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Auteur : Grafiati
Publié le 11 mars 2023

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1

Seleznev, E., V. Bereznev et I. Chernova. « TO EXPERIMENTAL EVALUATION OF SOLUTIONS OF PARTIAL NEUTRON TRANSPORT EQUATIONS IN FAST BREEDER REACTORS ». PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES : NUCLEAR AND REACTOR CONSTANTS 2019, no 3 (26 septembre 2019) : 163–69. http://dx.doi.org/10.55176/2414-1038-2019-3-163-169.

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Solutions of the partial neutron transport equations, being components of the neutron flux density, which is usually measured by ionization chambers, would seem to not be fixed experimentally. But ionization chambers can be created on the basis of various fissile materials, including those having a threshold fission cross section, which is used in experiments on active reactors to “filter” the signal from the background, when, for example, the signal in the chamber is used only on the basis of high-energy neutrons eliminate taking into account the ionization of the gas medium in the ionization chamber from gamma-quanta, i.e. exclude the background. Such ionization chambers include cameras based on the use of 232Th, 238U, 236U, 237Np, 234U with a fission threshold energy of 1.5, 1.3, 0.70, 0.32 and 0.26 MeV, respectively. Together with the use of a 235U non-threshold chamber, these chambers offer the possibility of obtaining some experimental estimates of the partial solutions of the neutron transport equations in a fast neutron reactor. At the same time, the use of a threshold ionization chamber that records only a fraction of the neutrons from their full spectrum during a non-stationary process in a reactor with a change in the fraction of delayed neutrons in it, i.e. amplification of one or another part of the neutron spectrum may not fully take into account these changes and, thus, increase the measurement error. The possibility of estimating the magnitude of such an error is given by partial solutions of the neutron transport equations.
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Khrushchinsky, A. A., et S. A. Kuten. « Primary Ionization Density Produced by Charged Fragments in the Working Volume of the Fission Chambers ». Nonlinear Phenomena in Complex Systems 24, no 4 (10 décembre 2021) : 329–37. http://dx.doi.org/10.33581/1561-4085-2021-24-4-329-337.

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The question of the spatial distribution of ion pairs created by 235U fission fragments in the active volume of the fission chamber has been studied. The formulas of the spatial distribution of ion pairs in cylindrical fission chambers are proposed, which allows you to evaluate correctly the density of ion pairs in any point in the sensitive volume of the fission chamber
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3

Hecht, Adam, Phoenix Baldez et Baldez Baldez. « Developments in New Measurements of Fission Cross-Sections, Fragment Yields, and Prompt and Quasi-Prompt Gammas for Nuclear Data Needs ». EPJ Web of Conferences 242 (2020) : 01002. http://dx.doi.org/10.1051/epjconf/202024201002.

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The University of New Mexico Fission Spectrometer was developed to measure fission product yield, as part of the LANL SPIDER collaboration. The spectrometer operates as an E-v detector to extract product mass event-by-event, with a time of flight region followed by an ionization chamber for kinetic energy measurements. By using the ionization chamber as a singlecathode/single-anode time projection chamber, stopping power and thus Z information is extracted, for coupled A and Z measurements. New work is being performed to add gamma ray detectors in the data stream, placed near the target region for prompt gammas and near the ionization chamber for quasiprompt (>50 ns) and later gammas, correlated with individual fission products. A stand-alone parallel plate ionization chamber (PPIC) is also being developed for fission tagging gamma ray data. The PPIC will also allow discrimination between charged particle out events and (n,n’γ), and discriminate between alpha emission and fission. Using layers in the PPIC, other targets can be measured simultaneously with a calibration target, giving relative fission cross sections. Past measurements with the spectrometer were performed at LANSCE and we plan to continue measurements there. The current work is supported by the NNSA Stewardship Science Academic Alliance.
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4

Zeinalov, Sh, P. Sedyshev, O. Sidorova et V. Shvetsov. « Nuclear fission investigation with twin ionization chamber ». International Journal of Modern Physics : Conference Series 50 (janvier 2020) : 2060013. http://dx.doi.org/10.1142/s2010194520600137.

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In this paper, we report recent results obtained in the development of digital pulse processing mathematics for prompt fission neutron (PFN) investigations using a twin ionization chamber (TIC) along with a fast neutron time-of-flight detector (ND). Due to some ambiguities in the literature concerning a pulse induction on TIC electrodes by fission fragment (FF) ionization, we first presented a detailed mathematical analysis of FF signal formation on the TIC anode. The analysis was done using the Shockley–Ramo theorem, which gives the relation between charged particle motion between TIC electrodes and the so-called weighting potential. The weighting potential was calculated by direct numerical solution of the Laplace equation (neglecting space charge) for the TIC geometry and ionization caused by FFs. Formulae for GI correction and digital pulse processing algorithms for PFN time-of-flight measurements and pulse shape analysis are presented and used in experiments for PFN investigations of two reactions, [Formula: see text]U(n[Formula: see text],f) and [Formula: see text]Cf(sf). Results of the measurements were compared to literature data to demonstrate the feasibility of the new developed techniques. These results were necessary for the development of a new PFN investigation facility consisting of a position sensitive fission fragment detector combined with 32 liquid scintillation neutron detectors.
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Ai, Ju Mei, et Qiang Wang. « Study on the Measurement of U-238 Neutron Yield Base on the Fission Chamber ». Advanced Materials Research 366 (octobre 2011) : 474–77. http://dx.doi.org/10.4028/www.scientific.net/amr.366.474.

