bluuebunny/crossref_metadata_2025 huggingface dataset:
Assessment of the relationships between elements and organic matter in water after a large landslide in the Bureyskoye reservoir (Russia)
Authors: Kozhevnikova Tatiana , Kondratyeva Lyubov , Golubeva Evgeniya , Manzhula Ilya
Published: September 2020

The article provides information on statistical approaches to identify the dominant factors that influenced the water quality in the Bureyskoye reservoir after a large landslide in December 2018 blocked access to a hydroelectric power plant. To restore the hydrological regime, blasting operations were carried out using trinitrotoluene and hexogen. The main indicators of water quality were volatile organic matters and elemental composition that varied along different banks above and below the landslide body and under the influence of explosives. In water samples from the artificial canal after the restoration of the reservoir flow, the content of Fe, Mn, Al, Cu and Zn remained at a low level and did not reach the initial values established prior to the blasting operations. However, an increase in the content of Pb by 7 times and Hg by 80 times was noted. The presence of methanol and methylated benzene derivatives in water could stimulate the formation of more toxic methylmercury, posing a risk to aquatic organisms. Correlation analysis was used to process the obtained data which made it possible to differentiate the contributions of natural (landslide, river tsunami) and anthropogenic factors (blasting) to the change in the chemical composition of water in the reservoir.
Assessment of the sorption potential of the plant l. Sativum l. in the process of formation of the biogeochemical barrier
Authors: Kornilkov Sergei , Antoninova Natalia , Sobenin Artem
Published: September 2020

For many years of industrial development of the Ural region, the mining industry remains one of the main components of the economy, the development of which is accompanied by large-scale environmental pollution and the accumulation of a significant amount of man-made waste with a high potential for negative impact. The article presents the results of experimental studies on the accumulation of heavy metals by L. sativum L. plants, in order to develop the principles of the formation of artificial biogeochemical barriers. As part of the research on the territory of the enterprise leading the development of the copper pyrite deposit, samples of dump waters were taken, which, in turn, were subjected to chemical analysis and a test to assess their phytotoxic (in the absence of a substrate) potential for seed germination and root growth in a model of L. sativum L. The samples were diluted in distilled water to obtain 8 different concentrations (1:80, 1:60, 1:40, 1:20, 1:10, 1: 5, 1: 2, 1: 1), and the effect of waste water without dilution with water, and distilled water was used as a control. In addition, the total amount of metals (Cr, Cu, Ni, Pb, Co and Zn) was determined. The data obtained demonstrated the phytotoxicity of the dump waters, a decrease in root growth in solutions with concentrations of 1: 1, 1: 2, 1: 5, 1:10 and 1:20 was noted, it was shown that these biological objects have accumulating properties with respect to a number of heavy metals.
Land use land cover change detection in the mining areas of V. D. Yalevsky coal mine-Russia
Authors: Azeez Аl-shateri Hoshmand Ahmed , Mukhitdinov Shuchrat
Published: September 2020

The dynamics of land use/land cover (LULC) changes, the effect of coal mining on the LULC changes, and the regional environmental impact are discussed in this study. The different land use classes mainly Forest, Water Bodies, Road, Mining Area, Agriculture and Grass in the study area of V. D. Yalevsky coal field area in Prokorvisk city in Kamerovo region of Russia are identified. On the other hand the impact of V. D. Yalevsky coal mine activities on LULC change on the environment and teritory are discussed. The LULC changes in the V. D. Yalevsky coal field area were analyzed for a period of 27 years e.g., from the year 1992 to 2019. The changes were detected on a 13-years time interval using Landsat-4 TM, Landsat-8 OLI. Furthermore supervised classification techniques using maximum likelihood method through ENVI (Environment for Visualizing Images) 5.1software was utilized. In addition post classification change detection method through ENVI was used to investigate the changes. The study reveals decrecment in LULC cotogories of forest to 25.35km², water bodies to -0.94km², agriculture to -98.48km², road to -10.80km². However increment in the rate of mining area to 100.72km² and grass cover 34.86 km² during the study period. Meanwhile 90.18% overall accuracy and (0.87) kappa coefitient for 1992 classified image, 93.41% overall accuracy and (0.91) Kappa koefitient for 2006 classified image and 88.69% overall accuracy and (0.85) kappa coefitient for 2019 classified image were obtained.
Measurements of neutron-induced light-charged particle emission reactions
Authors: Zhang Guohui , Bai Huaiyong , Jiang Haoyu , Cui Zengqi , Lu Yi , Hu Yiwei , Chen Jinxiang , Gledenov Yu. M. , Sedysheva M. V. , Khuukhenkhuu G. , Fan Ruirui , Jiang Wei , Yi Han , Tang Jingyu , Liang Zhou , Ning Changjun , An Qi , Bao Jie , Bao Yu , Cao Ping , Chen Haolei , Chen Qiping , Chen Yonghao , Yukai Chen , Chen Zhen , Feng Changqing , Gao Keqing , Gu Minhao , Han Changcai , Han Zijie , He Guozhu , He Yongcheng , Yang Hong , Huang Hanxiong , Huang Weiling , Huang Xiru , Ji Xiaolu , Ji Xuyang , Zhijie Jiang , Jing Hantao , Kang Ling , Kang Mingtao , Li Bo , Li Chao , Li Jiawen , Lun Li , Li Qiang , Xiao Li , Li Yang , Liu Rong , Liu Shubin , Liu Xingyan , Luan Guangyuan , Mu Qili , Qi Binbin , Ren Jie , Ren Zhizhou , Ruan Xichao , Song Zhaohui , Song Yingpeng , Sun Hong , Sun Kang , Sun Xiaoyang , Sun Zhijia , Tan Zhixin , Tang Hongqing , Tang Xinyi , Tian Binbin , Wang Lijiao , Wang Pengcheng , Wang Qi , Wang Taofeng , Wang Zhaohui , Wen Jie , Wen Zhongwei , Wu Qingbiao , Wu Xiaoguang , Wu Xuan , Xie Likun , Yang Yiwei , Yu Li , Yu Tao , Yu Yongji , Zhang Linhao , Zhang Qiwei , Zhang Xianpeng , Zhang Yuliang , Zhang Zhiyong , Zhao Yubin , Zhou Luping , Zhou Zuying , Zhu Danyang , Zhu Kejun , Zhu Peng
Published: September 2020

