Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations

Xiao-Xiao  Cai; Isabel  Llamas-Jansa; Steven  Mullet; Sverre  Hval; Esben Bryndt Klinkby; Thomas  Kittelmann; Kalliopi  Kanaki; Richard  Hall-Wilton; B. C.  Hauback

doi:10.1109/NSSMIC.2013.6829560

Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations

Xiao-Xiao Cai, Isabel Llamas-Jansa, Steven Mullet, Sverre Hval, Esben Bryndt Klinkby, Thomas Kittelmann, Kalliopi Kanaki, Richard Hall-Wilton, B. C. Hauback

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Abstract

Geant4 is an open source general purpose simulation toolkit for particle transportation in matter. Since the extension of the thermal scattering model in Geant4.9.5 and the availability of the IAEA HP model cross section libraries, it is now possible to extend the application area of Geant4 to reactor modelling. Before version 9.5, Geant4 HP thermal scattering model (i.e. the S(α; β) model ) supports only three bounded isotopes, namely, H in water and polyethylene, and C in graphite. Newly supported materials include D in heavy water, O and Be in beryllium oxide, H and Zr in zirconium hydride, U and O in uranium dioxide, Al metal, Be metal, and Fe metal. The native HP cross section library G4NDL does not include data for elements with atomic number larger than 92. Therefore, transuranic elements, which have impacts for a realistic reactor, can not be simulated by the combination of the HP models and the G4NDL library. However, cross sections of those missing isotopes were made available recently through the IAEA project “new evaluated neutron cross section libraries for Geant4”.

Original language	English
Title of host publication	Proceedings of 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC)
Number of pages	2
Publisher	IEEE
Publication date	2013
ISBN (Print)	978-1-4799-0533-1
DOIs	https://doi.org/10.1109/NSSMIC.2013.6829560
Publication status	Published - 2013
Event	2013 IEEE Nuclear Science Symposium and Medical Imaging Conference and Workshop on Room-Temperature Semiconductor X-ray and Gamma-Ray Detectors: Beyond Imagination of Future Science - COEX Convention Center Grand Ball Room, Seoul, Korea, Republic of Duration: 27 Oct 2013 → 2 Nov 2013 https://ewh.ieee.org/soc/nps/nss-mic/2013/NSSMain.html https://ieeexplore.ieee.org/xpl/conhome/6819718/proceeding

Conference

Conference	2013 IEEE Nuclear Science Symposium and Medical Imaging Conference and Workshop on Room-Temperature Semiconductor X-ray and Gamma-Ray Detectors
Location	COEX Convention Center Grand Ball Room
Country/Territory	Korea, Republic of
City	Seoul
Period	27/10/2013 → 02/11/2013
Internet address	https://ewh.ieee.org/soc/nps/nss-mic/2013/NSSMain.html https://ieeexplore.ieee.org/xpl/conhome/6819718/proceeding

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Cai, X.-X., Llamas-Jansa, I., Mullet, S., Hval, S., Klinkby, E. B., Kittelmann, T., Kanaki, K., Hall-Wilton, R., & Hauback, B. C. (2013). Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations. In Proceedings of 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC) IEEE. https://doi.org/10.1109/NSSMIC.2013.6829560

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author = "Xiao-Xiao Cai and Isabel Llamas-Jansa and Steven Mullet and Sverre Hval and Klinkby, {Esben Bryndt} and Thomas Kittelmann and Kalliopi Kanaki and Richard Hall-Wilton and Hauback, {B. C.}",

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Cai, X-X, Llamas-Jansa, I, Mullet, S, Hval, S, Klinkby, EB, Kittelmann, T, Kanaki, K, Hall-Wilton, R & Hauback, BC 2013, Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations. in Proceedings of 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC). IEEE, 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference and Workshop on Room-Temperature Semiconductor X-ray and Gamma-Ray Detectors, Seoul, Korea, Republic of, 27/10/2013. https://doi.org/10.1109/NSSMIC.2013.6829560

Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations. / Cai, Xiao-Xiao ; Llamas-Jansa, Isabel ; Mullet, Steven et al.
Proceedings of 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC). IEEE, 2013.

Research output: Chapter in Book/Report/Conference proceeding › Conference abstract in proceedings › Research › peer-review

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T1 - Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations

AU - Cai, Xiao-Xiao

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AU - Mullet, Steven

AU - Hval, Sverre

AU - Klinkby, Esben Bryndt

AU - Kittelmann, Thomas

AU - Kanaki, Kalliopi

AU - Hall-Wilton, Richard

AU - Hauback, B. C.

PY - 2013

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N2 - Geant4 is an open source general purpose simulation toolkit for particle transportation in matter. Since the extension of the thermal scattering model in Geant4.9.5 and the availability of the IAEA HP model cross section libraries, it is now possible to extend the application area of Geant4 to reactor modelling. Before version 9.5, Geant4 HP thermal scattering model (i.e. the S(α; β) model ) supports only three bounded isotopes, namely, H in water and polyethylene, and C in graphite. Newly supported materials include D in heavy water, O and Be in beryllium oxide, H and Zr in zirconium hydride, U and O in uranium dioxide, Al metal, Be metal, and Fe metal. The native HP cross section library G4NDL does not include data for elements with atomic number larger than 92. Therefore, transuranic elements, which have impacts for a realistic reactor, can not be simulated by the combination of the HP models and the G4NDL library. However, cross sections of those missing isotopes were made available recently through the IAEA project “new evaluated neutron cross section libraries for Geant4”.

AB - Geant4 is an open source general purpose simulation toolkit for particle transportation in matter. Since the extension of the thermal scattering model in Geant4.9.5 and the availability of the IAEA HP model cross section libraries, it is now possible to extend the application area of Geant4 to reactor modelling. Before version 9.5, Geant4 HP thermal scattering model (i.e. the S(α; β) model ) supports only three bounded isotopes, namely, H in water and polyethylene, and C in graphite. Newly supported materials include D in heavy water, O and Be in beryllium oxide, H and Zr in zirconium hydride, U and O in uranium dioxide, Al metal, Be metal, and Fe metal. The native HP cross section library G4NDL does not include data for elements with atomic number larger than 92. Therefore, transuranic elements, which have impacts for a realistic reactor, can not be simulated by the combination of the HP models and the G4NDL library. However, cross sections of those missing isotopes were made available recently through the IAEA project “new evaluated neutron cross section libraries for Geant4”.

U2 - 10.1109/NSSMIC.2013.6829560

DO - 10.1109/NSSMIC.2013.6829560

M3 - Conference abstract in proceedings

SN - 978-1-4799-0533-1

BT - Proceedings of 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC)

PB - IEEE

T2 - 2013 IEEE Nuclear Science Symposium and Medical Imaging Conference and Workshop on Room-Temperature Semiconductor X-ray and Gamma-Ray Detectors

Y2 - 27 October 2013 through 2 November 2013

ER -

Preliminary assessment of Geant4 HP models and cross section libraries by reactor criticality benchmark calculations

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