bluuebunny/crossref_metadata_2025 huggingface dataset:
Test laboratory studies of refractory gold-bearing ores of Magadan Region from the standpoint of their processing by heap leaching
Authors: Rubtsov Yury , Lavrov Aleksandr , Petukhov Aleksandr , Kostromin Mikhail , Lavrik Aleksandra
Published: September 2020

The main prospects for the development of gold mining in the Kolyma area are associated with the development of ore deposits. In the southwestern part of the Tenkinsk District and in Susuman District, there are gold deposits (Pavlik, Natalka and Degdekan), which belong to the low-sulfide formation. There are some areas of poor oxidized and low-sulphide ores, the concentration of which by gravity and flotation methods becomes ineffective. At present, at the level of laboratory research and experimental field tests, some low-cost technologies for rapid and activated heap leaching of gold from poor oxidized and low sulfide ores have been developed, and they are capable to be implemented in the harsh conditions of Magadan Region. This paper describes laboratory tests of 2 types of ores from deposits in the northeastern part of Magadan Region, carried out to develop an effective cyanide technology for gold heap leaching. The studies were carried out in the laboratory of the Insitute of Mining of FarEastern Branch of the Russian Academy of Sciences and Transbaikal State University.
Evaluation of the influence of the dispersion-sludge characteristics of the pulp on the beneficiation indicators of technogenic fluorite-containing tailings
Authors: Kienko Lydia , Voronova Olga
Published: September 2020

The article provides an assessment of the technological features of mature tailings from the processing of finely disseminated fluoritecontaining raw materials of the Yaroslavkaya Mining Company. The prospects for their secondary processing are considered. It has been established that the waste stored in various sectors of the enterprise’s tailings contain from 13 to 23% fluorite, 12-14% calcite. The characteristic is given to the technological features of raw materials. The fluorite grains present in the technogenic tailings are characterized by the presence of thin inclusions and veins of silicate minerals. An obstacle to the selective separation of minerals by the flotation method is the shielding coatings of the surface zone of mineral particles, formed from contact with reagents at the stage of primary ore processing and in the process of interaction with the water-air environment in the tailing dump. The ways of increasing the contrast of the adsorption properties of minerals are proposed. Important factors influencing the process of mineral selection, allowing to influence the quality characteristics of flotation of refractory secondary raw materials is fine grinding of the material in combination with a high degree of dilution of the pulp. The possibility of extracting concentrates with a CaF2 content of 95.2-95.6% with the recovery of fluorite in them of 57-60.7% is shown. The introduction of inter-cycle regrind of foam products into the operation scheme allows to reduce the content of silicone dioxide in concentrates to 0.98%, which meets the requirements of consumers.
Procedure for risk assessment of initiation and progression of oxidation processes during development of pyrite ore deposits
Authors: Einbinder Gennady , Mitishova Natalia , Radchenko Dmitry , Knyazkin Egor
Published: September 2020

In the modern conditions, the scale of subsoil transformation in the process of mineral extraction is characterized by an increased risk of accidents, often accompanied by man-made disasters. In this regard, hazard analysis and accident risk assessment is the most important scientific and technical task, the solution of which is based on methods for identification of hazards, study of development trends and assessment of consequences of theoretically possible accidents. In relation to development conditions of sulfide ore deposits, only an accident risk assessment with determination of the possible accident hazard degree, as well as preparation and timely correction of measures aimed at reduction of accident risks can ensure an acceptable level of industrial safety at the hazardous production facility.
Platinum and platinoids in the Bolotisty gold-placer deposit (Khabarovsky Krai, Russia)
Authors: Lavrik Natalya , Stepanova Valentina , Lavrik Alexandra
Published: September 2020

The article shows the results of studies the platinum mineralization (within the framework of studying the complexity of deposits) in the waste of heavy concentrate in the southeastern flank of the Bolotisty gold-placer deposit, which the located in the Khabarovsky Krai (Russia). The deposit is localized in the “erosion window” among the covers of Miocene basalts and Eocene andesites, where Cretaceous sedimentary, tuffaceous-sedimentary rocks of the basement of the volcano structure, broken through by an Eocene intrusive body of intermediate and basic composition, come to the surface. An abbreviated mineralogical analysis for monofraction of precious metals was carried out for a concentrate fraction weighing 1.813 kg with a grain size of -3.0 + 0.1 mm. Gold and platinum were found - 1.38 mg and 1.08 mg. Platinum has an iron impurity up to 3-5 % Fe and Cu, Ir, Rh impurities are variable. There are plate-like inclusions of native osmium with an admixture of ruthenium in 43 % of the studied platinum grains. There are single inclusions of ehrlichmanite. A large amount of high-temperature dipyramidal quartz, along with magnetite, chromite, tourmaline and other minerals is a characteristic feature of the concentrate and platinum grains of this area.
The role of digital simulation in assessing and reassessing the potential of complex coal deposits
Authors: Gavrilov Vladimir , Khoiutanov Evgenii , Nemova Natal’ya , Son Dmitrij
Published: September 2020