In the past two decades cooperating with Frank Laboratory of Neutron Physics (FLNP), Joint Institute for Nuclear Research (JINR) measurements of (n, α) reaction cross sections for 6Li, 10B, 25Mg, 39K, 40Ca, 54,56,57 Fe, 58Ni, 63Cu, 64,67 Zn, 95Mo, 143Nd and 147,149 Sm nuclei were performed in the MeV neutron energy region based on the 4.5 MV Van de Graaff accelerator at Peking University. In recent years, our measurements were extended in three aspects. Firstly, measurements were expanded from two-body reactions to three-body reactions such as 10B (n, t2 α). Secondly, the neutron energy region was extended from below 8 MeV to 8 - 11 MeV by using the HI-13 tandem accelerator of China Institute of Atomic Energy (CIAE), with which cross sections of 54,56 Fe(n, α)53,51Cr reactions were measured. Thirdly, based on the newly-built China Spallation Neutron Source (CSNS) Back-n WNS (White Neutron Source), differential and angle-integrated cross sections for 6Li(n, t) and 10B(n, α) reactions were measured in the neutron energy region from 1 eV to 3 MeV.
GDR cross sections updated in the IAEA-CRP
Authors: Utsunomiya Hiroaki , Gheorghe Ioana , Filipescu Dan M. , Stopani Konstantin , Belyshev Sergey , Wang Hongwei , Fan Gongtao , Ariizumi Takashi , Lui Yiu-Wing , Symochko Dmytro , Krzysiek Mateusz , Miyamoto Shuji , Goriely Stephane , Kawano Toshihiko
Published: September 2020

The Coordinated Research Project (CRP) with the code F41032 has been launched by the International Atomic Energy Agency (IAEA) in 2016 as a 5-year project with the scientific goal being two-fold: 1) updating the 2000 photonuclear data library and 2) constructing a reference database of photon strength functions. We report the experimental technique and methodology used for the former goal and selected giant-dipole resonance (GDR) data updated in the IAEA-CRP.
Isomer ratios for products of photonuclear reactions on Rh
Authors: Bezshyyko Oleg , Vodin Oleksandr , Golinka Larisa-Bezshyyko , Kadenko Ihor , Kotenko Andrii , Kushnir Volodymyr , Mitrochenko Viktor , Olejnik Stanislav , Perezhogin Sergey , Povar Tetiana
Published: September 2020

Over the past several years various preequilibrium models for nuclear reaction mechanisms description were developed. Diversified detailed experimental data in the medium excitation energy region for nuclei are needed for reasonable selection among these theoretical models. Lack of experimental data in this energy region does essentially limit the possibilities for analysis and comparison of different preequilibrium theoretical models. For photonuclear reactions this energy range covers 30-100 MeV. Experimental measurements and estimations of isomer ratios for products of photonuclear reactions with multiple particle escape on antimony were performed using bremsstrahlung spectrum as projectile with end-point energies 74,9 and 85,7 MeV. Method of the induced activity measurement was applied. For acquisition of gamma spectra we used HPGe spectrometer with 20% relative efficiency. Linear accelerator of electrons LU-40 was a source of bremsstrahlung. Energy resolution of electron beam was about 1% and a mean electron current varied within (3.8 - 5.3)μA.
Isomeric cross section study of neutron induced reactions on Ge isotopes
Authors: Vlastou R. , Kalamara A. , Gkatis G. , Stamatopoulos A. , Kokkoris M. , Chasapoglou S. , Axiotis M. , Lagoyannis A.
Published: September 2020

Cross sections for the70,76Ge(n,2n),72,73Ge(n,p) and72,74Ge(n,α) reactions have been measured at the 5.5 MV tandem T11/25 Accelerator Laboratory of NCSR Demokritos, using the activation technique. Neutron beams have been produced in the ~16-20 MeV energy region, by means of the3H(d,n)4He reaction. The maximum flux has been determined to be of the order of 105n/cm2s, while the flux variation of the neutron beam was monitored by using a BF3 detector. The cross section has been deduced with respect to the27Al(n,α)24Na and93Nb(n,2n)92mNb reference reactions. The contaminations from reactions induced on neighboring Ge isotopes and leading to the same residual nucleus, have been taken into account. After the end of the irradiations, the activity induced by the neutron beams at the targets and reference foils, has been measured by HPGe detectors. Statistical model calculations using the EMPIRE code were performed on the data measured in this work as well as on data reported in literature.
Fast neutron inelastic scattering from 7Li
Authors: Beyer Roland , Frotscher Axel , Junghans Arnd R. , Nyman Markus , Plompen Arjan , Grieger Marcel , Kogler Toni , Ludwig Felix , Reinicke Stefan , Schulz Stefan , Schwengner Ronald , Trinh Thu Trang , UrlaB Sebastian , Wagner Andreas
Published: September 2020

The inelastic scattering of fast neutrons from 7Li nuclei was investigated at the nELBE neutron-time-of-flight facility. The photon production cross section of 478 keV γ-rays from the first excited state of 7Li was determined by irradiating a disc of LiF with neutrons of energies ranging from 100 keV to about 10 MeV. The target position was surounded by a setup of 7 LaBr3 scintillation detectors and 7 high-purity germanium detectors to detect the de-excitation γ-rays. A 235U fission chamber was used to determine the incoming neutron flux. The number of detected photons was corrected for the detection efficiency, multiple scattering and the time-of-flight dependent data acquisition dead time. The preliminary results show reasonable agreement with some previous measurments but are about 15 % below the recent data taken at the GELINA facility.
Measurement of Gamma-Ray from Inelastic Neutron Scattering on 56Fe
Authors: Zhaohui WANG , Jie REN , Hongyi WU , Jing QIAN , Hanxiong HUANG , Wenming WANG , Wei JIANG , Xiaoguang WU , Qiwei ZHANG , Han YI , Qi WANG , Xia LI , Jie BAO , Xichao RUAN , Hantao JING , Jingyu TANG , Qi AN , Huaiyong BAI , Yu BAO , Ping CAO , Haowei CHEN , Qiping CHEN , Yonghao CHEN , Yukai CHEN , Zhen CHEN , Zengqi CUI , Ruirui FAN , Changqing FENG , Keqing GAO , Minhao GU , Changcai HAN , Zijie HAN , Guozhu HE , Yongcheng HE , Yang HONG , Weiling HUANG , Xiru HUANG , Xiaolu JI , Xuyang JI , Haoyu JIANG , Zhijie JIANG , Ling KANG , Mingtao KANG , Bo LI , Chao LI , Jiawen LI , Lun LI , Qiang LI , Xiao LI , Yang LI , Rong LIU , Shubin LIU , Xingyan LIU , Guangyuan LUAN , Qili MU , Changjun NING , Binbin QI , Zhizhou REN , Zhaohui SONG , Yingpeng SONG , Hong SUN , Kang SUN , Xiaoyang SUN , Zhijia SUN , Zhixin TAN , Hongqing TANG , Xinyi TANG , Binbin TIAN , Lijiao WANG , Pengcheng WANG , Taofeng WANG , Jie WEN , Zhongwei WEN , Qingbiao WU , Xuan WU , Likun XIE , Yiwei YANG , LI YU , Tao YU , Yongji YU , Guohui ZHANG , Linhao ZHANG , Xianpeng ZHANG , Yuliang ZHANG , Zhiyong ZHANG , Yubin ZHAO , Luping ZHOU , Zuying ZHOU , Danyang ZHU , Kejun ZHU , Peng ZHU
Published: September 2020

In nuclear reactors, inelastic neutron scattering is a significant energy-loss mechanism which has deep impacts on designments of nuclear reactor and radiation shielding. Iron is an important material in reactor. However, for the existing nuclear data for iron, there exists an obvious divergence for the inelastic scattering cross sections and the related gamma production sections. Therefore the precise measurements are urgently needed for satisfying the demanding to design new nuclear reactors (fast reactors), Accelerator Driven Subcritical System (ADS), and other nuclear apparatus. In this paper, we report a new system with an array of HPGe detectors, electronics and acquisition system. Experiments had been carried out on three neutron facilities.
Measurement and analysis of 155,157Gd(n,γ) from thermal energy to 1 keV
Authors: Massimi C. , Aberle O. , Andrzejewski J. , Audouin L. , Bacak M. , Balibrea J. , Barbagallo M. , Bečvář F. , Berthoumieux E. , Billowes J. , Bosnar D. , Brown A. , Caamaño M. , Calviño F. , Calviani M. , Cano-Ott D , Cardella R. , Casanovas A. , Castelluccio D. M. , Cerutti F. , Chen Y. H. , Chiaveri E. , Clai G. , Colonna N. , Console Camprini P. , Cortés G. , Cortés-Giraldo M. A. , Cosentino L. , Damone L. A. , Diakaki M. , Domingo-Pardo C , Dressler R. , Dupont E. , Durán I. , Fernández-Domínguez B. , Ferrari A. , Ferreira P. , Finocchiaro P. , Furman V. , Göbel K. , García A. R. , Gawlik A. , Gilardoni S. , Glodariu T. , Gonçalves I. F. , González-Romero E. , Griesmayer E. , Guerrero C. , Guglielmelli A. , Gunsing F. , Harada H. , Heinitz S. , Heyse J. , Jenkins D. G. , Jericha E. , Käppeler F. , Kadi Y. , Kalamara A. , Kavrigin P. , Kimura A. , Kivel N. , Knapova I. , Kokkoris M. , Krtička M. , Kurtulgil D. , Leal-Cidoncha E , Lederer C. , Leeb H. , Lerendegui-Marco J , Lonsdale S. J. , Macina D. , Manna A. , Marganiec J. , Martínez T. , Masi A. , Mastinu P. , Mastromarco M. , Maugeri E. A. , Mazzone A. , Mendoza E. , Mengoni A. , Milazzo P. M. , Mingrone F. , Mucciola R. , Musumarra A. , Negret A. , Nolte R. , Oprea A. , Patronis N. , Pavlik A. , Perkowski J. , Porras I. , Praena J. , Quesada J. M. , Radeck D. , Rauscher T. , Reifarth R. , Rocchi F. , Rubbia C. , Ryan J. A. , Sabaté-Gilarte M. , Saxena A. , Schillebeeckx P. , Schumann D. , Sedyshev P. , Smith A. G. , Sosnin N. V. , Stamatopoulos A. , Tagliente G. , Tain J. L , Tarifeño-Saldivia A. , Tassan-Got L , Valenta S. , Vannini G. , Variale V. , Vaz P. , Ventura A. , Vlachoudis V. , Vlastou R. , Wallner A. , Warren S. , Weiss C. , Woods P. J. , Wright T. , Žugec P. ,   the n_TOF Collaboration
Published: September 2020