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This paper discusses a variety of fission neutron yield measurement method, a D-T / D-D neutron yield monitoring of U-238 fission ionization chamber measuring system, the application of spontaneous decay of U-238 α-particles for initial debugging of the system. At different voltage on the α-particle energy spectrum and α particle counts were measured, given the U-238 fission chamber curve to determine the U-238 fission chamber measurement system the best operating parameters.
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6

Zeynalov, Sh, O. Zeynalova, F. J. Hambsch, P. Sedyshev et V. Shvetsov. « Ionization Chamber for Prompt Fission Neutron Investigations ». Physics Procedia 59 (2014) : 160–66. http://dx.doi.org/10.1016/j.phpro.2014.10.025.

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7

Tovesson, F., D. Duke, V. Geppert-Kleinrath, B. Manning, D. Mayorov, S. Mosby et K. Schmitt. « Fission fragment yields and total kinetic energy release in neutron-induced fission of235,238U,and239Pu ». EPJ Web of Conferences 169 (2018) : 00024. http://dx.doi.org/10.1051/epjconf/201816900024.

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Different aspects of the nuclear fission process have been studied at Los Alamos Neutron Science Center (LANSCE) using various instruments and experimental techniques. Properties of the fragments emitted in fission have been investigated using Frisch-grid ionization chambers, a Time Projection Chamber (TPC), and the SPIDER instrument which employs the 2v-2E method. These instruments and experimental techniques have been used to determine fission product mass yields, the energy dependent total kinetic energy (TKE) release, and anisotropy in neutron-induced fission of U-235, U-238 and Pu-239.
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Zeynalov, Shakir, Pavel Sedyshev, Olga Sidorova, Valery Shvetsov et Leonid Svetov. « Position sensitive twin ionization chamber for nuclear fission investigations ». International Journal of Modern Physics : Conference Series 48 (janvier 2018) : 1860123. http://dx.doi.org/10.1142/s2010194518601230.

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In this article, we report the recent achievements in the design of a back-to-back twin ionization chamber (TIC) for fission fragment (FF) mass, kinetic energy, and orientation. Correlated FF kinetic energies, their masses, and the angle of the fission axes in 3D Cartesian coordinates can be determined from analysis of the heights and shapes of the pulses induced by the FFs on the anodes of the TIC. These anodes were designed to consist of isolated [Formula: see text]-shaped strips connected to nodes of a chain filter made of serially-connected two-port networks. The double charge division method was implemented by digitizing four waveforms at the endpoints of the chain filters. It was shown that the fission fragments emission point on the target plane may be determined using the measured data. A position-sensitive neutron-induced fission detector for neutron imaging applications with both thermal and low energy neutrons was found as another possible implementation of the designed TIC. Preliminary measurements with thermal neutron-induced fission were done with RC chain filters and the results are reported here.
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9

Budtz-Jørgensen, C., H. H. Knitter, Ch Straede, F. J. Hambsch et R. Vogt. « A twin ionization chamber for fission fragment detection ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 258, no 2 (août 1987) : 209–20. http://dx.doi.org/10.1016/0168-9002(87)90058-1.

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10

Peck, Marius, Joachim Enders, Martin Freudenberger, Alf Göök, Andreas Oberstedt et Stephan Oberstedt. « Tests of ionization chambers for future photofission experiments ». EPJ Web of Conferences 193 (2018) : 04006. http://dx.doi.org/10.1051/epjconf/201819304006.

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A recent set-up of a multi-cathode Frisch-grid ionization chamber and experimental results of a proof-of-principle experiment are presented. Preliminary data on the obtained polar angular and mass distributions as well as total kinetic energy of fission fragments produced in neutron-induced fission of 232Th and 238U are discussed that show that the chamber has been operated successfully. For the additional measurement of the azimuthal angular distribution, a design of segmented anodes has been tested. Preliminary data do not allow a suffcient reconstruction of the azimuthal angle.
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11

Trinh, Dinh Hai, Van Tai Vo, Van Diep Le et Nhi Dien Nguyen. « Design and Construction of a Preamplifier for Research Reactor Control System Using Russia’s Neutron Detectors ». Nuclear Science and Technology 6, no 3 (30 septembre 2016) : 8–15. http://dx.doi.org/10.53747/jnst.v6i3.159.

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This paper presents the design and construction of a preamplifier device for Research Reactor Control System, using Russia’s Neutron Detectors of ionization and fission chambers. In this work, the preamplifier device which consists of a wide range Current to Frequency Converter block used with a compensation ionization chamber type KNK-3 to measure the thermal neutron flux in the range of 1x106 ¸ 1x1011 n/cm2.s, a Pulse Preamplifier block used with a fission chamber type KNK-15 to measure the thermal neutron flux in the range of 1x100 ¸ 1x106 n/cm2.s, and a Power Supply block, was designed and tested in different conditions in the laboratory and at Dalat Nuclear Research Reactor (DNRR). Obtained results show that, the above blocks have almost design specifications as equivalent or better in comparison with the same function blocks of the DNRR’s Control System which were designed by the former Soviet Union. They also meet the utilization requirements as well as the experimental and training purposes.
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12

Doré, D., E. Berthoumieux, Q. Deshayes, L. Thulliez, P. Legou, M. Combet, M. Kebbiri et al. « Performance validation of the first arm of FALSTAFF : 252Cf and 235U fission fragment characterisation ». EPJ Web of Conferences 211 (2019) : 04002. http://dx.doi.org/10.1051/epjconf/201921104002.

