Advanced Monte Carlo procedure for the IFMIF d-Li neutron source term based on evaluated cross section data

Simakov, S.P.; Fischer, U.; Möllendorff, Ulrich von; Schmuck, I.; Konobeev, A. Yu.; Korovin, Yu.A.; Pereslavtsev, P.

doi:10.1016/s0022-3115(02)01142-x

Cited by 72 publications

(43 citation statements)

References 8 publications

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“…In the frame of the IFMIF facility, a MCNPX deficient performance has been also reported to predict neutron yields due to interactions of deuterons in a thick lithium target [12]. For the same application, a similar conclusion was reported for PHITS [13].…”

Section: Introductionmentioning

confidence: 71%

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New capabilities for Monte Carlo simulation of deuteron transport and secondary products generation

Sauvan

Sanz

Ogando

2010

Nuclear Instruments and Methods in Physics Research Section A:

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Keywords: MCNPX Monte Carlo Charged particles Transport library Variance reductionSeveral important research programs are dedicated to the development of facilities based on deuteron accelerators. In designing these facilities, the definition of a validated computational approach able to simulate deuteron transport and evaluate deuteron interactions and production of secondary particles with acceptable precision is a very important issue. Current Monte Carlo codes, such as MCNPX or PHITS, when applied for deuteron transport calculations use built-in semi-analytical models to describe deuteron interactions. These models are found unreliable in predicting neutron and photon generated by low energy deuterons, typically present in those facilities.We present a new computational tool, resulting from an extension of the MCNPX code, which improve significantly the treatment of problems where any secondary product (neutrons, photons, tritons, etc.) generated by low energy deuterons reactions could play a major role. Firstly, it handles deuteron evaluated data libraries, which allow describing better low deuteron energy interactions. Secondly, it includes a reduction variance technique for production of secondary particles by charged particle-induced nuclear interactions, which allow reducing drastically the computing time needed in transport and nuclear response calculations. Verification of the computational tool is successfully achieved. This tool can be very helpful in addressing design issues such as selection of the dedicated neutron production target and accelerator radioprotection analysis. It can be also helpful to test the deuteron cross-sections under development in the frame of different international nuclear data programs.

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Section: Introductionmentioning

confidence: 71%

“…This same idea is implemented in the MCDelicious code [12], with the distinction that in the MCDelicious case the trajectories of deuterons are rectilinear.…”

Section: Variance Reduction Technique For Light Ionsmentioning

confidence: 99%

New capabilities for Monte Carlo simulation of deuteron transport and secondary products generation

Sauvan

Sanz

Ogando

2010

Nuclear Instruments and Methods in Physics Research Section A:

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“…To provide the data for describing the source neutron generation in the lithium target of the IFMIF neutron source by means of the McDeLicious Monte Carlo code [14], a complete new evaluation of the d+ 6,7 Li interaction cross sections up to 50 MeV deuteron energy has been performed. A new methodology was applied which takes into account compound nucleus reactions, pre-equilibrium processes, stripping and direct interactions [15].…”

Section: Specific Data For Ifimfmentioning

confidence: 99%

Development needs of nuclear data for fusion technology

Fischer

Batistoni

Forrest

et al. 2007

Nd2007

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“…Neutrons up to about 55 MeV will be produced by two 125 mA beams of 40 MeV deuterons bombarding a thick target of flowing liquid lithium. So far, nuclear design of IFMIF has been performed mainly using a code McDelicious developed in Forschungszentrum Karlsruhe (FZK) [2][3][4]. In future detailed design of IFMIF, more accurate estimation will be required on behaviors of fast neutrons with energies up to 55 MeV in materials.…”

Section: Introductionmentioning

confidence: 99%

Neutronics analysis of the International Fusion Materials Irradiation Facility using the PHITS code

Kaku

Watanabe

2007

Nd2007

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Abstract. The PHITS code is applied to neutronic calculations for the high flux test module in IFMIF. The neutron energy spectrum and heating rate calculated with the Li(d,xn) neutron source term obtained by the McDelicious code reproduce the FZK result fairly well. The sensitivity of three nuclear data libraries (LA150, NRG-2003, and JENDL/HE-2004) to nuclear heating calculation and the validity of KERMA approximation are discussed. A new nuclear data evaluation of the d + Li reaction is proposed on the basis of an advanced model calculation with a continuum-discretized coupled-channels (CDCC) method. A preliminary CDCC analysis of deuteron elastic scattering from Li is presented.

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Advanced Monte Carlo procedure for the IFMIF d-Li neutron source term based on evaluated cross section data

Cited by 72 publications

References 8 publications

New capabilities for Monte Carlo simulation of deuteron transport and secondary products generation

New capabilities for Monte Carlo simulation of deuteron transport and secondary products generation

Development needs of nuclear data for fusion technology

Neutronics analysis of the International Fusion Materials Irradiation Facility using the PHITS code

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