We have measured the capture cross section of the 155Gd and 157Gd isotopes between 0.025 eV and 1 keV. The capture events were recorded by an array of 4 C6D6 detectors, and the capture yield was deduced exploiting the total energy detection system in combination with the Pulse Height Weighting Techniques. Because of the large cross section around thermal neutron energy, 4 metallic samples of different thickness were used to prevent problems related to self-shielding. The samples were isotopically enriched, with a cross contamination of the other isotope of less than 1.14%. The capture yield was analyzed with an R-Matrix code to describe the cross section in terms of resonance parameters. Near thermal energies, the results are significantly different from evaluations and from previous time-of-flight experiments. The data from the present measurement at n_TOF are publicly available in the experimental nuclear reaction database EXFOR.
Neutron imaging at the n_TOF facility of CERN
Authors:   the n_TOF Collaboration, Bacak M. , Mingrone F. , Calviani M. , Torregrosa Martin C. , Aberle O. , Chiaveri E. , Fornasiere E. , Perillo-Marcone A , Vlachoudis V.
Published: September 2020

A neutron radiography station has been developed at the n_TOF facility of CERN. The characteristics of the neutron beam line and the imaging setup are presented in this paper together with first experimental results. A comparison of two different collimation systems is discussed and further improvements and upgrades are outlined.
Preliminary results on the 233U α-ratio measurement at n_TOF
Authors: Bacak M. , Aïche M. , Bélier G. , Berthoumieux E. , Diakaki M. , Dupont E. , Gunsing F. , Heyse J. , Kopecky S. , Krtička M. , Laurent B. , Leeb H. , Mathieu L. , Schillebeeckx P. , Serot O. , Taieb J. , Valenta S. , Vlachoudis V. , Aberle O. , Andrzejewski J. , Audouin L. , Balibrea J. , Barbagallo M. , Bečvář F. , Billowes J. , Bosnar D. , Brown A. , Caamaño M. , Calviño F. , Calviani  , Cano-Ott D , Cardella R. , Casanovas A. , Cerutti F. , Chen Y. H. , Chiaveri E. , Colonna  , Cortés G. , Cortés-Giraldo M. A. , Cosentino L. , Damone L. A. , Domingo-Pardo C , Dressler R. , Durán I. , Fernández-Domínguez B. , Ferrari A. , Ferreira P. , Finocchiaro P. , Furman V. , Göbel K. , García A. R. , Gawlik A. , Gilardoni S. , Glodariu T. , Gonçalves I. F. , González-Romero E. , Griesmayer E. , Guerrero C. , Harada H. , Heinitz S. , Jenkins D. G. , Jericha E. , Käppeler F. , Kadi Y. , Kalamara A. , Kavrigin P. , Kimura A. , Kivel N. , Knapova I. , Kokkoris M. , Kurtulgil D. , Leal-Cidoncha E , Lederer C. , Lerendegui-Marco J , Meo S. Lo , Lonsdale S. J. , Macina D. , Manna A. , Marganiec J. , Martínez T. , Masi A. , Massimi C. , Mastinu P. , Mastromarco M. , Maugeri E. A. , Mazzone A. , Mendoza E. , Mengoni A. , Milazzo P. M. , Mingrone F. , Musumarra A. , Negret A. , Nolte R. , Oprea A. , Patronis N. , Pavlik A. , Perkowski J. , Porras I. , Praena J. , Quesada J. M. , Radeck D. , Rauscher T. , Reifarth R. , Rubbia C. , Ryan J. A. , Sabaté-Gilarte M. , Saxena A. , Schumann D. , Sedyshev P. , Smith A. G. , Sosnin N. V. , Stamatopoulos A. , Tagliente G. , Tain J. L. , Tarifeño-Saldivia A. , Tassan-Got L , Vannini G. , Variale V. , Vaz P. , Ventura A. , Vlastou R. , Wallner A. , Warren S. , Weiss C. , Woods P. J. , Wright T. , Žugec P. ,   the n_TOF Collaboration
Published: September 2020

233U is the fissile nuclei in the Th-U fuel cycle with a particularily small neutron capture cross setion which is on average about one order of magnitude lower than its fission cross section. Hence, the measurement of the 233U(n, γ) cross section relies on a method to accurately distinguish between capture and fission γ-rays. A measurement of the 233U α-ratio has been performed at the n_TOF facility at CERN using a so-called fission tagging setup, coupling n_TOF 's Total Absorption Calorimeter with a novel fission chamber to tag the fission γ-rays. The experimental setup is described and essential parts of the analysis are discussed. Finally, a preliminary 233U α-ratio is presented.
Employing TALYS to deduce angular momentum rootmean-square values, Jrms, in fission fragments
Authors: Al-Adili A , Solders A. , Rakopoulos V.
Published: September 2020

Fission fragments exhibit large angular momenta J, which constitutes a challenge for fission models to fully explain. Systematic measurements of isomeric yield ratios (IYR) are needed for basic nuclear reaction physics and nuclear applications, especially as a function of mass number and excitation energy. One goal is to improve the current understanding of the angular momentum generation and sharing in the fission process. To do so, one needs to improve the modeling of nuclear de-excitation.

In this work, we have used the TALYS nuclear-reaction code to relax excited fission fragments and to extract root-mean-square (rms) values of initial spin distributions, after comparison with experimentally determined IYRs. The method was assessed by a comparative study on 252Cf(sf) and 235U(nth,f). The results show a consistent performance of TALYS, both in comparison to reported literature values and to other fission codes. A few discrepant Jrms values were also found. The discrepant literature values could need a second consideration as they could possibly be caused by outdated models. Our TALYS method will be refined to better comply with contemporary sophisticated models and to reexamine older deduced values in literature.
Measurement of the234U(n,f) cross section in the energy range between 14.8 and 17.8 MeV using Micromegas detectors
Authors: Kalamara A. , Chasapoglou S. , Michalopoulou V. , Stamatopoulos A. , Eleme Z. , Kokkoris M. , Lagoyannis A. , Patronis N. , Vlastou R.
Published: September 2020