The article addresses the increasing complexity of mined or prospective coal deposits. The paper analyses the role of digital simulation in operation assessment and reassessment of the potential of complex in structure coal deposits for more accurate understanding their investment attractiveness, reliability of knowledge on quantity and quality of the reserves. The article stresses the objective need to take into account the realities of the VUKA-world, when companies have to react rapidly to changing of external conditions by adapting organizational and technological measures as much as possible to the constantly overestimated potential of the raw material base. It is of note that reserves should be assessed in accordance with international requirements in the light of the increasing number of parameters for management. The complexity of the structure, the geomechanical heterogeneity of the rock mass, the mineral content of the impurities in the coal, its caking capacity, oxidation and enrichment are taken into account in the estimation. The paper presents the measures to increase the level of utilization of geological potential through the application of selective mining and the control of different quality coal streams in preparation for enrichment and during primary processing.
Seismic activity of major hidden faults in the Priamurye region
Authors: Tusikova Svetlana , Merkulova Tatyana , Gil’manova Gulshat
Published: September 2020

Based on the data of the relief analysis and the geophysical fields, major submeridional and NW-trending hidden faults are detected in the Priamurye region. The seismic energy calculations are performed for the instrumental observation period given the historical events. The faults showing the highest seismic activity are revealed. The seismic energy released by hidden faults is commensurable with a similar value obtained for the seismoactive faults detected from the geological data.
Monitoring of the stress-strain state of open pits’ adjacent rock mass
Authors: Panzhin Andrey , Panzhina Natalia
Published: September 2020

In the course of the work to identify the modern coordinates of the points of the state (SGN) and reference mine surveying (RMSN) networks of Orenburg Minerals JSC, the deformation characteristics of the earth’s surface in different time periods were obtained and a geomechanical model of the rock mass was built both on the industrial site itself (quarry, dump), and beyond the areas, influenced by mining. Based on the data obtained, the parameters of deformation of the rock mass and the adjacent rock mass in three planes, as well as the relative deformations and the magnitudes of the tectonic stresses that caused them were identified; during the analysis of negative factors potentially dangerous areas of the adjacent rock mass were also identified.
Prompt Fission Neutron Spectra for Neutron-Induced Fission of 239Pu and 235U
Authors: Devlin Matthew , Gomez Jaime A. , Kelly Keegan J. , O'Donnell John M. , Haight Robert C. , Taddeucci Terry N. , Neudecker Denise , Wu Ching-Yen , Henderson Jack , White Morgan C. , Bucher Brian , Buckner Matthew Q. , Lee Hye Young , Mosby Shea M. , Ullmann John L. , Fotiades Nikolaos , Henderson Roger A.
Published: September 2020

We report the current results of a large effort to accurately measure the Prompt Fission Neutron Spectra (PFNS) for neutron-induced fission of 235U and 239Pu for incident neutrons with energies from 1 to 20 MeV. The Chi-Nu experiment at the Los Alamos Neutron Science Center used an unmoderated, white spectrum of neutrons to induce fission in actinide samples that were placed inside a parallel plate avalanche counter to provide a fast fission signal. A double time-of-flight technique was used to determine the incoming and outgoing neutron energies. Two neutron detector arrays, one with 54 liquid scintillators and another with 22 lithium glass detectors, were used to detect the outgoing neutrons and measure the PFNS distributions over a wide range in outgoing neutron energy, from below 100 keV to 10 MeV. Extensive Monte Carlo modeling was used to understand the experiment response and extract the PFNS. Systematic errors and uncertainties in the method have been examined and quantified. A summary of these results for incoming energies from 1 to 5 MeV is presented here.
Setup for the measurement of the 235U(n, f) cross section relative to n-p scattering up to 1 GeV
Authors: Manna A. , Aberle O. , Alcayne V , Amaducci S. , Andrzejewski J. , Audouin L. , Babiano V-Suarez , Bacak M. , Barbagallo M. , Bennett S. , Berthoumieux E. , Bosnar D. , Brown A. S. , Busso M. , Caamaño M. , Caballero L. , Calviani M. , Calvi Fño , Cano-Ott D , Casanovas A. , Cerutti F. , Chiaveri E. , Colonna N. , Cortés G. P. , Cortés-Giraldo M. A. , Coséntino L. , Cristallo S. , Damone L. A. , Davies P. J. , Diakaki M. , Dietz M. , Domingo-Pardo C , Dressler R. , Ducasse Q. , Dupont E. , Durán I. , Eleme Z. , Fernández-Domíngez B. , Ferrari A. , Ferro-Goncalves I , Finocchiaro P. , Furman V. , Garg R. , Gawlik A. , Gilardoni S. , Göbel K. , González-Romero E. , Guerrero C. , Gunsing F , Heinitz S. , Heyse J. , Jenkins D. G. , Jericha E. , Jiri U. , Junghans A. , Kadi Y , Käppeler F , Kimura A. , Knapová I. , Kokkoris M. , Kopatch Y. , Krtiička M. , Kurtulgil D. , Ladarescu I. , Lederer-Woods C , Lerendegui-Marco J , Lonsdale S.-J. , Macina D. , Martínez T , Masi A. , Massimi C. , Mastinu P. F , Mastromarco M. , Maugeri E. , Mazzone A. , Mendoza E. , Mengoni A. , Michalopoulou V , Milazzo P. M. , Millán-Callado M. A. , Mingrone F , Moreno-Soto J , Musumarra A. , Negret A. , Nolte R. , Ogállar F , Oprea A. , Patronis N. , Pavlik A. , Perkowski J. , Petrone C. , Piersanti L. , Pirovano E. , Porras I. , Praena J. , Quesada J.M. , Ramos D. , Reifarth R. , Rochman D. , Rubbia C. , Sabaté-Gilarte M. , Saxena A. , Schillebeeckx P. , Schumann D. , Sekhar A. , Smith A.G. , Sosnin N. , Sprung P. , Stamatopoulos A. , Tagliente G. , Tain J. L. , Tarifeno-Saldivia A. E. , Tassan-Got L , Thomas B. , Torres-Sánchez P. , Tsinganis A. , Urlass S. , Valenta S. , Vannini G. , Variale V. , Vaz P. , Ventura A. , Vescovi D. , Vlachoudis V , Vlastou R. , Wallner A. , Woods P. J. , Wright T J. , Žugec P.
Published: September 2020