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The renewed interest for the study of nuclear fission is mainly motivated by the development of GEN-IV reactor concepts, mostly foreseen to operate in the fast neutron energy domain. To support this development, new high-quality nuclear data are needed. In this context, a new experimental setup, the FALSTAFF spectrometer, dedicated to the study of nuclear fission is under development. Employing the double-velocity (2V) and energy-velocity (EV) methods, the fission fragment mass before and after neutron evaporation will be deduced and the correlation between prompt neutron multiplicity and fragment mass will be determined. The first arm of the spectrometer is achieved. It is composed of two SED-MWPC detectors (a combination of a foil to produce secondary electrons and a Multi-Wire Proportional Chamber to detect them) and an axial ionization chamber. The SED-MWPC give access to the velocity (V) via time-of-flight and position measurements. The ionization chamber measures the fragment kinetic energy (E) and the energy loss profile. Preliminary results for spontaneous fission of 252Cf and from the thermal-neutron induced fission experiment on 235U, performed at the Orphée reactor (CEA-Saclay, France), are presented.
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13

Khrushchinsky, A. A., S. A. Kuten, K. A. Verenich, L. F. Babichev et Thi Dieu Hien Le. « Optimization of the Radiator Composition of a "Non-Burning" Fission Ionization Chamber ». Nonlinear Phenomena in Complex Systems 24, no 2 (25 juin 2021) : 166–74. http://dx.doi.org/10.33581/1561-4085-2021-24-2-166-174.

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The paper is devoted to the analysis and optimization of the composition of the fission ionization chamber radiator, consisting of a mixture of two and three nuclides, to ensure the constant sensitivity of the chamber over a long period of time.
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14

Peck, Marius, Uwe Bonnes, Joachim Enders, Alf Göök, Joerg Hehner et Stephan Oberstedt. « Performance of a twin position-sensitive Frisch-grid ionization chamber for photofission experiments ». EPJ Web of Conferences 239 (2020) : 05011. http://dx.doi.org/10.1051/epjconf/202023905011.

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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.
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15

Gaudefroy, Laurent, et Adeline Ebran. « Production yields of micro-second isomers populated in 252Cf(SF) ». EPJ Web of Conferences 242 (2020) : 01003. http://dx.doi.org/10.1051/epjconf/202024201003.

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A twin Frisch grid ionization chamber loaded with an ultra-thin 252 Cf sample is used in order to detect spontaneous fission events. The chamber is surrounded by 8 HPGe detectors allowing to perform γ-spectroscopic measurements. We are interested in the decay of isomeric states populated in fission fragments. In this contribution we report on preliminary results on production yields of isomeric states with half-lives ranging from few nanoup to few micro-seconds.
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16

Kuchmagra, O., I. Maznii, H. Odynokin, A. Sadovnikov, A. Skorbun et S. Stadnik. « Fission Ionization Chamber as Reference Source in Neutron Flux Analysis ». Nuclear and Radiation Safety, no 4(76) (17 novembre 2017) : 45–49. http://dx.doi.org/10.32918/nrs.2017.4(76).07.

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The paper considers the statistics of intervals between neutron registration by the detecting system based on fission ionization chamber KHT31-1, statistics of intervals between noise signal impulses in absence of neutrons and possibility to distinguish neutron flows from different sources. It is shown that spurious noise signal from alpha decay of 234U in a radiator of the ionization chamber KHT31-1 can be used as a reference signal in measuring neutron fluxes from different sources. The analysis of long-term continuous sets of measurements is taken as a basis of mathematical treatment.
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17

Bacak, M., M. Aiche, G. Bélier, E. Berthoumieux, M. Diakaki, E. Dupont, F. Gunsing et al. « Preliminary results on the 233U capture cross section and alpha ratio measured at n_TOF (CERN) with the fission tagging technique ». EPJ Web of Conferences 211 (2019) : 03007. http://dx.doi.org/10.1051/epjconf/201921103007.

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233U is of key importance among the fissile nuclei in the Th-U fuel cycle. A particularity of 233U is its small neutron capture cross-section, which is on average about one order of magnitude lower than the fission cross-section. The accuracy in the measurement of the 233U capture cross-section depends crucially on an efficient capture-fission discrimination, thus a combined set-up of fission and γ-detectors is needed. A measurement of the 233U capture cross-section and capture-to-fission ratio was performed at the CERN n_TOF facility. The Total Absorption Calorimeter (TAC) of n_TOF was employed as γ-detector coupled with a novel compact ionization chamber as fission detector. A brief description of the experimental set-up will be given, and essential parts of the analysis procedure as well as the preliminary response of the set-up to capture are presented and discussed.
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Zeynalov, Shakir, Pavel Sedyshev, Valery Shvetsov et Olga Sidorova. « Prompt Fission Neutron Investigation in 235U(nth,f) and 252Cf(sf) Reactions ». EPJ Web of Conferences 211 (2019) : 04003. http://dx.doi.org/10.1051/epjconf/201921104003.

