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Measurement of the 244Cm and 246Cm neutron-induced capture cross sections at the n_TOF facility V. Alcayne1, A. Kimura2, E. Mendoza1, D. Cano-Ott1, T. Martínez1, O. Aberle3, J. Andrzejewski4, L. Audouin5, V. Bécares1, M. Bacak3,6,7, M. Barbagallo3,8, F. Beˇ cvᡠr9, G. Bellia10,11, E. Berthoumieux7, J. Billowes12, D. Bosnar13, A. Brown14, M. Busso8,15,16, M. Caamaño17, L. Caballero-Ontanaya18, F. Calviño19, M. Calviani3, A. Casanovas19, F. Cerutti3, Y. H. Chen5, E. Chiaveri3,12,20, N. Colonna8, G. Cortés19, M. A. Cortés-Giraldo20, L. Cosentino10, S. Cristallo8,15,21, L. A. Damone8,22, M. Diakaki23,3, M. Dietz24, C. DomingoPardo18, R. Dressler25, E. Dupont7, I. Durán17, Z. Eleme26, B. Fernández-Domínguez17, A. Ferrari3, P. Finocchiaro10, V. Furman27, K. Göbel28, A. Gawlik4, S. Gilardoni3, T. Glodariu29, I. F. Gonçalves30, E. González-Romero1, C. Guerrero20, F. Gunsing7, H. Harada2, S. Heinitz25, J. Heyse31, D. G. Jenkins14, F. Käppeler32, Y. Kadi3, T. Katabuchi33, N. Kivel25, I. Knapova9, M. Kokkoris23, Y. Kopatch27, M. Krtiˇ cka9, D. Kurtulgil28, I. Ladarescu18, C. Lederer-Woods24, J. Lerendegui-Marco20, S. Lo Meo34,35, S. J. Lonsdale24, D. Macina3, A. Manna35,36, A. Masi3, C. Massimi35,36, P. Mastinu37, M. Mastromarco3, F. Matteucci38,39, E. A. Maugeri25, A. Mazzone8,40, A. Mengoni34, V. Michalopoulou23, P. M. Milazzo38, F. Mingrone3, A. Musumarra10,11, A. Negret29, R. Nolte41, F. Ogállar42, A. Oprea29, N. Patronis26, A. Pavlik43, J. Perkowski4, L. Persanti8,15,21, I. Porras42, J. Praena42, J. M. Quesada20, D. Radeck41, D. Ramos-Doval5, T. Rauscher44,45, R. Reifarth28, D. Rochman25, M. Sabaté-Gilarte3,20, A. Saxena46, P. Schillebeeckx31, D. Schumann25, S. Simone10, A. G. Smith12, N. V. Sosnin12, A. Stamatopoulos23, G. Tagliente8, J. L. Tain18, T. Talip25, A. Tarifeño-Saldivia19, L. Tassan-Got3,23,5, A. Tsinganis3, J. Ulrich25, S. Urlass3,47, S. Valenta9, G. Vannini35,36, V. Variale8, P. Vaz30, A. Ventura35, D. Vescovi8,15, V. Vlachoudis3, R. Vlastou23, A. Wallner48, P. J. Woods24, T. Wright12, and P. Žugec13 1Centro de Investigaciones Energéticas Medioambientales y Tecnológicas (CIEMAT), Spain 2Japan Atomic Energy Agency (JAEA), Tokai-mura, Japan 3European Organization for Nuclear Research (CERN), Switzerland 4University of Lodz, Poland 5Institut de Physique Nucléaire, CNRS-IN2P3, Univ. Paris-Sud, Université Paris-Saclay, F-91406 Orsay Cedex, France 6Technische Universität Wien, Austria 7CEA Irfu, Université Paris-Saclay, F-91191 Gif-sur-Yvette, France 8Istituto Nazionale di Fisica Nucleare, Sezione di Bari, Italy 9Charles University, Prague, Czech Republic 10INFN Laboratori Nazionali del Sud, Catania, Italy 11Dipartimento di Fisica e Astronomia, Università di Catania, Italy 12University of Manchester, United Kingdom 13Department of Physics, Faculty of Science, University of Zagreb, Zagreb, Croatia 14University of York, United Kingdom 15Istituto Nazionale di Fisica Nucleare, Sezione di Perugia, Italy 16Dipartimento di Fisica e Geologia, Università di Perugia, Italy 17University of Santiago de Compostela, Spain 18Instituto de Física Corpuscular, CSIC - Universidad de Valencia, Spain ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 © The Authors, published by EDP Sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0/).