The neutron induced fission of 235U is extensively used as a reference for neutron fluence measurements in various applications, ranging from the investigation of the biological effectiveness of high energy neutrons, to the measurement of high energy neutron cross sections of relevance for accelerator driven nuclear systems. Despite its widespread use, no data exist on neutron induced fission of 235U above 200 MeV. The neutron facility n_TOF offers the possibility to improve the situation. The measurement of 235U(n,f) relative to the differential n-p scattering cross-section, was carried out in September 2018 with the aim of providing accurate and precise cross section data in the energy range from 10 MeV up to 1 GeV. In such measurements, Recoil Proton Telescopes (RPTs) are used to measure the neutron flux while the fission events are detected and counted with dedicated detectors. In this paper the measurement campaign and the experimental set-up are illustrated.
Effect of target density uncertainties on extracted experimental cross sections for the natTi(α, x)51Cr,46Sc reactions
Authors: Usman Ahmed Rufai , Khandaker Mayeen Uddin , Haba Hiromitsu
Published: September 2020

The production optimization of medical radioisotopes for various applications requires careful analysis of all production parameters. The importance of such radioisotopes in nuclear medicine cannot be overemphasized. During cross section calculations, experimentalist sometimes find more than one reported literature value of a certain parameter, each leading to a different effect on the overall cross sections. In the present work, we considered the effect of slight variations of density values of titanium reported in the literature on the experimental cross sections. Several reported density values (4.50, 4.51 and 4.54 g/cm3) were found in the literature, but only the lowest and highest values (4.50 and 4.54 g/cm3) were considered in this study. The said densities were used to calculate the cross sections of Ti(a, x)51Cr,46Sc radioisotopes. The corresponding trends of the excitation functions of 51Cr and 46Sc were analyzed for the selected density values. The calculated cross sections from the different density values have been analyzed and compared graphically to show the level of variations, as well as comparison with theoretical TALYS code calculated cross sections. About 1 percent variation of the cross sections have been observed. Following the observed slight variation in cross sections effect of the various density values, we recommend that IAEA could update its nuclear data service database to include recommended density values for all metals using reliable sources.
Development of MC-based uncertainty estimation technique of unfolded neutron spectrum by multiple-foil activation method
Authors: Aoki Katsumi , Kin Tadahiro , Patwary Md Kawchar Ahmed , Araki Naoto , Yoshinami Kosuke , Yamaguchi Masaya , Itoh Masatoshi , Watanabe Yukinobu
Published: September 2020

Unfolding process plays an important role in neutron energy distribution measurement by means of the multiple-foil activation method. We have developed an algorithm for estimating uncertainty of resultant neutron distribution. For the demonstration of the algorithm, we have conducted an experiment to measure thick-target neutron yield (TTNY) of the C(d,n) reaction induced by 20-MeV deuterons with the multiple-foil activation method. The experiment was conducted at Cyclotron and Radioisotope Center, Tohoku University in Japan. The obtained experimental data were analyzed by the algorithm. As a result, we found that uncertainty of derived TTNY has dependency on neutron emission energy. In addition, the dependency is caused by excitation functions of activation reactions. Therefore, we found the particular reactions causing large uncertainty in TTNY. The result of present study shows that the algorithm can evaluate uncertainty and its causes.
New 209Bi photodisintegration data and physical criteria of data reliability
Authors: Belyshev Sergey , Davydov Alexander , Filipescu Dan , Gheorghe Ioana , Ishkhanov Boris , Kyznetsov Aleksandr , Orlin Vadim , Stopani Konstantin , Utsunomiya Hiroaki , Varlamov Vladimir
Published: September 2020

The well-known problem of noticeable disagreements between photoneutron cross sections from various experiments was discussed in detail for 209Bi. Data for partial photoneutron reactions cross sections obtained at Livermore (USA) using quasimonoenergetic annihilation photons and the method of neutron multiplicity sorting were analyzed using the objective physical criteria and the experimental-theoretical method for evaluation. Because of significant systematic uncertainties involved in the method for determining the neutron multiplicity, experimental data do not satisfy the criteria of reliability and differ noticeably from the evaluated data. The new experimental data for 209Bi (γ, in) reactions with i = 1–4 were obtained using quasimonochromatic laser Compton-scattering (LCS) γ-ray beams at the NewSUBARU synchrotron radiation facility and the novel technique of direct neutron-multiplicity sorting with a flat-efficiency detector. It was found that new σ(γ, 1n), σ (γ, 2n), and σ (γ, 3n) contradict noticeably to the Livermore data. It was shown that at the same time the new 209Bi photoneutron cross-sections are in good agreement with data evaluated using experimental-theoretical method and assuring the reliability of those.
Photoneutron reaction cross sections for 75As and 181Ta: Sytematic uncertainties and data reliability
Authors: Varlamov Vladimir , Davydov Alexander , Ishkhanov Boris , Kaidarova Valeriya , Orlin Vadim
Published: September 2020