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The prompt neutron emission in thermal neutron induced fission of 235U and spontaneous fission of 252Cf was investigated by using digital signal electronics. The goal was to check a new revised data analysis software with fission fragment (FF) kinetic energy corrections after prompt fission neutron (PFN) emission. The revised software was used to reanalyze old data measured in EC-JRC-IRMM, where 252Cf(sf) reaction was investigated. Both measurements were done using similar twin Frisch grid ionization chamber for fission fragment detection with equivalent NE213 fast neutron detector. About 0.5*106 FF with PFN coincidences have been analyzed in both measurements. The fission fragment kinetic energy, mass and angular distribution were investigated along with prompt neutron time of flight and pulse shape analysis using a six channel synchronous waveform digitizer (WFD) with sampling frequency of 250 MHz and 12 bit resolution in the 235U(nth,f) reaction. Similar WFD with sampling frequency of 100 MHz was used for PFN investigation in 252Cf(sf) reaction. These two experiments were considered as a reference for further investigations with a new setup composed of position sensitive ionization chamber to detect FF and an array of 32 liquid scintillators recently constructed in Dubna to detect neutrons.
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Skobelev, A., et A. Nikolaev. « CALCULATION OF THERMAL NEUTRON FLUX IN RADIATION SHIELDING BY PROGRAM FRIGATE WITH USING A SUBMODELLING METHOD ». PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES : NUCLEAR AND REACTOR CONSTANTS 2020, no 1 (26 mars 2020) : 50–58. http://dx.doi.org/10.55176/2414-1038-2020-1-50-58.

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Using the example of calculating the thermal neutron flux density in an ionization chamber, where a methodically correct solution is required to be obtained only within a fragment of the computational model, and particle transport from the source to the studied region can be carried out in a more rough approximation, the use of DSN-DSN schemes discrete ordinate method on grids with a completely heterogeneous structure in combination with the submodeling method. The paper presents the results of calculating the thermal neutron flux density and the number of fission reactions in the sensitive part of an ionization chamber located in a concrete radiation protection shaft using the FRIGATE program (DSN method using the submodeling method) and cross-validation with the TDMCC program (Monte-Carlo method). The work continued the study, aimed at verifying the method of submodeling by spatial, angular, and energy variables, recommended for use in radiation protection calculations by deterministic codes. Cross-verification was performed using the FRIGATE DSN program and the TDMCC Monte Carlo code using the example of calculating the thermal neutron flux density and the number of fission reactions in the sensitive part of the fission ionization chamber. Verification results showed good agreement between the considered functionals (constant methodological discrepancy within 25 %). The obtained results confirm the effectiveness of using DSN programs in combination with irregular grids and the submodeling method in radiation protection calculations.
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Ivanov, M. P., G. M. Ter-Akopian, B. V. Fefilov et A. S. Voronin. « Study of 238U spontaneous fission using a double ionization chamber ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 234, no 1 (janvier 1985) : 152–57. http://dx.doi.org/10.1016/0168-9002(85)90821-6.

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Kögler, Toni, Roland Beyer, Arnd R. Junghans, Ronald Schwengner et Andreas Wagner. « Determination of the fast-neutron-induced fission cross-section of 242Pu at nELBE ». EPJ Web of Conferences 169 (2018) : 00009. http://dx.doi.org/10.1051/epjconf/201816900009.

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The fast-neutron-induced fission cross section of 242Pu was determined in the energy range of 0.5 MeV to 10MeV at the neutron time-of-flight facility nELBE. Using a parallel-plate fission ionization chamber this quantity was measured relative to 235U(n,f). The number of target nuclei was thereby calculated by means of measuring the spontaneous fission rate of 242Pu. An MCNP 6 neutron transport simulation was used to correct the relative cross section for neutron scattering. The determined results are in good agreement with current experimental and evaluated data sets.
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Higgins, Daniel, Uwe Greife, Shea Mosby et Fredrik Tovesson. « Total kinetic energy and fragment mass distributions from fission of Th-232 and U-233 ». EPJ Web of Conferences 193 (2018) : 02003. http://dx.doi.org/10.1051/epjconf/201819302003.

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Properties of fission in Th-232 and U-233 were studied at the Los Alamos Neutron Science Center at incident neutron energies from subthermal to 40 MeV. Fission fragments are observed in coincidence using a twin ionization chamber with Frisch grids. The average total kinetic energy released from fission and fragment mass distributions are calculated from observations of energy deposited and conservation of mass and momentum. Accurate experimental measurements of these parameters are necessary to better understand the fission process in isotopes relevant to the thorium fuel cycle, in which Th-232 is used as a fertile material to generate the fissile isotope of U-233. This process mirrors the uranium breeder process used to produce Pu-239 with several potential advantages including the comparative greater abundance of thorium, inherent nuclear weapons proliferation resistance, and reduced actinide production. Thus, there is increased interest in the thorium fuel cycle to meet future energy demands and improve safety and security while increasing profitability for the nuclear power industry. This research is ongoing and preliminary results are presented.
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Chen, Hongfei, XiaoJun Sun, Pu Zheng, Jun Xiao, Tonghua Zhu, Junjie Sun, Jianyu Zhu, Yu Cao, Jie Yan et Zhenghong Li. « Detection of correlated fission fragments with a twin Frisch-grid ionization chamber ». Journal of Instrumentation 17, no 09 (1 septembre 2022) : P09004. http://dx.doi.org/10.1088/1748-0221/17/09/p09004.

