: 50%

“…3) the production cross section of product nuclei in thin lead targets, both enriched with [206][207][208] Pb and with the naturally occurring composition, as well as 209 Bi for proton energy 0.04, 0.07, 0.1, 0.15, 0.25, 0.4, 0.6, 0.8, 1.2, 1.6, and 2.6 GeV [6,7]; and 4) the double-differential cross sections for neutron generation under irradiation of Pb, W, Zr, Cu, Al, and Na thin targets by 0.8, 1, and 1.6 GeV protons, using a time-of-flight spectrometer [4,8].…”

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Experimental determination and computational modeling of threshold reaction rates in 0.8 GeV proton-irradiated lead target

et al. 2009

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The results of an experimental determination and computational modeling of the rates of threshold reactions on 209 the external surface of and inside a thick lead target irradiated by 0.8 GeV protons are presented. The reaction rates were measured by γ spectrometry using Ge and (Ge-Li) detectors with resolution 1.8 and 2.9 keV, respectively, on the 1332 keV γ-line. Measurements of 2467 independent and cumulative threshold reaction rates were performed with 244 samples. The LAHET program was used for computational modeling of the results. The MENDL and MENDL2p libraries, the EXFOR databases, and the LAHET program were used to construct the excitation functions of the nuclides formed. The experimentally measured reaction rates are compared with the computed rates. The neutron and proton fluxes along the target, both on its external surface and in the interior volume, were calculated using the experimental threshold reaction rates and the computed cross sections of the reactions averaged over the spectrum of the neutrons and protons. The reaction rates measured inside and on the surface of a natural-lead target were used to determine the accuracy with which the target's activity is measured.Two types of facilities are now being designed and built on the basis of high-current accelerators. The first type consists of neutron sources which can be used successfully in fundamental and applied physics, materials science, and biology; the second type consists of electronuclear facilities for transmutation of radioactive wastes and, possibly, the production of electricity. Even though there are structural differences, which are due to the purpose of a facility, the two types have a unit in common -a target which is bombarded by a proton beam from a high-current linear accelerator. Ordinarily, a Pb + Bi eutectic, Pb, Hg (liquid targets), or W, Ta (solid targets) are used as target materials.The presence of a target unit, which is used to generate neutrons of a hadron-nuclear cascade, in nuclear facilities raises the problem of determining its basic neutron-physical parameters. Individual parameters directly affect the nuclear-physical characteristics of the blanket (the total yield and spectrum of neutrons from the target); other parameters affect the nuclear-physical characteristics of the target itself (energy release, radiation resistance, production of residual prod-

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Section: Irradiation Of a Lead Target And Determination Of The Numbersupporting

confidence: 50%

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confidence: 99%

Experimental determination and computational modeling of threshold reaction rates in 0.8 GeV proton-irradiated lead target

et al. 2009

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“…Furthermore, it is well known that the spectra of secondary spallation neutrons and heavy extended targets are close to evaporative spectra, whose average energy is ~3 MeV. Only ~10% of such neutrons have energy about 14.5 MeV, the fraction of cascade neutrons with energy above ~0.1 GeV, initiating fission of 232 Th and 238 U, is even lower [11]. Thus, many low-energy neutrons but few cascade neutrons, giving rise to fission of 232 Th and 238 U, are present in the system.…”

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confidence: 97%

“…Many computational-theoretical investigations and numerous experiments studying neutron generation and energy production in heavy targets in proton beams are now being conducted. Examples are [4][5][6][7][8][9][10][11][12][13].…”

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Analysis of the main nuclear-physical characteristics of the interaction of proton beams with heavy metal targets

et al. 2008

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It is shown that the concept of relativistic heavy-nuclear energy is untenable. Using a large group of different experiments in the proton energy range 0. it is demonstrated that the high-energy hadron transport program SHIELD, which is based on modern nuclear models, has predictive power. The interaction of protons with energy ranging from 0.1 to 100 GeV with a simple model system target + blanket, containing heavy elements (lead, thorium, depleted and enriched uranium), is examined. The energy release, neutron production, and production of fissile isotopes in the system are calculated. It is found that for all values of the proton energy which are considered the useful yield of energy in weakly fissile media is inadequate (thorium, depleted uranium) and is completely absent in non-fissile media (lead). A blanket containing enriched uranium will be necessary in order to use the scheme for useful production of energy. In this variant, the optimal proton energy is 1-3 GeV, which corresponds to the conventional concept of electronuclear facilities whose main purpose is to transmute nuclear wastes and produce electricity at the same time.The concept of commercial production of energy using accelerators to accelerate heavy charged particles has been discussed since the beginning of the 1950s. According to this concept, a beam of protons or ions with sufficiently high energy should generate a large number of neutrons on interacting with a heavy target. Facilities which function according to this principle are said to be electronuclear facilities. The accelerator must be a high-current accelerator in order to produce more neutrons, and for this reason the target is a complicated technical system. An advantage of electronuclear facilities over conventional nuclear reactors is that there is no possibility of reactivity accidents.

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“…Such spectrometers handle the conditions of "good" geometry and allow high resolution mea surements over a very wide range of energies from a few hundred keV up to a few GeV. The time of flight spectrometers at LANL [19,20], JINR [21,22], KEK [23], Saclay [24] and ITEP [25,26] are examples of such detectors. The drawbacks of this method are: (1) a strong neu tron energy dependence of the energy resolution which is impaired with energy, (2) the need for time tag to the neutron production event, (3) necessity of fulfilling the "good" geometry condition, and (4) obligatory long range distance, a path length, from the neutron source, which sharply decreases the solid angle of neutron detection, deteriorates the background condition and increases the measurement time.…”

Section: Methods Of High Energymentioning

confidence: 99%

High-energy neutron spectrometry

Yurevich

2012

Phys. Part. Nuclei

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We review progress made in the last quarter of a century in the field of neutron spectrometry over a wide energy range from ~1 MeV to a few tens of GeV. We consider spectrometers and detectors constructed in various laboratories for neutron measurements in numerous fundamental and applied studies. We discuss the results of works devoted to the development of experimental methods and the elaboration of new detec tors. We pursue some promising avenues of further investigations.

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Double-differential cross sections for the production of neutrons from Pb, W, Zr, Cu, and Al targets irradiated with 0.8-, 1.0-, and 1.6-GeV protons

Cited by 11 publications

References 27 publications

Experimental determination and computational modeling of threshold reaction rates in 0.8 GeV proton-irradiated lead target

Experimental determination and computational modeling of threshold reaction rates in 0.8 GeV proton-irradiated lead target

Analysis of the main nuclear-physical characteristics of the interaction of proton beams with heavy metal targets

High-energy neutron spectrometry

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