Energy deposition for 10 MeV neutrons in oxygen, carbon, argon and hydrogen gaseous chambers (1mx1mx1m). Energy Deposition in 90% argon (1.782mg/cm 3 )

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Presentation transcript:

Energy deposition for 10 MeV neutrons in oxygen, carbon, argon and hydrogen gaseous chambers (1mx1mx1m). Energy Deposition in 90% argon (1.782mg/cm 3 ) and 10% CH 4 (0.1782mg/cm 3 ) gaseous chambers, for 10 MeV neutrons. Neutron Cross Section in natural composition of oxygen, carbon, argon and hydrogen. Energy deposition for 1 MeV neutrons in oxygen, carbon, argon and hydrogen gaseous chambers (1mx1mx1m). Mary Tsagri, CERN – PH / SFT Mary Tsagri, CERN – PH / SFT Radiative Capture Cross Section of neutrons in Natural HYDROGEN. Agreement between Geant4, JEFF- 3.0 and JEF-2.2. Large differences with the new libraries: ENDF/B- VII.0 and JEFF-3.1, which coincide. GEANT4 GEANT4 Validation & Simulation Validation & Simulation Geant4 is a toolkit for the simulation of the passage of energetic particles through matter. Its areas of application include HEP, Nuclear & Accelerator physics, as well as studies in space and medical science. Validation: Validation: The Geant4 toolkit is used in production by numerous HEP experiments. In the past, validation for many application areas have been made. This work undertakes a new validation of neutron interactions in gases relevant for gaseous detectors. Various improvements are being introduced quasi continuously. Contrary to the theoretically predictable electromagnetic interaction of particles like γ, e ±, etc., the interaction of neutrons with matter, i.e. atomic nuclei, relies rather on measurements up to about 10 MeV neutron kinetic energy. Geant4 created its own library of cross sections for neutrons, derived from evaluations current in the late 1990s, with some updates over the last 5 years. One aim is to find the origin of neutron cross sections used in Geant4 (for elements where this information is not available), and identify ones for which the use of newer evaluations will be necessary. In this work, we make a comparison between cross sections from the neutron libraries and Geant4, aiming to improve the performance of Geant4 and its reliability too. We validate the Geant4 Cross Sections for key chamber gases against benchmark data from several Neutron Libraries, including recent and those older evaluations. For this we used JANIS 3.0 (Java-based Nuclear Information Software) including all libraries which had data available for each element. Libraries used: ENDF/B-VII.0 & ENDF/B-VI.8 : Evaluated Nuclear Data File (December 2006 and 2001, respectively) JEF-2.2 : Joint Evaluated File (January 1997) JEFF-3.0 : Joint Evaluated Fission and Fusion, “...this library superseded JEF ” (April 2002) JEFF-3.1 : “...this library superseded JEFF ” (May 2005) JEFF-3.0/A : Neutron Activation File JENDL-3.3 : Japanese Evaluated Nuclear Data Library (2002) Validation: Validation: The Geant4 toolkit is used in production by numerous HEP experiments. In the past, validation for many application areas have been made. This work undertakes a new validation of neutron interactions in gases relevant for gaseous detectors. Various improvements are being introduced quasi continuously. Contrary to the theoretically predictable electromagnetic interaction of particles like γ, e ±, etc., the interaction of neutrons with matter, i.e. atomic nuclei, relies rather on measurements up to about 10 MeV neutron kinetic energy. Geant4 created its own library of cross sections for neutrons, derived from evaluations current in the late 1990s, with some updates over the last 5 years. One aim is to find the origin of neutron cross sections used in Geant4 (for elements where this information is not available), and identify ones for which the use of newer evaluations will be necessary. In this work, we make a comparison between cross sections from the neutron libraries and Geant4, aiming to improve the performance of Geant4 and its reliability too. We validate the Geant4 Cross Sections for key chamber gases against benchmark data from several Neutron Libraries, including recent and those older evaluations. For this we used JANIS 3.0 (Java-based Nuclear Information Software) including all libraries which had data available for each element. Libraries used: ENDF/B-VII.0 & ENDF/B-VI.8 : Evaluated Nuclear Data File (December 2006 and 2001, respectively) JEF-2.2 : Joint Evaluated File (January 1997) JEFF-3.0 : Joint Evaluated Fission and Fusion, “...this library superseded JEF ” (April 2002) JEFF-3.1 : “...this library superseded JEFF ” (May 2005) JEFF-3.0/A : Neutron Activation File JENDL-3.3 : Japanese Evaluated Nuclear Data Library (2002) Elastic Cross Section of neutrons in natural hydrogen. Agreement between Geant4, JEFF-3.0, ENDF/B-VI.8, JEF-2.2, JEFF-3.1, ENDF/B-VII.0 and JENDL-3.3. Radiative Capture Cross Section of neutrons in natural carbon. Geant4 overlaps with JENDL-3.3. Also