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Abstract Twin Frisch-grid ionization chambers (TFGICs) have been widely used in the measurement of total kinetic energy (TKE), angular distribution, mass, and charge of the correlated fission fragments. To study these correlated fission parameters, we have developed a TFGIC with a digital acquisition system for use at both the Chinese Mianyang research reactor (CMRR) and neutron science facility in the Institute of Nuclear Physics and Chemistry (INPC), as well as the China Spallation Neutron Source (CSNS). The distribution of the electric field was investigated with Garfield toolkit, the results showed that the ratio of the electric field of the collect region to the drift region (Ec /Ed ) must be greater than a critical value Z (1.78). An individual experiment, carried out with a compound alpha source (241Am and 243Am), was used to validate the preliminary performance of this detector. The effects of the electric field on the anode pulse height agreed well with the simulation results. Furthermore, the results also indicated that the energy resolution of (68.40 ± 1.07) keV at 5.39 MeV (243Am) and (69.67 ± 1.09) keV at 5.49 MeV (241Am) could be achieved. An initial in-beam fission experiment of 235U reaction with 14 MeV neutrons was also performed to test the setup, and the results showed that the reconstructed emission angle could achieve a resolution of 0.221 ± 0.002 on the difference of the cosines determined from both halves of TFGIC. The present work primarily reported the development of a TFGIC with a digital acquisition system in INPC.
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Calviani, M., P. Cennini, D. Karadimos, V. Ketlerov, V. Konovalov, W. Furman, A. Goverdowski, V. Vlachoudis et L. Zanini. « A fast ionization chamber for fission cross-section measurements at n_TOF ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 594, no 2 (septembre 2008) : 220–27. http://dx.doi.org/10.1016/j.nima.2008.06.006.

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Meierbachtol, K., F. Tovesson, C. W. Arnold, A. B. Laptev, T. A. Bredeweg, M. Jandel, R. O. Nelson et M. C. White. « Development of an Ionization Chamber for the SPIDER Fission Fragment Detector ». Nuclear Data Sheets 119 (mai 2014) : 389–91. http://dx.doi.org/10.1016/j.nds.2014.08.108.

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Göök, Alf, Franz-Josef Hambsch et Stephan Oberstedt. « Prompt fission neutron emission in the reaction 235U(n,f) ». EPJ Web of Conferences 169 (2018) : 00004. http://dx.doi.org/10.1051/epjconf/201816900004.

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Experimental activities at JRC-Geel on prompt fission neutron (PFN) emission in response to OECD/NEA nuclear data requests are presented in this contribution. Specifically, on-going investigations of PFN emission from the reaction 235U(n,f) in the region of the resolved resonances, taking place at the GELINA facility, are presented. The focus of this contribution lies on studies of PFN correlations with fission fragment properties. The experiment employs a scintillation detector array for neutron detection, while fission fragment properties are determined via the double kinetic energy technique using a position sensitive twin ionization chamber. This setup allows us to study several correlations between properties of neutron and fission fragments simultaneously. Results on PFN correlations with fission fragment properties from the present study differ significantly from earlier studies on this reaction, induced by thermal neutrons.
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Wen, J., Y. Yang, Z. Wen, X. Liu, R. Liu, Z. Han, M. Wang et L. Zheng. « A multi-layered fast ionization chamber prototype for fission cross section measurements ». Journal of Instrumentation 13, no 07 (24 juillet 2018) : P07020. http://dx.doi.org/10.1088/1748-0221/13/07/p07020.

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Simon, G., J. Trochon, F. Brisard et C. Signarbieux. « Pulse height defect in an ionization chamber investigated by cold fission measurements ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 286, no 1-2 (janvier 1990) : 220–29. http://dx.doi.org/10.1016/0168-9002(90)90224-t.

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Ambrožič, Klemen, Klaudia Malik, Barkara Obryk et Luka Snoj. « JSI TRIGA neutron and gamma field characterization by TLD measurements ». EPJ Web of Conferences 225 (2020) : 04034. http://dx.doi.org/10.1051/epjconf/202022504034.

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A well characterized radiation field inside a research nuclear reactor irradiation facilities enables precise qualification of radiation effects to the irradiated samples such as nuclear heating or changes in their electrical or material properties. To support the increased utilization of the JSI TRIGA reactor irradiation facilities in the past few years mainly on account of testing novel detector designs, electronic components and material samples, we are working on increasing the neutron and gamma field characterization accuracy using various modeling and measurement techniques. In this paper we present the dose field measurements using thermo-luminescent detectors (TLD’s) with different sensitivities neutron and gamma sensitivities, along with multiple ionization and fission chamber. Experiment was performed in several steps from reactor start-up, steady operation and a rapid shutdown, during which the ionization and fission chamber signals were acquires continuously, while the TLD’s were being irradiated at different stages during reactor operation and after shutdown, to also capture response to delayed neutron and gamma field. The results presented in this paper serve for validation of JSI designed JSIR2S code for delayed radiation field determination, initial results of its application on the JSI TRIGA TLD measurements will also be presented.
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Khryachkov, Vitaly, Andrei Goverdovskii, Vladimir Ketlerov, Vecheslav Mitrofanov et Alexei Sergachev. « Investigation of the heavy nuclei fission with anomalously high values of the fission fragments total kinetic energy ». EPJ Web of Conferences 169 (2018) : 00011. http://dx.doi.org/10.1051/epjconf/201816900011.

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Binary fission of 232Th and 238U induced by fast neutrons were under intent investigation in the IPPE during recent years. These measurements were performed with a twin ionization chamber with Frisch grids. Signals from the detector were digitized for further processing with a specially developed software. It results in information of kinetic energies, masses, directions and Bragg curves of registered fission fragments. Total statistics of a few million fission events were collected during each experiment. It was discovered that for several combinations of fission fragment masses their total kinetic energy was very close to total free energy of the fissioning system. The probability of such fission events for the fast neutron induced fission was found to be much higher than for spontaneous fission of 252Cf and thermal neutron induced fission of 235U. For experiments with 238U target the energy of incident neutrons were 5 MeV and 6.5 MeV. Close analysis of dependence of fission fragment distribution on compound nucleus excitation energy gave us some explanation of the phenomenon. It could be a process in highly excited compound nucleus which leads the fissioning system from the scission point into the fusion valley with high probability.
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31

Almaraz-Calderon, Sergio, K. Ernst Rehm, Benjamin W. Asher, Melina L. Avila, Kalle Auranen, Birger B. Back, Jie Chen et al. « Fusion-induced fission measurements with the MUSIC active target detector ». EPJ Web of Conferences 242 (2020) : 01005. http://dx.doi.org/10.1051/epjconf/202024201005.

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The rapid neutron capture process (r-process) is believed to be responsible for about half of the production of the elements heavier than iron and it may also contribute to abundances of some lighter nuclides. Great excitement was recently generated by evidence for r-process nucleosynthesis in binary neutron star mergers via multi-wavelength observations of kilonova emission and gravitational waves. In order to interpret the observations and validate theoretical predictions, an understanding of the fission process, in particular of the evolution of fission barrier heights, is needed. An experimental study of fusioninduced fission cross sections using active-target detectors is a promising idea since the fission excitation function can be studied with a single beam energy. The Multi-Sampling Ionization Chamber (MUSIC) is an active-target detector in which a gas serves as both, counting gas and target nuclei. A proof-of principle experiment to explore the ability to identify fission events with MUSIC was recently performed at Argonne National Laboratory. In this work, ideas, results and perspectives will be discussed.
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32

Karadimos, D., et Et al. « 234U(n,f) cross section with the FIC detector at CERN (n TOF) ». HNPS Proceedings 16 (1 janvier 2020) : 175. http://dx.doi.org/10.12681/hnps.2596.

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The analysis technique applied to the data and the reaction cross section 234U(n,f) from the FIC (Fission Ionization Chamber) detector at the n TOF facility is pre- sented here. A comparison of the measured neutron induced fission cross section of 234U nucleus is given with the available data from the bibliography. The measure- ments took place at the installation of CERN in Geneva. The detector was placed in front of the neutron beam for the determination of the neutron induced fission cross section of various isotopes of the Th cycle. For the data acquisition, several flash Analog to Digital Converter (fADC) channels were used. This facilitated the detailed off-line analysis of data since all information was stored in the computer. The automation of the process was required because the high amount of stored data. The data analysis aimed at the discrimination of fission events. For this end we had to deal with three main issues: i) The subtraction of the background, ii) the fitting of the pulses and iii) the automation of the process.
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33

Tutin, G. A., I. V. Ryzhov, V. P. Eismont, A. V. Kireev, H. Condé, K. Elmgren, N. Olsson et P. U. Renberg. « An ionization chamber with Frisch grids for studies of high-energy neutron-induced fission ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 457, no 3 (janvier 2001) : 646–52. http://dx.doi.org/10.1016/s0168-9002(00)00775-0.

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Göök, A., W. Geerts, F. J. Hambsch, S. Oberstedt, M. Vidali et Sh Zeynalov. « A position-sensitive twin ionization chamber for fission fragment and prompt neutron correlation experiments ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 830 (septembre 2016) : 366–74. http://dx.doi.org/10.1016/j.nima.2016.06.002.

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Bocquet, J. P., R. Brissot et H. R. Faust. « A large ionization chamber for fission fragment nuclear charge identification at the LOHENGRIN spectrometer ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 267, no 2-3 (mai 1988) : 466–72. http://dx.doi.org/10.1016/0168-9002(88)90487-1.

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Göök, Alf, Franz-Josef Hambsch et Stephan Oberstedt. « Neutron Multiplicity Correlations with Fission Fragment Mass and Energy from 239Pu(n,f) ». EPJ Web of Conferences 239 (2020) : 05009. http://dx.doi.org/10.1051/epjconf/202023905009.

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There exists experimental evidence for strong fluctuations of the average neutron multiplicity from resonance to resonance in 239Pu(n,f). These fluctuations have been shown to impact nuclear reactor benchmarks by reducing the criticality. The fluctuating neutron multiplicity can be explained as a consequence of the competition between direct fission and the (n,γf) process. However, there is also evidence for fluctuations of the fission fragment mass yields from resonance to resonance. The mass yield fluctuations may also contribute to fluctuations of the neutron multiplicity averaged over all fission fragment masses. In order to model the contribution to the neutron multiplicity fluctuations by the fission fragment mass yield fluctuations new data on the correlations between fission fragment properties and neutron multiplicities are in need. We present experiments carried out to determine prompt neutron multiplicity correlations with fission fragment masses and total kinetic energies in the reaction 239Pu(n,f). The experiment has been performed at the GELINA facility at JRC-Geel. A twin position-sensitive Frisch-grid ionization chamber is used for fission fragment identification via the double kinetic energy technique. An array of scintillation detectors is employed for neutron counting. Correlations between average neutron multiplicities and fission fragment properties have been measured with improved resolution in both mass and TKE, compared to data from the literature.
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37

Wang, Xianglei. « A finite element simulation of transition-edge sensor for measuring kinetic energy of fission fragments ». EPJ Web of Conferences 239 (2020) : 17022. http://dx.doi.org/10.1051/epjconf/202023917022.