The234U(n,f) reaction cross section was measured for three neutron energies 14.8, 16.5 and 17.8 MeV, relative to the238U(n,f) reference reaction. The in-beam measurements were carried out by using a set-up based on Micromegas detectors, while the quasi-monoenergetic neutron beams were produced by means of the3H(d,n)4He reaction at the 5.5MV Tandem T11/25 Accelerator Laboratory of the National Center for Scientific Research "Demokritos" in Athens (Greece). Additionaly,α-spectroscopy measurements were performed in order to determine the active mass of the samples and the corresponding impurities. In order to estimate the fission-fragment detection efficiency, Monte Carlo simulations were carried out using the GEF and FLUKA codes. Furthermore, simulations were also performed by coupling the NeuSDesc and MCNP5 codes for the determination of the neutron energy distribution in all the irradiated samples and the results were used in order to correct for the contribution of low energy parasitic neutrons in the fission yield. The final cross section data are presented, along with the methodology adopted for the treatment of the parasitic neutrons.
Study of the neutron-induced fission cross section of 237Np at CERN's n_TOF facility over a wide energy range
Authors: Stamatopoulos A. , Tsinganis A. , Diakaki M. , Colonna N. , Kokkoris M. , Vlastou R. , Kalamara A. , Schillebeeckx P. , Tassan-Got L , Žugec P. , Sabaté-Gilarte M. , Patronis N. , Eleme Z. , Heyse J. , Aberle O. , Andrzejewski J. , Audouin L. , Bacak M. , Balibrea J. , Barbagallo M. , Bečvář F. , Berthoumieux E. , Billowes J. , Bosnar D. , Brown A. , Caamaño M. , Calviño F. , Calviani M. , Cano-Ott D , Cardella R. , Casanovas A. , Cerutti F. , Chen Y. H. , Chiaveri E. , Cortés G. , Cortés-Giraldo M. A. , Cosentino L. , Damone L. A. , Domingo-Pardo C , Dressler R. , Dupont E. , Durán  , Femandez-Domínguez B. , Ferrari A. , Ferreira P. , Finocchiaro P. , Furman V. , Göbel K. , García A. R. , Gawlik A. , Gilardoni S. , Glodariu† T. , Gonçalves I. F. , González-Romero E. , Griesmayer E. , Guerrero C. , Gunsing F. , Harada H. , Heinitz S. , Jenkins D. G. , Jericha E. , Käppeler F. , Kadi Y. , Kavrigin P. , Kimura A. , Kivel N. , Knapova I. , Krtička M. , Kurtulgil D. , Leal-Cidoncha E , Lederer C. , Leeb H. , Lerendegui-Marco J , Meo S. Lo , Lonsdale S. J. , Macina D. , Manna A. , Marganiec J. , Martínez T. , Masi A. , Massimi C. , Mastinu P. , Mastromarco M. , Maugeri E. A. , Mazzone A. , Mendoza E. , Mengoni A. , Milazzo P. M. , Mingrone F. , Musumarra A. , Negret A. , Nolte R. , Oprea A. , Pavlik A. , Perkowski J. , Porras I. , Praena J. , Quesada J. M. , Radeck D. , Rauscher T. , Reifarth R. , Rubbia C. , Ryan J. A. , Saxena A. , Schumann D. , Sedyshev P. , Smith A. G. , Sosnin N. V. , Tagliente G. , Tain J. L. , Tarifeño-Saldivia A. , Valenta S. , Vannini G. , Variale V. , Vaz P. , Ventura A. , Vescovi D. , Vlachoudis V. , Wallner A. , Warren S. , Weiss C. , Woods P. J. , Wright T. ,   the n_TOF Collaboration
Published: September 2020

Neutron-induced fission cross sections of isotopes involved in the nuclear fuel cycle are vital for the design and safe operation of advanced nuclear systems. Such experimental data can also provide additional constraints for the adjustment of nuclear model parameters used in the evaluation process, resulting in the further development of fission models. In the present work, the 237Np(n,f) cross section was studied at the EAR2 vertical beam-line at CERN's n_TOF facility, over a wide range of neutron energies, from meV to MeV, using the time-of-flight technique and a set-up based on Micromegas detectors, in an attempt to provide accurate experimental data. Preliminary results in the 200 keV – 14 MeV neutron energy range as well as the experimental procedure, including a description of the facility and the data handling and analysis, will be presented.
Observations of poorly-known features of the 239Pu and 235U prompt fission neutron spectra
Authors: Kelly Keegan J. , Gomez Jaime A. , O'Donnell John M. , Devlin Matthew , Haight Robert C. , Taddeucci Terry N. , Mosby Shea M. , Lee Hye Young , Neudecker Denise , Kawano Toshihiko , Lovell Amy E. , Talou Patrick , White Morgan C , Ching-Yen Wu , Henderson Roger A. , Henderson Jack , Buckner Matthew Q.
Published: September 2020

Prompt fission neutron spectrum (PFNS) evaluations use provide nuclear data for the PFNS across a wide range of incident and outgoing neutron energies. However, experimental data underlying the evaluation are sparse, inconsistent, and incomplete with respect to the desired incident and outgoing energy coverage. As such, evaluations sometimes predict features of the PFNS, such those relating to multi-chance fission and pre-equilibrium pre-fission neutron emission, without any experimental validation. The Chi-Nu experiment at Los Alamos National Laboratory has recently obtained high-precision results for the 239Pu and 235U PFNS which, for the first time in both cases, have shed light on multi-chance fission and pre-equilibrium contributions to the observed fission neutron spectrum. In addition to providing the first experimental data on some of these fission properties, the angular coverage of the Chi-Nu experiment allows for the extraction of angular distributions of pre-equilibrium pre-fission neutrons. PFNS results of multi-chance fission and pre-equilibrium pre-fission neutron emission are discussed in this proceedings in terms of the observed neutron spectrum and the average PFNS energies.
New reaction rates for the destruction of7Be during big bang nucleosynthesis measured at CERN/n_TOF and their implications on the cosmological lithium problem
Authors: Mengoni A. , Damone L.A. , 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. , 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. , 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. , Doval D. Ramos , 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