There is well-known problem of significant systematic disagreements between data for reactions (γ, 1n), (γ, 2n), obtained at Livermore (USA) and Saclay (France) using the method of photoneutron multiplicity sorting. The averaged ratios RS/Lint of integrated cross sections obtained at Saclay and Livermore for 19 nuclei from 51V to 239U are equal to 0.84 for (γ, 2n) and 1.07 for (γ, 1n) reactions. For 75As RS/Lint ratios for both partial reactions are very close (1.22 and 1.21) but for 181Ta - are quite different (0.89 and 1.25). Using the objective physical data reliability criteria it was found that there are serious doubts in reliability of Saclay and Livermore data. The newly evaluated reliable cross sections disagree with experimental data. In addition to unreliable sorting of many neutrons between both partial reactions many neutrons were lost - on the case of 181Ta in 1n channel, in the case of 75As in both 1n and 2n channels.
Measurement of the energy-differential cross-section of the 12C(n,p)12B and 12C(n,d)11B reactions at the n_TOF facility at CERN
Authors: Barbagallo M. , Aberle O. , Alcayne V. , Amaducci S. , Andrzejewski J. , Audouin L. , Babiano-Suarez V , Bacak M. , Bennett S. , Berthoumieux E. , Bosnar D. , Brown A. S. , Busso M. , Caamaño M. , Caballero L. , Calviani M. , Calviño F. , Cano-Ott D , Casanovas A. , Cerutti F. , Chiaveri E. , Colonna N. , Cortés G. P. , Cortés-Giraldo M. A. , Cosentino L. , Cristallo S. , Damone L. A. , Davies P. J. , Diakaki M. , Dietz M. , Domingo-Pardo C , Dressler R. , Ducasse Q. , Dupont E. , Durán I. , Eleme Z. , Fernández-Domíngez B. , Ferrari A. , Ferro-Gonçalves I. , Finocchiaro P. , Furman V. , Garg R. , Gawlik A. , Gilardoni S. , Göbel K. , González-Romero E. , Guerrero C. , Gunsing F. , Heinitz S. , Heyse J. , Jenkins D. G. , Jericha E. , Jiri U. , Junghans A. , Kadi Y. , Käppeler F. , Kimura A. , Knapová I. , Kokkoris M. , Kopatch Y. , Krtička M. , Kurtulgil D. , Ladarescu I. , Lederer-Woods C , Lerendegui-Marco J , Lonsdale S.-J. , Macina D. , Manna A. , Martínez T. , Masi A. , Massimi C. , Mastinu P. F. , Mastromarco M. , Maugeri E. , Mazzone A. , Mendoza E. , Mengoni A. , Michalopoulou V. , Milazzo P. M. , Millán-Callado M. A. , Mingrone F. , Moreno-Soto J , Musumarra A. , Negret A. , Ogállar F. , Oprea A. , Patronis N. , Pavlik A. , Perkowski J. , Petrone C. , Piersanti L. , Pirovano E. , Porras I. , Praena J. , Quesada J. M. , Ramos Doval D. , Reifarth R. , Rochman D. , Rubbia C. , Sabaté- Gilarte M. , Saxena A. , Schillebeeckx P. , Schumann D. , Sekhar A. , Smith A. G. , Sosnin N. , Sprung P. , Stamatopoulos A. , Tagliente G. , Tain J. L. , Tarifeño-Saldivia A. E. , Tassan-Got L , Thomas B. , Torres-Sánchez P. , Tsinganis A. , Urlass S. , Valenta S. , Vannini G. , Variale V. , Vaz P. , Ventura A. , Vescovi D. , Vlachoudis V. , Vlastou R. , Wallner A. , Woods P. J. , Wright T. J. , Žugec P.
Published: September 2020

Although the 12C(n,p)12B and 12C(n,d)11B reactions are of interest in several fields of basic and applied Nuclear Physics the present knowledge of these two cross-sections is far from being accurate and reliable, with both evaluations and data showing sizable discrepancies. As part of the challenging n_TOF program on (n,cp) nuclear reactions study, the energy differential cross-sections of the 12C(n,p)12B and 12C(n,d)11 B reactions have been measured at CERN from the reaction thresholds up to 30 MeV neutron energy. Both measurements have been recently performed at the long flight-path (185 m) experimental area of the n_TOF facility at CERN using a pure (99.95%) rigid graphite target and two silicon telescopes. In this paper an overview of the experiment is presented together with a few preliminary results.
Toward short-lived and energy-dependent fission product yields from neutron-induced fission
Authors: Tonchev Anton P , Silano Jack A , Hagmann Chris , Henderson Roger , Stoyer Mark A , Gooden Matthew , Bredeweg Todd , Wilhelmy Jerry , Tornow Werner , Howell Calwin , Finch Sean , Krishichayan FNU
Published: September 2020

Fission product yields (FPYs) are an important source of information that are used for basic and applied physics. They are essential observables to address questions relevant to nucleosynthesis in the cosmos that created the elements from iron to uranium, for example, in energy generating processes from fission recycling in binary neutron star mergers; resolving the reactor neutrino anomaly; decay heat release in nuclear reactors; and many national security applications. While new applications will require accurate energy-dependent FPY data over a broad set of incident neutron energies, the current evaluated FPY data files contain only three energy points: thermal, fast, and 14-MeV incident energies.