19Universitat Politècnica de Catalunya, Spain 20Universidad de Sevilla, Spain 21Istituto Nazionale di Astrofisica - Osservatorio Astronomico di Teramo, Italy 22Dipartimento di Fisica, Università degli Studi di Bari, Italy 23National Technical University of Athens, Greece 24School of Physics and Astronomy, University of Edinburgh, United Kingdom 25Paul Scherrer Institut (PSI), Villingen, Switzerland 26University of Ioannina, Greece 27Joint Institute for Nuclear Research (JINR), Dubna, Russia 28Goethe University Frankfurt, Germany 29Horia Hulubei National Institute of Physics and Nuclear Engineering, Romania 30Instituto Superior Técnico, Lisbon, Portugal 31European Commission, Joint Research Centre, Geel, Retieseweg 111, B-2440 Geel, Belgium 32Karlsruhe Institute of Technology, Campus North, IKP, 76021 Karlsruhe, Germany 33Tokyo Institute of Technology, Japan 34Agenzia nazionale per le nuove tecnologie (ENEA), Bologna, Italy 35Istituto Nazionale di Fisica Nucleare, Sezione di Bologna, Italy 36Dipartimento di Fisica e Astronomia, Università di Bologna, Italy 37Istituto Nazionale di Fisica Nucleare, Sezione di Legnaro, Italy 38Istituto Nazionale di Fisica Nucleare, Sezione di Trieste, Italy 39Dipartimento di Astronomia, Università di Trieste, Italy 40Consiglio Nazionale delle Ricerche, Bari, Italy 41Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100, 38116 Braunschweig, Germany 42University of Granada, Spain 43University of Vienna, Faculty of Physics, Vienna, Austria 44Department of Physics, University of Basel, Switzerland 45Centre for Astrophysics Research, University of Hertfordshire, United Kingdom 46Bhabha Atomic Research Centre (BARC), India 47Helmholtz-Zentrum Dresden-Rossendorf, Germany 48Australian National University, Canberra, Australia Abstract. The neutron capture reactions of the 244Cm and 246Cm isotopes open the path for the formation of heavier Cm isotopes and heavier elements such as Bk and Cf in a nuclear reactor. In addition, both isotopes belong to the minor actinides with a large contribution to the decay heat and to the neutron emission in irradiated fuels. There are only two previous 244Cm and 246Cm capture cross section measurements: one in 1969 using a nuclear explosion [1] and the most recent data measured at J-PARC in 2010 [2]. The data for both isotopes are very scarce due to the difficulties in performing the measurements: high intrinsic activity of the samples and limited facilities capable of providing isotopically enriched samples. We have measured both neutron capture cross sections at the n_TOF Experimental Area 2 (EAR-2) with three C6D6detectors and also at Area 1 (EAR-1) with the TAC. Preliminary results assessing the quality and limitations (background subtraction, measurement technique and counting statistics) of this new experimental datasets are presented and discussed. 1 Introduction Accurate neutron capture cross section data for minor actinides (MAs) are required to estimate the production and transmutation rates of MAs in light-water reactors (LWR) with a high burnup, critical fast reactors like Gen-IV systems and other innovative devices such as ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 2
accelerator driven systems (ADS) [3]. The 244Cm (T1/2=18.1 years) and 246Cm (T1/2=4730 years) isotopes are among the most important MAs due to the difficulties in their transmutation and their contribution to the radiotoxicity of the irradiated nuclear fuels. In particular, even after three years of cooling, 244Cm shares nearly 50% of the total actinide decay heat in irradiated reactor fuels with a high burnup. In addition, both of them are in the path of the creation of any heavier Cm isotopes and heavier elements like Bk and Cf. Only two previous capture measurements were done before the n_TOF measurements. The first one, done in 1969 [1], used the neutrons produced in an under-ground nuclear explosion. The 244Cm (n,γ) cross section was measured in a range from 20 eV to 1 keV and for the 246Cm(n,γ) from 20 eV to 400 eV. The second capture measurement was performed in 2010 with a large coverage Ge-array in the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at J-PARC [2]. In this second measurement the data obtained for both isotopes range from 2 eV to 300 eV. The resonance analysis was done up to 30 eV. The scarcity of the available data and the many experimental challenges involved in the two previous measurements motivated an additional measurement under different conditions, i.e., in a different facility, with different detectors and monitors and with a different methodology. 