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It is necessary to accurately measure the kinetic energy of fission fragments when using the Time-Of-Flight method to determine the mass of fission fragments. The ionization chamber and the Au-Si surface barrier detector are conventional kinetic-energy detectors, but their energy resolution is not sufficient to achieve a mass resolution of 1 amu. The Transition-Edge Sensor (TES) is a cryogenic calorimeter that can be used to measure the kinetic energy by measuring the temperature variation induced by the energy of the incident particle, with a typical resolution of 0.02% of TES detector can be achieved[1]. In this article, we designed a TES to measure the kinetic energy of fission fragments, and the signals of this TES with different incident particle positions, kinetic energy, and thermal conductivity were simulated using ANSYS. Therefore, we verified the feasibility of the TES and improved the count rate of the TES to 100cps.
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38

Heeg, P., J. Pannicke, M. Mutterer, P. Schall, J. P. Theobald, K. Weingärtner, K. F. Hoffmann et al. « The double-torus ionization chamber diogenes for the investigation of charged particle associated nuclear fission ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 278, no 2 (juin 1989) : 452–66. http://dx.doi.org/10.1016/0168-9002(89)90865-6.

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Al-Adili, Ali, Kaj Jansson, Diego Tarrío, Franz-Josef Hambsch, Alf Göök, Stephan Oberstedt, Marc Olivier Frégeau et al. « Studying fission neutrons with 2E-2v and 2E ». EPJ Web of Conferences 169 (2018) : 00002. http://dx.doi.org/10.1051/epjconf/201816900002.

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This work aims at measuring prompt-fission neutrons at different excitation energies of the nucleus. Two independent techniques, the 2E-2v and the 2E techniques, are used to map the characteristics of the mass-dependent prompt fission neutron multiplicity, v(A), when the excitation energy is increased. The VERDI 2E-2v spectrometer is being developed at JRC-GEEL. The Fission Fragment (FF) energies are measured using two arrays of 16 silicon (Si) detectors each. The FFs velocities are obtained by time-of-flight, measured between micro-channel plates (MCP) and Si detectors. With MCPs placed on both sides of the fission source, VERDI allows for independent timing measurements for both fragments. 252Cf(sf) was measured and the present results revealed particular features of the 2E-2v technique. Dedicated simulations were also performed using the GEF code to study important aspects of the 2E-2v technique. Our simulations show that prompt neutron emission has a non-negligible impact on the deduced fragment data and affects also the shape of v(A). Geometrical constraints lead to a total-kinetic energy-dependent detection efficiency. The 2E technique utilizes an ionization chamber together with two liquid scintillator detectors. Two measurements have been performed, one of 252Cf(sf) and another one of thermal-neutron induced fission in 235U(n,f). Results from 252Cf(sf) are reported here.
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40

Dieu Hien, Le Thi, A. A. Khrutchinsky et S. A. Kuten. « MODELING OF CHARGE TRANSPORT IN THE ACTIVE VOLUME OF THE IONIZATION FISSION CHAMBER IN CURRENT MODE ». Proceedings of the National Academy of Sciences of Belarus. Physics and Mathematics Series 54, no 1 (5 avril 2018) : 97–109. http://dx.doi.org/10.29235/1561-2430-2018-54-1-97-109.

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41

Chen, H. F., P. Zheng, X. J. Sun, J. Xiao, T. H. Zhu, J. J. Sun, J. Y. Zhu, Z. H. Li, Y. Cao et J. Yan. « Characterize the grid inefficiency correction of Frisch grid ionization chamber with Garfield and SRIM ». Journal of Instrumentation 17, no 03 (1 mars 2022) : P03023. http://dx.doi.org/10.1088/1748-0221/17/03/p03023.

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Abstract Grid inefficiency (GI) correction is critically important to accurately determine the energy and emission angle of charged particles in Frisch grid ionization chambers (FGIC). Presently, three correction methods have been proposed in the literature. All these three methods rely strongly on the accurate and stable calibration between two different electrical chain gains in experiments. To avoid these challenges, they are firstly investigated with Monte Carlo method by using Garfield and SRIM toolkit. Two types of grid wire (diameter 90 and 180 μm) were simulated to investigate the impacts of GI correction on energy correction, and ten different emission angles were adopted to estimate the effects of these correction methods on the angle reconstruction. The simulation results clearly distinguished the differences among these correction methods in energy determination. The correlation analysis (R = 0.99) among these different correction methods indicated that the impact of either correction approach is small on the determination of emission angle. The present work firstly investigates the effects of GI correction on emission angle with Monte Carlo methods, which is the basis of future work to measure the total kinetic energy and mass distribution of Fission Fragment (FF).
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42

Chuklyaev, S. V., et Yu N. Pepelyshev. « KNK-21A fission ionization chamber for measuring the flux and temperature of thermal neutrons in pulsed sources ». Atomic Energy 76, no 6 (juin 1994) : 463–67. http://dx.doi.org/10.1007/bf02408112.

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Glazyuk, Yakov Vadimovich, Vladimir Petrovich Alferov, Boris Semenovich Salamaha et Ilya Gennadyevich Veselov. « On the Contribution of the Additional Component of the Ionization Current to the Formation of the Output Pulse of the Ionization Fission Chamber ». Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2022, no 4 (décembre 2022) : 102–11. http://dx.doi.org/10.26583/npe.2022.4.09.

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44

Gunsing, F., F. Belloni, E. Berthoumieux, M. Diakaki, E. Dupont et E. Ferrer-Ribas. « MicroMegas-based detectors for time-of-flight measurements of neutron-induced reactions ». EPJ Web of Conferences 239 (2020) : 17007. http://dx.doi.org/10.1051/epjconf/202023917007.