Recent measurements using mono-energetic and pulsed neutron beams at the Triangle Universities Nuclear Laboratory (TUNL) tandem accelerator and employing a dual fission ionization chambers setup have produced self-consistent, high-precision data critical for testing fission models for the neutron-induced fission of the major actinide nuclei. This paper will present new campaign just beginning utilizing a RApid Belt-driven Irradiated Target Transfer System (RABITTS) to measure shorter-lived fission products and the time dependence of fission yields, expanding the measurements from cumulative towards independent fission yields.
Towards an effective model for (d,p) and (d,n) nucleon-transfer reactions to bound states for FLUKA
Authors: Salvat-Pujol Francesc , Ferrari Alfredo
Published: September 2020

A general overview is presented of an effective model for the inclusion of (d,p) and (d,n) nucleon transfer direct reactions to bound states of the residual nucleus in the general-purpose radiation-transport code FLUKA. The model relies on the distorted-wave Born approximation, employing state-of-the-art subroutines for the numerical solution of the radial Schrödinger equation for the deuteron- and nucleon-nucleus wave-functions, as well as contemporary optical potential models for the latter two. A final variation of a handful of deuteron optical potential parameters provides the model with additional flexibility and enhances the agreement with experimental nucleon angular distributions in a considerable range of target nuclei and deuteron energies.
Recent shell-model investigation and its possible role in nuclear structure data study
Authors: Yuan Cenxi , Ge Yulin , Liu Menglan , Chen Guangshang , Cai Boshuai
Published: September 2020

Up to now, the nuclear shell model is rarely used in the nuclear data study because of several reasons. First, medium and heavy mass nuclei far from the shell-model cores, normally doubly magic nuclei, require a huge amount of calculation resource even in a limited shell-model space. Second, large deformation is difficult to be described in the limited model space, which is based on spherical symmetry. Third, high precision evaluation of nuclear structure data challenges the ability of the shell model. Even so, it is worth starting preliminary nuclear data investigations based on the shell model. With the present computational ability, it is possible to investigate 1000 or more nuclei in the framework of the shell model, which should be helpful for nuclear data study. In the present work, some recent shell-model investigations are briefly introduced. Based on these works, a simple nuclear force is suggested to be used in the systematic nuclear structure data study. The south-west region of 132Sn is taken as an example to show the ability of such a simple nuclear force.
Measurement of the 236U(n,f) cross section at fast neutron energies with Micromegas Detectors
Authors: Diakaki M. , Michalopoulou V. , Tsinganis A. , Axiotis A. , Kalamara A. , Kokkoris M. , Lagoyiannis A. , Patronis N. , Stamatopoulos A. , Vlastou R.
Published: September 2020

In the present work, the measurement of the 236U(n,f) cross section was performed, with reference to the 238U(n,f) reaction. The measurements took place at the neutron beam facility of the National Centre for Scientific Research "Demokritos" (Greece) and the quasi-monoenergetic neutron beams were produced via the 2H(d,n)3He reaction in the energy range 4–10 MeV. Five actinide targets (two 236U, two 238U and one 235U) and the corresponding Micromegas detectors for the detection of the fission fragments were used. Detailed Monte Carlo simulations were performed, on one hand for the study of the neutron flux and energy distribution at the position of each target, and on the other hand for the study of the energy deposition of the fission fragments in the active volume of the detector. The mass and homogeneity of the actinide targets were experimentally determined via alpha spectroscopy and the Rutherford Backscattering Spectrometry, respectively. The experimental procedure, the analysis, the methodology implemented to correct for the presence of parasitic neutrons and the cross section results will be presented and discussed.
Parameter Optimization and Sensitivity Studies of Spontaneous Fission with FREYA
Authors: Vogt R. , Randrup J. , Talou P. , Van Dyke J. T. , Bernstein L. A.
Published: September 2020

For many years, the state of the art for simulating fission in transport codes amounted to sampling from average distributions. However, such "average" fission models have limited capabilities. Energy is not explicitly conserved and no correlations are available because all particles are emitted independently. However, in a true fission event, the emitted particles are correlated. Recently, Monte Carlo codes generating complete fission events have been developed, thus allowing the use of event-by-event analysis techniques. Such techniques are particularly useful because the complete kinematic information is available for the fission products and the emitted neutrons and photons. It is therefore possible to extract any desired observables, including correlations. The fast event-by-event fission code FREYA (Fission Reaction Event Yield Algorithm) generates large samples of complete fission events, employing only a few physics-based parameters. A recent optimization of these parameters for the isotopes in FREYA that undergo spontaneous fission is described and results are presented. The sensitivity of neutron observables in FREYA to the input yield functions is also discussed and the correlation between the average neutron multiplicity and fragment total kinetic energy is quantified.
Performance of a twin position-sensitive Frisch-grid ionization chamber for photofission experiments
Authors: Peck Marius , Bonnes Uwe , Enders Joachim , Göök Alf , Hehner Joerg , Oberstedt Stephan
Published: September 2020

A position-sensitive twin Frisch-grid ionization chamber has been constructed for future photofission experiments using nearly monochromatic, linearly polarized gamma-ray beams. By exchanging the anode plates in the standard ionization chamber on both sides by an array of grid- and strip-anodes, which are rotated by 90° relative to each other and read out by means of resistive charge division, a position sensitivity is achieved that allows the azimuthal fragment emission angle and hence the fission axis orientation to be determined. The performance of this gaseous detector has been studied using the well-known 252Cf spontaneous fission process. The fission axis orientation could be determined relative to an arbitrary axis in space with a resolution better than 7° FWHM. Measured pre-neutron mass and total kinetic energy distributions are consistent with literature, which ensures that the mass and energy resolution for fission fragments is not affected by the position-sensitive structure.
Implementation of Probability Table Generation Using Ladder Method in Ruler
Authors: Wu Xiaofei , Liu Ping , Ge Zhigang
Published: September 2020