New measurements of the7Be(n,α)4He and7Be(n,p)7Li reaction cross sections from thermal to keV neutron energies have been recently performed at CERN/n_TOF. Based on the new experimental results, astrophysical reaction rates have been derived for both reactions, including a proper evaluation of their uncertainties in the thermal energy range of interest for big bang nucleosynthesis studies. The new estimate of the7Be destruction rate, based on these new results, yields a decrease of the predicted cosmological7Li abundance insufficient to provide a viable solution to the cosmological lithium problem.
Beta-delayed gamma spectra in CENDL-3.2
Authors: Zhu Shuyu , Zhao Xiaoxue , Shu Nengchuan , Wu Haicheng , Liu Lin , Chen Yongjing , Liu Lile
Published: September 2020

A new program is developed to compute the beta delayed fission gamma spectrum, and applied to compute the spectra of n+235U, 239Pu and 241Pu fissions wherein the recent nuclear database is adopted. The results show that most spectra are well in agreement with the data from ENDF/B-VII.0 library, and some are quite different, which should be caused by the improvement of the nuclear database.
Unresolved resonance range processing and probability tables generation in the GAIA2 system
Authors: Jeannesson C. , Leal L. , Jouanne C. , Coste-Delclaux M.
Published: September 2020

The objective of this paper is to present the work carried out at the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) to process nuclear data in the unresolved resonance range (URR). Recently, a great deal of effort has been devoted at IRSN to develop an independent nuclear data processing system, GAIA2. First, a nuclear data storing object, independent from the ENDF-6 format, has been implemented in order to transmit information between the components of a module-based scheme. Then, the generation of probability tables in the URR has been added as an independent module named TOP (as Table Of Probability), and tested on a selected set of benchmarks. The methods used and the results are discussed, and some limitations in the manner to construct the tables are pointed out.
NDPlot - A plotting tool for nuclear data
Authors: Jin Yongli , Tao Xi , Wang Jimin , Shu Nengchuan , Qian Jing , Ge Zhigang
Published: September 2020

NDPlot is an efficient plotting tool for nuclear data. It is not only a plotting tool, but also an integrated application system. The first beta version of NDPlot was released in October 2018. The current version is 0.94 beta. NDPlot can plot experimental and evaluated data of reaction cross sections, angular distributions of secondary particles, energy distributions of secondary particles and product energy-angle distributions etc. It also provides data processing functions such as curve summation capability to meet user’s requirements.
The systematics of neutron reaction cross sections
Authors: Wang Jimin , Tao Xi , Huang Xiaolong , Ge Zhigang
Published: September 2020

The parameterized theoretical formulae of excitation functions for (n, 2n) and (n, γ) reactions have been established, and for (n,tot), (n,non), (n,3n), (n,p), (n,d), (n,t), (n,3 He) and (n,α) have been recommended. According to these formulae, the SEF code have been developed for systematics calculation of these reactions. The calculated results with the systematics of the corresponding reactions of the discretional nucleus can be provided by the SEF code in the applied range quickly. At the same time, the comparison of calculated results with experimental and evaluated data can be given graphically.
New 23Na evaluation in the resolved resonance range taking into account both differential and double differential experiments
Authors: Tamagno Pierre , Archier Pascal , De Saint Jean Cyrille , Noguère Gilles
Published: September 2020

In 2012 CEA produced a entire new evaluation of sodium nuclear data for the release of the JEFF-3.2 evaluated nuclear data library. During the evaluation process performed with the CONRAD code, several differential measurements (total and discrete inelastic cross-sections) have been used. However double differential data (elastic angular distribution) that were yet available in the EXFOR database were not incorporated in the analysis at that time. The experimental elastic angular distribution were discarded because of it was impossible to obtain a good agreement for both angle-integrated cross-sections and double differential ones. The underlying cause of this disagreement is expected to be due to the attribution of quantum numbers to resonance and related channel amplitudes. Indeed these numbers are imposed during the analysis but impact differently angular distributions and angle-integrated cross-sections. An automated search for an accurate set of quantum numbers has been implemented in order to produce a reliable quantum numbers set. In this paper we present a new evaluation of Na-23 taking into account both differential and double differential measurements. The analysis performed with the CONRAD code reached the level of agreement with experimental data for the total and inelastic cross-sections but this time with a significant improvement for the elastic angular distributions. This new evaluation produced in the ENDF-6 format has then been tested and validated on critical facilities calculation (MASURCA and ZPPR) in different configurations (nominal and voided) in order to assess its performances.
Data assimilation of post irradiation examination experiments to adjust fission yields
Authors: Siefman Daniel , Hursin Mathieu , Pautz Andreas
Published: September 2020

Nuclear data, especially fission yields, create uncertainties in the predicted concentrations of fission products in spent fuel. Herein, we present a new framework that extends data assimilation methods to burnup simulations by using data from post-irradiation examination experiments. The adjusted fission yields improve the bias and reduce the uncertainty of predicted fission product concentrations in spent fuel. Our approach modifies fission yields by adjusting the model parameters of the code GEF with post-irradiation examination experiments. We used the BFMC data assimilation method to account for the non-normality of GEF's fission yields. In the application that we present, the assimilation decreased the average bias of the predicted fission product concentrations from 26% to 15%. The average relative standard deviation decreased from 21% to 14%. The GEF fission yields after data assimilation agreed better with those in ENDF/B-VIII.O. For Pu-239 thermal fission, the average relative difference from ENDF/B-VIII.O was 16% before data assimilation and 11% after. For the standard deviations of the fission yields, GEF's were, on average, 16% larger than those from ENDF/B-VIII.O before data assimilation and 15% smaller after.
Validated scattering kernels for triphenylmethane at cryogenic temperatures
Authors: Cantargi Florencia , Dawidowski Javier , Helman Christian , Márquez Damian José Ignacio , Granada Rolando Jose , Romanelli Giovanni , Cuello Julio Gabriel , Skoro Goran , Krzystyniak Matthew
Published: September 2020