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MicroMegas detectors are versatile gaseous detectors which are used for ionizing particle detection. A MicroMegas detector consists of two adjacent gas-filled volumes. One volume acts as a drift region with an electric field operating in the ionization chamber regime, the second volume is the amplification region acting as a parallel-plate avalanche counter. The use of the microbulk technique allows the production of thin, radiation resistant, and low-mass detector with a highly variable gain. Such MicroMegas detectors have been developed and used in combination with neutron time-of-flight measurements for in-beam neutron-flux monitoring, fission and light-charged particle reaction cross section measurements, and for neutron-beam imaging. An overview of MicroMegas detectors for neutron detection and neutron reaction cross section measurements and related results and developments will be presented.
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45

Gaudefroy, L., T. Roger, J. Pancin, C. Spitaels, J. Aupiais et J. Mottier. « A twin Frisch-grid ionization chamber as a selective detector for the delayed gamma-spectroscopy of fission fragments ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 855 (mai 2017) : 133–39. http://dx.doi.org/10.1016/j.nima.2017.02.071.

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46

Chatel, Carole, Ludovic Mathieu, Mourad Aïche, Maria Diakaki, Gilles Noguere et Olivier Bouland. « Towards the experimental validation of a small Time-Projection-Chamber for the quasi-absolute measurement of the fission cross section ». EPJ Web of Conferences 253 (2021) : 11013. http://dx.doi.org/10.1051/epjconf/202125311013.

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To accurately measure neutron-induced fission cross sections, to characterize neutron-beam lines or to make dosimetric investigations, it is necessary to have high accuracy measurements of neutron fluence. It is possible to perform independent and precise neutron flux measurements with respect to the 1H(n,n)p elastic scattering cross section. The use of a silicon detector is recommended from 1 to 70 MeV neutron energy. However, it has been observed that a high electrons background forbids its use below 1 MeV. Hence, a new gaseous proton-recoil telescope is developed and characterized to overcome this limit. It should provide quasi-absolute neutron flux measurements with an accuracy around 3% and is not sensible to gamma and electrons background. It consists in two ionization chambers read by a segmented micromegas technology detection plane. The gas pressure inside is adjustable to the proton range in the detector and therefore to the neutron energy. This detector is described in details below and the newest results of its characterization are presented. A special attention is paid to detection efficiency measurements.
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47

Pakari, O., V. Lamirand, G. Perret, L. Braun, P. Frajtag et A. Pautz. « Current Mode Neutron Noise Measurements in the Zero Power Reactor CROCUS ». EPJ Web of Conferences 170 (2018) : 04017. http://dx.doi.org/10.1051/epjconf/201817004017.

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The present article is an overview of developments and results regarding neutron noise measurements in current mode at the CROCUS zero power facility. Neutron noise measurements offer a non-invasive method to determine kinetic reactor parameters such as the prompt decay constant at criticality α = βeff / λ, the effective delayed neutron fraction βeff, and the mean generation time λ for code validation efforts. At higher detection rates, i.e. above 2×104 cps in the used configuration at 0.1 W, the previously employed pulse charge amplification electronics with BF3 detectors yielded erroneous results due to dead time effects. Future experimental needs call for higher sensitivity in detectors, higher detection rates or higher reactor powers, and thus a generally more versatile measurement system. We, therefore, explored detectors operated with current mode acquisition electronics to accommodate the need. We approached the matter in two ways: 1) By using the two compensated 10B-coated ionization chambers available in CROCUS as operational monitors. The compensated current signal of these chambers was extracted from coremonitoring output channels. 2) By developing a new current mode amplification station to be used with other available detectors in core. Characteristics and first noise measurements of the new current system are presented. We implemented post-processing of the current signals from 1)and 2) with the APSD/CPSD method to determine α. At two critical states (0.5 and 1.5 W), using the 10B ionization chambers and their CPSD estimate, the prompt decay constant was measured after 1.5 hours to be α=(156.9 ± 4.3) s-1 (1σ). This result is within 1σ of statistical uncertainties of previous experiments and MCNPv5-1.6 predictions using the ENDF/B-7.1 library. The newsystem connected to a CFUL01 fission chamber using the APSDestimate at 100 mW after 33 min yielded α = (160.8 ± 6.3) s-1, also within 1σ agreement. The improvements to previous neutron noise measurementsinclude shorter measurement durations that can achievecomparable statistical uncertainties and measurements at higherdetection rates.
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Vorobev, V. A., S. Yu Obudovskii et Yu A. Kashchuk. « The method for determining the charge collection time and the mean charge in the pulse of the ionization fission chamber ». Izmeritel`naya Tekhnika, no 2 (2019) : 60–64. http://dx.doi.org/10.32446/0368-1025it.2019-2-60-64.

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Vorobev, V., S. Obudovskii et Y. Kashchuk. « The method for determining the charge collection time and the mean charge in the pulse of the ionization fission chamber ». Izmeritel`naya Tekhnika, no 2 (2019) : 60–64. http://dx.doi.org/10.32446/0368-1052it.2019-2-60-64.

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Ryzhov, I. V., G. A. Tutin, A. G. Mitryukhin, V. S. Oplavin, S. M. Soloviev, J. Blomgren, P. U. Renberg et al. « Measurements of neutron-induced fission cross-sections of 205Tl, 204,206,207,208Pb and 209Bi with a multi-section Frisch-gridded ionization chamber ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 562, no 1 (juin 2006) : 439–48. http://dx.doi.org/10.1016/j.nima.2006.03.021.

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