Probability table is one of the most important and natural methods used to simulate the neutron transport in unresolved resonance range in reactor physics. A new module for generating probability tables in the unresolved-resonance region has been developed for the nuclear data processing code Ruler, using ladder method. In order to validate and verify the accuracy of this module, Probability tables have been calculated and compared with NJOY2016. Agreement is observed in the comparisons of the probability tables and corresponding cross-section values that are calculated by Ruler and NJOY2016. Ruler has improved computational efficiency greatly comparing with NJOY2016 as multi-thread parallel algorithm is applied.
Trends on major actinides from an integral data assimilation
Authors: Rimpault Gerald , Noguère Gilles , de Saint Jean Cyrille
Published: September 2020

The objective of this work is to revisit integral data assimilation for a better prediction of the characteristics of SFR cores.

ICSBEP, IRPhE and MASURCA critical masses, PROFIL irradiation experiments and the FCA-IX experimental programme (critical masses and spectral indices) with well-mastered experimental technique have been used. As calculations are performed without modelling errors (with as-built geometries) and without approximations with the TRIPOLI4 MC code, highly reliable C/E are achieved.

Assimilation results suggest a 2.5% decrease for 238U capture from 3 keV to 60 keV, and a 4-5% decrease for 238U inelastic in the plateau region. For this energy range, uncertainties are respectively reduced to 1-2% and to 2-2.5% for 238U capture and 238U inelastic respectively.

The increase trends on 239Pu capture cross section of around 3% in the [2 keV-100 keV] energy range come from a low PROFIL 240Pu/239Pu ratio C/E. For 240Pu capture cross section, the increase trend of around 4% in the [3 keV-100 keV] energy range goes in the same direction as the recent ENDF/B.VIII evaluation though at a much lower level.

The nuclear data uncertainty associated to SFR ASTRID critical mass is reduced to 470 pcm.
Processing and application of nuclear data for low temperature criticality assessment
Authors: Ware Tim , Hanlon David , Hanlon Tara , Hiles Richard , Lingard Malcolm , Perry Ray , Richards Simon
Published: September 2020

Until recently, criticality safety assessment codes had a minimum temperature at which calculations can be performed. Where criticality assessment has been required for lower temperatures, indirect methods, including reasoned argument or extrapolation, have been required to assess reactivity changes associated with these temperatures.

The ANSWERS Software Service MONK® version 10B Monte Carlo criticality code, is capable of performing criticality calculations at any temperature, within the temperature limits of the underlying nuclear data in the BINGO continuous energy library. The temperature range of the nuclear data has been extended below the traditional lower limit of 293.6 K to 193 K in a prototype BINGO library, primarily based on JEFF-3.1.2 data. The temperature range of the thermal bound scattering data of the key moderator materials was extended by reprocessing the NJOY LEAPR inputs used to produce bound data for JEFF-3.1.2 and ENDF/B-VIII.0. To give confidence in the low temperature nuclear data, a series of MONK and MCBEND calculations have been performed and results compared against external data sources. MCBEND is a Monte Carlo code for shielding and dosimetry and shares commonalities to its sister code MONK including the BINGO nuclear data library. Good agreement has been achieved between calculated and experimental cross sections for ice, k-effective results for low temperature criticality benchmarks and calculated and experimentally determined eigenvalues for thermal neutron diffusion in ice.

To quantify the differences between ice and water bound scattering data a number of MONK criticality calculations were performed for nuclear fuel transport flask configurations. The results obtained demonstrate good agreement with extrapolation methods. There is a discernible difference in the use of ice and water data.
Results of the Collaborative International Evaluated Library Organisation (CIELO) Project
Authors: Fleming M. , Chadwick M. , Brown D. , Capote R. , Ge Z. , Herman M. , Ignatyuk A. , Ivanova T. , Iwamoto O. , Koning A. , Plompen A. , Trkov A.
Published: September 2020

Simulation of nuclear systems requires complete data that represents the relevant nuclear physics. This requires many types of experimental measurements, theoretical physics, semi-empirical models and software systems, as well as experts to integrate and guide the process. This discipline is collectively known as nuclear data, and separate programmes within various European countries, the USA, Japan, Russia, and other OECD Nuclear Energy Agency (NEA) member countries have been operating for many decades. The NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC) exists to improve the quality and completeness of nuclear data by bringing together representatives of the major nuclear data evaluation projects of NEA member countries and selected Invitees. The Sub- and Expert Groups of the WPEC typically focus on specific technical topics, while the Collaborative International Evaluated Library Organisation Pilot Project (CIELO) was established to generate complete evaluations for a selection of the most important isotopes for criticality in nuclear technologies: 235,238U, 239Pu, 56Fe, 16O and 1H.

