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

Content Provider	IEEE Xplore Digital Library
Author	Xiao-Xiao Cai Llamas-Jansa, I. Mullet, S. Hval, S. Klinkby, E. Kittelmann, T. Kanaki, K. Hall-Wilton, R. Hauback, B.C.
Copyright Year	2013
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”.
Starting Page	1
Ending Page	2
File Size	106969
Page Count	2
File Format	PDF
e-ISBN	9781479905348
DOI	10.1109/NSSMIC.2013.6829560
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2013-10-27
Publisher Place	South Korea
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Libraries Benchmark testing Neutrons Scattering Metals Inductors Isotopes
Content Type	Text
Resource Type	Article

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor

Testing of cross section libraries for triga criticality benchmark.

Study of spent fuel management by transmutation in an accelerator driven subcritical system

Anew physics model for the charged particle transport with Geant4

New Standard Evaluated Neutron Cross Section Libraries for the GEANT4 Code and First Verification

Activation of silicon carbide composites in fusion systems

Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO

Using various point wise and multi-group cross section libraries in MORET criticality calculations

Chalk river N.R.X. Nuclear reactor

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

Similar Documents

Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor

Testing of cross section libraries for triga criticality benchmark.

Study of spent fuel management by transmutation in an accelerator driven subcritical system

Anew physics model for the charged particle transport with Geant4

New Standard Evaluated Neutron Cross Section Libraries for the GEANT4 Code and First Verification

Activation of silicon carbide composites in fusion systems

Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO

Using various point wise and multi-group cross section libraries in MORET criticality calculations

Chalk river N.R.X. Nuclear reactor

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