Spallation neutron production and the current intra-nuclear cascade and transport codes

Filges, D.; Goldenbaum, F.; Enke, M.; Galin, J.; Herbach, C.-M.; Hilscher, D.; Jahnke, U.; Letourneau, A.; Lott, B.; Neef, R.D.; Nünighoff, K.; Paul, N.; Péghaire, A.; Pieńkowski, L.; Schaal, H.; Schröder, U.; Sterzenbach, G.; Tietze, Anna; Tishchenko, V. G.; Tōke, J.; Wohlmuther, M.

doi:10.1007/s100500170058

Cited by 27 publications

(9 citation statements)

References 1 publication

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“…We remind that the INC code ISABEL has been extensively tested and shown to provide an overall reasonable description of the properties of the primary residues. For representative comparisons, we first mention the recent work of Paradella et al [44] on 136 Xe (200 MeV/nucleon) + p. Moreover, Filges et al [46] performed a comparison of primary residue excitation energy distributions calculated with ISABEL with experimental data from [47] for p(1.2GeV) + 197 Au and saw a good agreement ( Fig. 22 of [46]).…”

Section: Results and Comparisonsmentioning

confidence: 89%

Microscopic description of proton-induced spallation reactions with the constrained molecular dynamics (CoMD) model

Assimakopoulou

Souliotis

Bonasera

et al. 2019

J. Phys. G: Nucl. Part. Phys.

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We studied the complete dynamics of the proton-induced spallation process with the microscopic framework of the Constrained Molecular Dynamics (CoMD) Model. We performed calculations of proton-induced spallation reactions on 181 Ta, 208 Pb, and 238 U targets with the CoMD model and compared the results with a standard two-step approach based on an intranuclear cascade model (INC) followed by a statistical deexcitation model. The calculations were also compared with recent experimental data from the literature. Our calculations showed an overall satisfactory agreement with the experimental data and suggest further improvements in the models. We point out that this CoMD study represents the first complete dynamical description of spallation reactions with a microscopic N-body approach and may lead to advancements in the physics-based modelling of the spallation process.

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Section: Results and Comparisonsmentioning

confidence: 89%

Microscopic description of proton-induced spallation reactions with the constrained molecular dynamics (CoMD) model

Assimakopoulou

Souliotis

Bonasera

et al. 2019

J. Phys. G: Nucl. Part. Phys.

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“…The principle behind the MCNP is statistical sampling, which makes use of the randomness of numbers. The MCNP records the trajectory of neutrons emitted by a source and determines whether the neutron is able to penetrate a shield after interacting with radioisotopes on the shield [8,9]. The set-up for the simulation using MCNP5 in this study is made up of three main interacting packages of software obtained from the Radiation Safety Information and Computational Center of the Oak Ridge National Laboratory, Tennessee, USA.…”

Section: Monte Carlo Methods For Nuclear Plantsmentioning

confidence: 99%

Monte Carlo Simulations of Nuclear Fuel Burnup

Kommalapati¹,

Asah-Opoku²,

Du³

et al. 2016

Nuclear Material Performance

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In the operation of a nuclear power plant, it is very important to determine the time evolution of material composition and radionuclide inventory during the entire operation of the plant. In the experiments, the Monte Carlo N-Particle eXtended (MCNPX) code was found to be accurate in predicting the uranium fuel depletion, the plutonium production and the buildup of most of the fission products in a nuclear reactor. The goal in this chapter is to analyze the effect of different nuclear fuel grades on the total radioactivity of the reactor core by employing nuclear burnup calculations for the three different fuels: mixed oxide fuel (MOX), uranium oxide fuel (UOX) and commercially enriched uranium (CEU), utilizing simulations with MCNPX code. The calculated results indicate that there is a buildup of plutonium isotopes for UOX and CEU, whereas there is a decline in the plutonium radioisotopes for MOX fuel with burnup time. The study of reactor neutronic parameters showed UOX fuel performs better relative to MOX and CEU. Zircaloy, with low thermal neutron absorption cross-section and high thermal conductivity, produced better results for the effective multiplication factor K eff and hence proved to be a much more effective clad material.

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“…Secondly, we employed the neutron production data 12,13) in targets of W, Pb, and Hg having a diameter of 15 cm and a thickness from 2 to 35 cm, which were bombarded with protons of 1.2 and 2.5 GeV. The data were obtained as the average neutron multiplicity by counting light outputs originating from neutron capture events occurring in a spherical scintillator tank surrounding the target.…”

Section: Outline Of Experimental Datamentioning

confidence: 99%

“…12) For comparison, the result of the MCNPX calculation is cited from Ref. 13). The library-based calculation reproduces well the experimental trend as a function of target thickness for both incident energies of 1.2 and 2.5 GeV.…”

Section: Neutron Yieldmentioning

confidence: 99%

Validation of JENDL High-Energy File through Analyses of Spallation Experiments at Incident Proton Energies from 0.5 to 2.83 GeV

Tazaki

Kosako

Fukahori

2009

Journal of Nuclear Science and Technology

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The most updated version of the JENDL high-energy file, JENDL/HE-2007, was validated with a focus on heavy elements of W, Pb, and Hg through analyses of spallation experiments using thick targets at incident proton energies from 0.5 to 2.83 GeV. For this purpose, the processing of the PHITS code system was adjusted to simulate nucleon transport phenomena using only a cross-section library including pionproduction data up to 3 GeV with the aid of an intranuclear cascade evaporation model to treat reactions induced by accompanied pions. It was found that the data up to 3 GeV in JENDL/HE-2007 predict the neutron spectra produced in thick targets with energies lower than 15 MeV with good accuracy while they underestimate those from 20 to 100 MeV by a factor of 0.4 to 0.5. It is also confirmed from analyses of the reaction rates in thick targets that the cross-section data of the dosimetry reactions of 93 Nb(n,4n) 90 Nb and 59 Co(n,4n) 56 Co for high-energy neutron field are reasonable. The present benchmark is the first index that JENDL/HE-2007 is applicable to neutronic design for a spallation-based facility with almost the same accuracy as for a conventional methodology using the intranuclear cascade model of Bertini and generalized evaporation model (GEM).

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Spallation neutron production and the current intra-nuclear cascade and transport codes

Cited by 27 publications

References 1 publication

Microscopic description of proton-induced spallation reactions with the constrained molecular dynamics (CoMD) model

Microscopic description of proton-induced spallation reactions with the constrained molecular dynamics (CoMD) model

Monte Carlo Simulations of Nuclear Fuel Burnup

Validation of JENDL High-Energy File through Analyses of Spallation Experiments at Incident Proton Energies from 0.5 to 2.83 GeV

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