This project stimulated numerous activities, resulting in major contributions to the Special Issue of the Nuclear Data Sheets journal and the production of a suite of new nuclear data evaluations that have been incorporated in major nuclear data libraries ENDF and JEFF. The outcomes of these evaluations include significant harmonisa-tion of discrepancies between the independent programmes, improvement in the performance for international standard nuclear criticality and neutron transmission benchmarks, complete uncertainties for nearly all parameters and the utilisation of modern data storage technologies. This work has leveraged the considerable, parallel experimental work in collecting improved experimental measurements to support nuclear data and highlighted high-priority areas for further study. A productive and durable framework for international evaluation has been established which will build upon the lessons learned. These will continue through new WPEC groups and a new IAEA evaluation network, which has been initiated in response to the success of the CIELO project. This article summaries some performance feedback on the CIELO evaluations, including recent results, and will describe ongoing and future, planned CIELO-related collaborations to further advance our understanding.
New equipment for neutron scattering cross-section measurements at GELINA
Authors: Nyman Markus , Adam Thomas , Borcea Catalin , Boromiza Marian , Dessagne Philippe , Henning Gregoire , Kerveno Maëlle , Negret Alexandru , Olacel Adina , Pirovano Elisa , Plompen Arjan
Published: September 2020

Two new experimental setups are being developed at European Commission’s Joint Research Centre in Geel, Belgium. The scintillator array ELISA (ELastic and Inelastic Scattering Array) is for high-quality neutron scattering cross section and angular distribution measurements. It has the capability to separate neutron-and photon-induced events via pulse-shape analysis. Inelastic scattering can also be resolved from the elastic channel. The ELISA setup and data analysis procedure were validated by performing measurements using carbon and iron samples. The DELCO spectrometer (Detection of ELectrons from COnversion) is intended for inelastic neutron scattering cross-section measurements in cases where the detection of γ rays is not feasible. The current status of DELCO, results from the first tests, and future prospects will be discussed.
Neutron beam line for TOF measurements at the Spanish National Accelerator Lab (CNA)
Authors: Macías Miguel , Fernández Begoña , Praena Javier
Published: September 2020

A few years ago, the Spanish National Accelerator Lab (CNA) developed the first accelerator-based neutron facility in Spain called HiSPANoS (HiSPAlis Neutron Source). The first applications of the line were related to integral measurements applied to nuclear astrophysics, dosimetry and single event effects produced by neutrons in electronic devices. The successful of HiSPANoS pushed the enhancement of the facility. In collaboration with the NEC® Company, two devices were designed for pulsing ion beams (Chopper) and for compressing in time (Buncher) the pulsed beams. The Chopper-Buncher system has been already installed and commissioned. Proton and deuteron beams are delivered with repetition rates from 62.5 kHz to 2 MHz and 1 ns pulse width. In addition, a new line of the 3 MV Tandem Pelletron accelerator was designed for neutron time-of-flight (TOF) experiments. Conventional devices and a dedicated Pick-Up for timing measurements form the new line. In order to check the performance of the whole TOF system, we have carried out the measurement of the neutron spectrum produced by 7Li(p,n)7Be reaction at Ep = 1912 keV. Such spectrum has been measured by the TOF technique few times and it can be considered a standard neutron field, in particular in nuclear astrophysics. The first result of such experiment performed at CNA is shown in some detail. The excellent performance of the accelerator, the Chopper-Buncher system and the acquisition system allow us to offer the TOF line at HiSPANoS-CNA to the neutron community.
Use of shielding integral benchmark archive and database for nucleardata validation
Authors: Kodeli I. , Cabellos O. , Leal L.
Published: September 2020

Shielding benchmarks were extensively used for the validation and improvement of nuclear data since many years. Recent evaluations however mostly rely on the validation using critical benchmarks, which can introduce biases and compensation effects. A new Working Party on International Nuclear Data Evaluation Co-operation Subgroup 47 (WPEC SG47) entitled "Use of Shielding Integral Benchmark Archive and Database for Nuclear Data Validation" was started in June 2019 with the objective to promote further development and use of Shielding Integral Benchmark Archive and Database (SINBAD) and thus contribute to the diversification of the nuclear data validation practice by including more extensively other types of integral measurements, such as shielding benchmarks, in the validation and evaluation procedure. Use of shielding benchmarks is expected to provide a wider-scope test of the performance of the evaluated nuclear data and would ultimately contribute to a production of more general-purpose cross-section evaluations.
Two absolute integral measurements of the 197Au(n,γ) stellar cross-section and solution of the historic discrepancies
Authors: Praena Javier , Jiménez-Bonilla Pablo
Published: September 2020

The Maxwellian averaged cross section (MACS) for 197Au(n,γ) is used in neutron capture cross section measurements as a reference for reactions important for astrophysics, reactor and dosimetry applications. The traditionally adopted value for this reference cross section, in the energy range relevant for astrophysical (3 < E n < 200 keV), was obtained by Ratynski and Käppeler in 1988. However, the MACS calculated using the 2006 standards evaluation is approximately 6 % above the Ratynski and Käppeler (R&K) evaluation. Because of this discrepancy new experiments and reanalyses were done in an attempt to resolve the problem. In 2011 we started as well a series of integral experiments (activation) for determining the MACS-30 (kT=30 keV) of Au with two different Maxwellian neutron spectra: i) QMNS-25 (as R&K) and ii) MNS-30 (new method). Our results agree with those obtained with the standard evaluation. At present (2018), the updated MACS-30 has been included as standard. Here we present the results of our measurements and the reasons for the lower value of the R&K measurement.
Impact of the ENDF/B-VIII.0 library on modeling nuclear tools for oil exploration
Authors: Mauborgne Marie-Laure , Radtke R.J. , Stoller Christian , Haranger Fabien
Published: September 2020