2 Experiment The same samples used at J-PARC have been measured at n_TOF. In this facility, the neutron beam is generated through spallation of 20 GeV/c protons, which are extracted in pulses from the CERN Proton Synchrotron and impinging on a lead target. The pulses have a nominal intensity of 7×1012 protons and a time spread of 7 ns (rms). The neutrons travel along two beam lines towards the two experimental areas along : EAR-1 flight length of 185 m [4] (horizontal) and EAR-2 flight length of 19 m [5] (vertical). The neutron flux is larger in the EAR-2 and the energy resolution is better in the EAR-1. The samples have been measured in both experimental areas. The measurement in EAR-2 has been done with three C6D6detectors and the Total Energy Detection (TED) [6] technique, and the measurement in EAR-1 with the n_TOF Total Absorption Calorimeter (TAC) [7], designed to detect the complete γ-ray cascade. Measuring in both experimental areas with different detectors and techniques will allow to crosscheck results and, presumably, to reduce the final uncertainties. The targets used for the experiment consist in two samples of 244Cm and one of 246Cm. There were 0.4 mg of 244Cm in each of the 244Cm samples and 1.1 mg of 246Cm in the 246Cm sample. The isotopic abundances of the different actinides are presented in Table 1. Table 1. Isotopic composition (% atoms) of the 244Cm and 246Cm samples. 244Cm sample 246Cm sample 244Cm 60.3±1.1 20.3±0.5 245Cm 2.4±0.3 1.1±0.3 246Cm 6.3±0.6 57.7±1.5 247Cm - 2.8±0.4 248Cm - 8.8±0.2 240Pu 31.0±0.6 9.3±0.2 2.1 Measurement at the EAR-2 The three C6D6detectors were placed at 5 cm from the sample and perpendicular to the beam. In addition, three additional detectors were used for monitoring the beam. Two of ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 3
them measured the intensity of the proton beam. The third one was the SiMon [8], an array of four silicon detectors facing a thin enriched lithium fluoride foil, for monitoring the neutron beam. To obtain accurate weighting functions required for the PHWT [9] technique, a very detailed description of the experimental set-up has been implemented in the Geant4 toolkit [10]. The simulated response functions have been validated with experimental data obtained with several calibration sources ( 133Ba, 137Cs, 60Co, 88Y, AmBe and CmC). The geometry implemented in Geant4 and one of the simulated response functions are shown in Figure 1. The data obtained at n_TOF are processed with the Pulse Shape Analysis (PSA) routine [11]. (MeV) dep E 0 0.2 0.4 0.6 0.8 1 1.2 1.4 1.6 1.8 2 counts/second/BinWidth 1000 2000 3000 4000 5000 6000 MC Exp-Background Figure 1. Geometry of the EAR-2 setup as implemented in Geant4 (left). Comparison between simulated (MC) and experimental response function to an 88Y source (right). The results of the fits are stored in ROOT files [12]: signal amplitudes, signal areas, times, etc.. Also the conversion from time-of-flight to neutron energy is done. Accurate amplitude-to-energy calibrations and gain stability checks were performed on a weekly basis for the three C6D6detectors using 133Ba, 137Cs, 60Co, 88Y, AmBe and CmC calibration sources. Small gain shifts ( 8%) are observed and corrected as a function of time. The total number of counts as a function of neutron energy measured with the Cm samples in place are shown in Figure 2. Also shown are the estimated total background, the beam related background, and the no-beam related background. These backgrounds have been obtained from dedicated measurements. A preliminary but rather complete analysis of the data measured at the EAR-2 has been performed and two preliminary capture yields (no background subtracted) have been obtained, one for the 244Cm samples and the other for the 246Cm sample. Both yields (no background subtracted) are presented in Figure 3 together with the yields obtained from the JEFF-3.3 [13] cross sections with the experimental background and the characteristics of the EAR-2 neutron beam (neutron flux +resolution function)[14]. The relative differences between the experimental and the evaluated yields (in %) are shown at the bottom of each panel, integrated for each resonance. The results have been normalized to the first large resonance of 240Pu at 1 eV. ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 4
Neutron energy(eV) 2− 10 1− 10 1 10 2 10 Counts 4 10 5 10 Cm sample 244 Beam bkg. No beam bkg. Total bkg. Neutron energy(eV) 2− 10 1− 10 1 10 2 10 Counts 4 10 5 10 Cm sample 246 Beam bkg. No beam bkg. Total bkg. Figure 2. Total number of counts (750 bins per decade) and estimated backgrounds registered in the 244Cm (left) and 246Cm (right) EAR-2 measurements. ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 5