Cold neutrons are widely used in different fields of research such as the study of the structure and dynamics of solids and liquids, the investigation of magnetic materials, biological systems, polymer science, and a rapidly growing area of industrial applications. In a pulsed neutron source where the pulse width is an important parameter to be considered, hydrogenated materials are often used because of their high energy transfer in each collision. The preliminary scattering kernel for triphenylmethane, a material of great potential interest for cold neutron production, had been presented at the ND2016 conference. Here, a new model for the generation of the scattering kernels for this material, together with experimental results on its total cross section measured at the VESUVIO instrument (ISIS Neutron and Muon Source, United Kingdom) is presented. The thermal scattering kernel was generated by means of the NJOY Nuclear Data Processing system, using as input the vibrational modes obtained by density functional theory techniques (DFT). The agreement between measurements and our model validates the scattering kernel construction and the cross section library generated in ENDF and ACE formats.
Measurement of the neutron energy spectrum of Back-n #ES1 at CSNS
Authors: Chen Yonghao , Luan Guangyuan , Bao Jie , Jing Hantao , An Qi , Bai Huaiyong , Cao Ping , Chen Qiping , Cheng Pinjing , Cui Zengqi , Fan Ruirui , Feng Changqing , Gu Minhao , Guo Fengqin , Han Changcai , Han Zijie , He Guozhu , He Yongcheng , He Yuefeng , Huang Hanxiong , Huang Weiling , Huang Xiru , Ji Xiaolu , Ji Xuyang , Jiang Haoyu , Jiang Wei , Kang Ling , Kang Mingtao , Li Bo , Li Lun , Li Qiang , Li Xiao , Li Yang(a) , Li Yang(b) , Liu Rong , Liu Shubin , Liu Xingyan , Ma Yinglin , Ning Changjun , Qi Binbin , Ren Jie , Ruan Xichao , Song Zhaohui , Sun Hong , Sun Xiaoyang , Sun Zhijia , Tan Zhixin , Tang Hongqing , Tang Jingyu , Wang Pengcheng , Wang Qi , Wang Taofeng , Wang Yanfeng , Wang Zhaohui , Wang Zheng , Wen Jie , Wen Zhongwei , Wu Qingbiao , Wu Xiaoguang , Wu Xuan , Xie Likun , Yang Yiwei , Yi Han , Yu Li , Yu Tao , Yu Yongji , Zhang Guohui , Zhang Jing , Zhang Linhao , Zhang Liying , Zhang Qingming , Zhang Qiwei , Zhang Xianpeng , Zhang Yuliang , Zhang Zhiyong , Zhao Yingtan , Zhou Liang , Zhou Zuying , Zhu Danyang , Zhu Kejun , Zhu Peng
Published: September 2020

The China spallation neutron source (CSNS) was built and started running since 2018. It produces neutrons by impinging 1.6 GeV protons onto a tungsten target with 25 Hz repetition frequency. A beam line exploiting the back-streaming neutrons (Back-n) was built mainly for nuclear data measurement and started commissioning simultaneously with CSNS in 2018. There are two experimental endstations along the Back-n beam line: endstation 1 (#ES1) with a neutron flight path of about 55 m and endstation 2 (#ES2) with about 76 m. The neutron energy spectra of both #ES1 and #ES2 were measured since it is important for feasibility study and analysis. In this paper, the measurement of the neutron energy spectrum of Back-n #ES1 is reported. It is measured by a multi-layer fission chamber using the 235U samples as the neutron converters. The neutron energy spectrum from 0.1 eV to 30 MeV is obtained. The integral neutron flux (from 0.1 eV to 30 MeV) normalized to the proton beam power of 100 kW is 1.55×107 neutrons/cm2/s.
Validation of heavy water cross section using AmBe neutron source
Authors: Kostal Michal , Schulc Martin , Novak Evzen , Czakoj Tomas , Matej Zdenek , Cvachovec Frantisek , Mravec Filip , Jansky Bohumil , Leal Luiz
Published: September 2020

Physical quantities derived from integral experiments can usually be measured much more accurately than that from differential nuclear data. The accurate knowledge of integral parameters provide excellent grounds for testing and tuning differential data such as, for instance, cross sections. Measurement of neutron leakage spectra with 252Cf neutron source located at sphere center is often used for integral experiments. While this type of experiments provide information for cross section tuning, however, care must be taken to avoid misleading interpretation, namely, at high energies due to the very low portion of high energy neutrons in 252Cf spectrum. This issue can be alleviated by the use of point source with different spectra shape. For that purpose one suitable candidate seems to be the AmBe neutron source which has a relatively high average energy and peak character of emitted neutrons. Indeed, AmBe seems an interesting option because the calculated leakage neutron spectra are not very sensitive to the input shape of the neutron spectra. Thus the neutron leakage spectra calculated using tabulated of International Organization for Standardization spectra is nearly the same as stilbene measured AmBe spectra as an input.
Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction
Authors: Kral Dusan , Zeman Miroslav , Katovsky Karel , Melyan Elmira , Holomb Robert
Published: September 2020