In the oil field, exploration of the subsurface through well logging provides measurements of the characteristics of rock formations and fluids to help identify and evaluate potential reservoirs. Downhole nuclear measurements focus on formation properties such as natural radioactivity, formation density, and hydrogen content, as well as the identification of the elemental and mineralogical composition of the rock through spectroscopy. Accurate nuclear modeling is a fundamental part of nuclear well logging tool development, from concept through design to response characterization. Underlying the accuracy of nuclear modeling is a good knowledge of nuclear cross sections of the elements in the tool, borehole, and subsurface formations. The recent focus on replacing tools based on radio-isotopic sources with those based on D-T neutron generators opens many opportunities for new measurements but highlights the deficiencies of current cross sections. For example, in neutron-induced inelastic and capture gamma ray spectroscopy, major obstacles come from a lack of or inaccuracies in the cross sections of essential materials.
Excitation function of natCu(3He,x)65Zn nuclear reaction for 3He beam monitoring purpose
Authors: Khandaker Mayeen Uddin , Nagatsu Kotaro , Obata Honoka , Minegishi Katsuyuki , Zhang Ming-Rong , Ali Samer K. I. , Otuka Naohiko
Published: September 2020

The excitation function of the natCu(3He,x)65Zn nuclear reaction was measured from its threshold up to 53 MeV incident energy relative to the natTi(3He,x)48V monitor reaction by using the conventional stacked foil activation technique combined with HPGe γ-ray spectrometry. Our result is systematically higher than the IAEA recommendation, and more experimental works are desired especially above 25 MeV.
Molten salt fast reactor SAMOFAR: Safety issues of the chemical plant
Authors: Marchix Anthony , Dieuaide Manon
Published: September 2020

The concept of Molten Salt Fast Reactor (MSFR) has been selecting by the Generation IV International forum as it presents interesting features in terms of safety, sustainability and economics. SAMOFAR project aims to provide the safety assessment of the MSFR concept based on the Thorium fuel cycle. This document provides the radiological assessments for the chemical plant, including shielding requirements and decay heat evaluations.
Study of dose rate in the brain model based on the neutron beam of SUT-MNSR
Authors: Li Kaijian , Limphirat Ayut , Sanguansak Nuanwan
Published: September 2020

Boron neutron capture therapy (BNCT) is tumor-cell targeted radiotherapy that has significant superiority over conventional radiotherapies. The most neutron beams used for BNCT are from the reactors with high power, new design Miniature Neutron Source Reactor(MNSR) with 45kW with BNCT beam for Suranaree University of Technology(SUT) is being designed and built. According to SUT-MNSR physics design, SUT-MNSR will have the epithermal neutron beam for BNCT treatment. The dose rate distribution in the body should be estimated before SUT-MNSR is used for BNCT clinical trials (Brain tumor). This paper introduces the simulation for SUT-MNSR neutron beam by Monte Carlo N-Particle Transport Code (MCNP), and the establishment of human brain model and physics dose rate distribution in brain tumor by MCNP program.The brain model is established according to the different element in the skin, skull and tissue, the distribution of neutron dose and Gamma dose in the brain model were calculated.
Production yields of 𝛽+ emitters for range verification in proton therapy
Authors: Rodríguez-González T. , Guerrero C. , Jiménez-Ramos M.C. , Dendooven P. , Lerendegui-Marco J. , Fraile L.M. , Millán-Callado M.A. , Ozoemelam I. , Parrado A. , Quesada J.M.
Published: September 2020

In-vivo Positron Emission Tomography (PET) range verification relies on the comparison of the measured and estimated activity distributions from β+ emitters induced by the proton beam on the most abundant elements in the human body, right after (looking at the long-lived β+ emitters 11C, 13N and 15O) or during (looking at the short-lived β+ emitters 29P, 12N, 38mK and 10C) the irradiation. The accuracy of the estimated activity distributions is basically that of the underlying cross section data. In this context, the aim of this work is to improve the knowledge of the production yields of β+ emitters of interest in proton therapy. In order to measure the long-lived β+ isotopes, a new method has been developed combining the multi-foil technique with the measurement of the induced activity with a clinical PET scanner. This technique has been tested successfully below 18 MeV at CNA (Spain) and will be used at a clinical beam to obtain data up to 230 MeV. However, such method does not allow measuring the production short-lived isotopes (lower half-life). For this, the proposed method combines a series of targets sandwiched between aluminum foils (acting as both degraders and converters) placed between two LaBr3 detectors that will measure the pairs of 511 keV γ-rays. The first tests will take place at the AGOR facility at KVI-CART, in Groningen.
Predesign of a flexible multibody system excited by moving load using a mechatronic system approach
Authors: Hamza Ghazoi , Barkallah Maher , Hammadi Moncef , Choley Jean-Yves , Riviere Alain , Louati Jamel , Haddar Mohamed
Published: September 2020

In this paper, a new analytical approach to object oriented modeling is presented for the predesign of a multibody system. We investigate the dynamic behavior of a system of interconnected components using the modeling language Modelica. In engineering, beam-masses are often used as design models. In fact, the considered system is composed of a flexible beam subjected to a moving load and supporting one or more translating elastic subsystems. Each subsystem is controlled by a vibration absorber and the structure is affected dynamically only through the moving character of the load. The problem of calculation of the dynamic response of this system is very important in many engineering applications such as in the predesign and analysis of a robotic portal systems, machine tools and bridge crane systems. The object oriented modeling approach will be presented to demonstrate the importance of this approach to parametric investigation. It will illustrate how subsystems from Modelica Standard Library can be connected to the developed structure in order to study the vibrational behavior of such a system. For validation purpose, results are compared with those reported in the literature.