(eV) n E 1 2 3 4 5 6 7 8 9 10 Capture Yield + bkg 0.05 0.1 0.15 0.2 0.25 0.3 0.35 Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm - 1000 bins per decade 244 1 2 3 4 5 6 7 8 9 10 2− 1.5− 1− 0.5− 0 0.5 1 1.5 2 (eV) n E 1 2 3 4 5 6 7 8 9 10 Capture Yield + bkg 0.02 0.04 0.06 0.08 0.1 0.12 0.14 0.16 0.18 0.2 Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm-245 (n,f) Cm-247 (n,f) )γCm-248 (n, )γAm-243 (n, Cm sample - 1000 bins per decade 246 1 2 3 4 5 6 7 8 9 10 15− 10− 5− 0 5 10 15 (eV) n E 10 20 30 40 50 60 70 Capture Yield + bkg 14 16 18 20 22 24 26 28 3− 10× Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm - 1000 bins per decade 244 10 20 30 40 50 60 70 50− 40− 30− 20− 10− 0 10 20 30 40 50 (eV) n E 10 20 30 40 50 60 70 Capture Yield + bkg 12 14 16 18 20 3− 10× Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm-245 (n,f) Cm-247 (n,f) )γCm-248 (n, )γAm-243 (n, Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm-245 (n,f) Cm-247 (n,f) )γCm-248 (n, )γAm-243 (n, Cm sample - 1000 bins per decade 246 10 20 30 40 50 60 70 15− 10− 5− 0 5 10 15 (eV) n E 80 100 120 140 160 180 200 Capture Yield + bkg 11 12 13 14 15 16 17 18 19 20 3− 10× Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm - 750 bins per decade 244 80 100 120 140 160 180 200 60− 40− 20− 0 20 40 60 (eV) n E 80 100 120 140 160 180 200 Capture Yield + bkg 10 12 14 16 18 3− 10× Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm-245 (n,f) Cm-247 (n,f) )γCm-248 (n, )γAm-243 (n, Experimental Yield Total Sammy Yield )γPu-240 (n, )γCm-244 (n, )γCm-246 (n, Cm-244 (n,f) Cm-245 (n,f) Cm-247 (n,f) )γCm-248 (n, )γAm-243 (n, Cm sample - 750 bins per decade 246 80 100 120 140 160 180 200 60− 40− 20− 0 20 40 60 Figure 3. Preliminary experimental yields (no background subtracted) of the measured 244Cm (left) and 246Cm (right) samples. Together with the experimental data points, we show an estimation of the contribution of the capture and fission reactions in each isotope present in the samples. These contributions have been obtained using the SAMMY computer code to calculate the reaction yields taking into account the experimental conditions such as Doppler and resolution broadening, and taking the reaction cross sections from JEFF-3.3. The resulting yields were then normalized to fit the experimental results and added to the background, obtained from dedicated measurements. ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 6
2.2 Measurement at the EAR-1 The measurement in EAR-1 was performed with the TAC, which is an array of 40 BaF2 crystals designed to detect the full capture γ-ray cascades. The data analysis is ongoing and it will follow similar procedures than the ones performed in previous TAC experiments [15] [16]. Signals are grouped into TAC events with a 20 ns coincidence window, and cuts in total deposited energy and detection multiplicity allow to improve the signal to background ratio. The total number of counts as a function of neutron energy measured with the 244Cm samples in place are shown in Figure 4, together with the estimated backgrounds. The better energy resolution and smaller instantaneous neutron fluence in EAR-1 results in a narrower resonant structure and a larger contribution of the no-beam related background. Neutron energy(eV) 1 10 2 10 Counts 2 10 3 10 4 10 Cm sample 244 Beam bkg. No beam bkg. Total bkg. Figure 4. Total number of counts (1000 bins per decade) and estimated backgrounds registered in the 244Cm EAR-1 measurement. 3 Conclusions The capture cross sections of 244Cm and 246Cm are required to estimate the production and transmutation rates of MAs in LWR and also for new reactor types. There are only two previous capture measurements of these two isotopes, both of them with many experimental difficulties.Therefore, a new measurement has been performed at n_TOF using the two experimental areas and preliminary capture yields have been obtained. References [1] M. S. Moore et. al., Phys. Rev. C, 3, 1656 (1971) [2] A. Kimura et. al., Jour. Nucl. Sc. Tech. 49, 708 (2012) [3] G. Aliberti et. al., , Ann. Nucl. Ener. 33, 700 (2006) [4] C. Guerrero et al., Eur. Phys. J. A 49, 27 (2013) [5] C. Weiss et al., Nucl. Instrum. Meth. A 799, 90 (2015) [6] R.L. Macklin and J.H. Gibbons,Phys. Rev. 159, 1007 (1967) [7] C.Guerrero et al., Nucl. Instrum. Meth. A 608, 424 (2009) [8] S. Marrone et al., Nucl. Instrum. Meth. A 517, 389 (2004) ,(201 E Web of Conferences https://doi.org/10.1051/e onf /20192 PJ pjc 9) 211 000811030 WONDER-2018 30 8 7
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