Threshold activation detectors (TAD) are of great importance for a determination of neutron energy spectra and flux density. For different sources, it is necessary to choose the right combination of materials that cover the estimated spectra. Several different materials were irradiated in a quasi-monoenergetic neutron field with 29.1 MeV peak neutrons energy in the CANAM facility. Neutrons were produced in p + Li-7 reaction in a thin target and the foils were situated in the proton beam axis and close geometry to the Li target. The integral number of protons was established from accelerator telemetry and lithium target activation measurements after the experiment. During the experiment, one long irradiation was done for following foils: Al, Au, Bi, Co, Cu, Fe, In, Mn, Pb, Ta, V, Y and four short irradiations for foils: Cu, Fe, In, Ta, V, W, Y. The foils were irradiated in a sandwich configuration, sorted by cross-section where the materials with higher cross-section were placed in the back of the sandwich. Neutrons produced in the p + Li-7 reaction have a quasi mono-energetic spectrum which provides a suitable basis for cross-section determination. Experimental results were calculated for (n,xn), (n,p) and (n,α) reactions via the dosimetry foils activation method including a gamma-ray spectroscopy method. Several important spectroscopic corrections have to be applied to increase the accuracy of the obtained results, including neutron background suppression. Experimental data will be submitted to the EXFOR database.
Total neutron cross-section extracted from transmission experiments with liquid oxygen using neutron energies from 18 to 27 MeV
Authors: Ansorge Martin , Bém Pavel , Hladík David , Majerle Mitja , Mrázek Jaromír , Novák Jan , Šimečková Eva , Štefánik Milan
Published: September 2020

Fast neutron generators driven by isochronous cyclotron U-120M developed at Nuclear Physics Institute were used for neutron cross-section measurements. The target station with 2 mm thin lithium was used to produce pulsed beams of fast quasi-monoenergetic neutrons in the 7Li(p,n) reaction. The Time-of-Flight technique was used to determine the exact neutron energy spectra. The transmission measurements on liquid oxygen were conducted for several neutron peak energies between 18 and 27 MeV and the cross-sections for reaction natO(n,tot) were derived.
Nuclear data activities of the EUROfusion consortium
Authors: Fischer Ulrich , Avrigeanu Marilena , Avrigeanu Vlad , Konobeyev Alexander , Kodeli Ivo , Leeb Helmut , Fleming Michael , Gilbert Mark , Rochman Dimitri , Pereslavtsev Pavel , Sauvan Patrick , Schnabel Georg , Simakov Stanislav , Sjöstrand Henrik
Published: September 2020

The activities of the EUROfusion consortiums on the development of high quality nuclear data for fusion applications are presented. The activities, implemented in the Power Plant Physics and Technology (PPPT) programme of EUROfusion, include nuclear data evaluations for neutron and deuteron induced reactions and the production of related data libraries which satisfy the needs for nuclear analyses of the DEMO fusion power plant and the IFMIF-DONES neutron source. The activities are closely linked to the JEFF initiative of the NEA Data Bank. The evaluation work is complemented by extensive benchmark, sensitivity and uncertainty analyses to check the performance of the evaluated cross-section data and libraries against integral experiments.
Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
Authors: Vasiliev Alexander , Pecchia Marco , Rochman Dimitri , Perret Gregory , Ferroukhi Hakim , Laureau Axel , Lamirand Vincent , Pautz Andreas
Published: September 2020

The international experimental program PETALE will be carried out at the CROCUS research reactor of EPFL. The program aims at measuring neutron penetration in slabs made of materials composing typical LWR reactor pressure vessel. The measurements will be used for code and nuclear data validation and for the evaluation of the reflecting properties of these materials. In this paper the representativity of the PETALE experiments is assessed with respect to operational LWR reactors dosimetry and activation evaluations using the Paul Scherrer Institute (PSI) in-house tool NUSS. The NUSS tool allows the stochastic sampling of nuclear data using covariance matrices available in modern nuclear data libraries and the subsequent running of a Monte Carlo code with the modified data files. The representativity can then be assessed based on the Pearson correlation coefficients. The ultimate goal of the work is first of all to assess if the planned PETALE measurements could be applicable beyond their primary purpose and serve for extending the PSI validation database for LWR reactor dosimetry evaluations. Secondly, provided that the PETALE measurements are found useful for the task above, the information on the correlations between the PETALE neutron detectors’ responses and the reactor dosimetry quantities of interest, shall be presented and discussed.
Measurement of temperature-dependent thermal neutron spectrum in CaH2 moderator material for space reactor
Authors: lee Jaehong , Sano Tadafumi , Hori Jun-ichi , Kimura Rei , Sako Takayuki , Yamada Akira , Nishiyama Jun
Published: September 2020

In order to accurately design a CaH2 moderated small high-temperature reactor, it is necessary to experimentally confirm the temperature-dependent thermal neutron spectrum in the CaH2 moderator material. To obtain the temperature-dependent thermal neutron spectrum in the CaH2, we have carried out the neutron scattering experiment using the TOF method at the Kyoto University Institute for Integrated Radiation and Nuclear Science - Linear Accelerator (KURNS-LINAC). In present experiment, we raised the temperature of the CaH2 from a room temperature 294 k to 392 K and 565 K, and obtained the change of the thermal neutron TOF spectrum for the increase of temperature. The obtained thermal neutron TOF spectra in the CaH2 are compared with the calculated results using the Monte-Carlo simulation code MCNP-6.2.
Evolution of the importance of neutron-induced reactions along the cycle of an LFR
Authors: Romojaro Pablo , Álvarez-Velarde Francisco
Published: September 2020

The Lead-cooled Fast Reactor is one of the three technologies selected by the Sustainable Nuclear Energy Technology Platform that can meet future European energy needs. Several LFR concepts are now in design phase, such as MYRRHA and ALFRED, and accurate nuclear data are required for the neutronic and safety assessment of the fast reactor designs. In this work, an assessment of the evolution of the importance of neutron-induced reactions along the cycle of a reference LFR design (i.e., ALFRED) with the state-of-the-art JEFF-3.3 nuclear data library is performed. Sensitivity analyses have been carried out with MCNP6 code in order to identify the most relevant isotopes and reactions from the neutronic point of view at BoL, BoC and EoC. Furthermore, an uncertainty quantification has been performed with the SUMMON system to study the evolution of uncertainties in the keff along the reactor cycle. The results from this work provide an exhaustive picture on the influence of nuclear data on core criticality performance, identifying key quantities and nuclear data needs relevant to achieve an improved safety level for LFR.