in this plot are shown: ENDF/B-VI.8, JEFF-3.0, JEF-2.2, ENDF/B-VII.0 and JEFF-3.1. Elastic Cross Section of neutrons in natural carbon. Geant4 fits well with JEFF-3.0, ENDF/B-VI.8, JEF-2.2, JEFF-3.1, ENDF/B-VII.0 and JENDL-3.3. Radiative Capture Cross Section of neutrons in natural krypton. Geant4 does not follow any of the libraries. JEF-2.2 is behind JEFF-3.0. Elastic Cross Section of neutrons in natural krypton. Geant4 follows in general, JEFF-3.0, JEFF- 3.1, JEF-2.2 and JENDL-3.3. Large differences with the new library ENDF/B-VII.0. Elastic Cross Section of neutrons in natural argon. Agreement between Geant4, JEFF-3.0 and JEF-2.2. Large discrepancies with the new libraries ENDF/B-VII.0 and JEFF- 3.1, which coincide with each other. Radiative Capture Cross Section of neutrons in argon. Agreement between Geant4, JEFF-3.0 and JEF-2.2. Large differences with the new libraries ENDF/B-VII.0 and JEFF-3.1 which overlap. Elastic Cross Section of neutrons in natural xenon. Good agreement between Geant4, JEFF-3.0, ENDF/B-VI.8 and JEFF-3.1 above MeV. Differences with the recent library: ENDF/B-VII.0. Radiative Capture Cross Section of neutrons in xenon. Geant4 follows JEFF-3.1 and JEFF- 3.0 for energies above MeV. Quite good agreement with ENDF/B-VI.8. Below MeV JEFF-3.0 underlies JEFF-3.1. Inelastic Cross Section of neutrons in natural argon. Geant4, JEF 2.2 and ENDF/B-VII.0. The long blue/black line represents the production of one neutron in the exit channel. The short ones, near 20 MeV, show the sum of “all” inelastic interaction [like (n,p), (n,d), (n,t), …] Simulation: The high multiplicity and the high rate in LHC experiments imply high neutron background mostly up to 1-10 MeV. The eventual goal of this work is to simulate monochromatic neutrons of energies 1 and 10 MeV. Elastic recoils of heavy nuclei like Argon deposit energy below ~ keV, which increases with decreasing atomic number A. Therefore, the case of Hydrogen is the most extreme one. Even though, Hydrogen is not used as principle active gas in chambers, it is part of the chemical composition of various quenchers, making ~5-10% of the total gas composition. Thus, the impact of the quencher is not at all negligible, since an elastically recoiling proton can take a large fraction (max. 100%) of the energy of the interacting neutron. In fact, such recoiling protons will deposit their energy as relatively long tracks and they cannot be suppressed easily/fast from further consideration. This work allows to quantify the implications of hydrogen compositions like the quencher gas CH4. Technical Details: G4 version: 9.2.p01. Physics List: QGSP_BERT_HP. Incident number of neutrons: Simulation: The high multiplicity and the high rate in LHC experiments imply high neutron background mostly up to 1-10 MeV. The eventual goal of this work is to simulate monochromatic neutrons of energies 1 and 10 MeV. Elastic recoils of heavy nuclei like Argon deposit energy below ~ keV, which increases with decreasing atomic number A. Therefore, the case of Hydrogen is the most extreme one. Even though, Hydrogen is not used as principle active gas in chambers, it is part of the chemical composition of various quenchers, making ~5-10% of the total gas composition. Thus, the impact of the quencher is not at all negligible, since an elastically recoiling proton can take a large fraction (max. 100%) of the energy of the interacting neutron. In fact, such recoiling protons will deposit their energy as relatively long tracks and they cannot be suppressed easily/fast from further consideration. This work allows to quantify the implications of hydrogen compositions like the quencher gas CH4. Technical Details: G4 version: 9.2.p01. Physics List: QGSP_BERT_HP. Incident number of neutrons: Conclusions: Once this work is completed, it might make future Geant4 updates easier to implement. This is an ambitious but necessary first step, keeping in mind the wide applications Geant4 has found in various disciplines. Throughout this work we have focused on typical gaseous compositions used in chambers in HEP experiments, and in particular in LHC experiments. We have identified that for Ar, Xe, Kr, H, C and O (not shown here) G4 follows rather well JEF 2.2. This justifies that an update of the input used by the Geant4 code is in place. Moreover, neutron cross sections from recent libraries are now available. The structure of these data files allows an easy access by Gent4 itself without the need of further treatment. As a first byproduct, we applied the same reasoning for the first time also for the quenchers, which are inherent to the working principle of any gaseous detector. After all, their part makes about 5-10% of the total detector gas. More specifically, we conclude in this work, as expected, that a quencher with Hydrogen composition seems to be sensitive to the neutron background in experiments in LHC and even more so in sLHC with the expected much higher neutron fluxes References: