First IFMIF/EVEDA Radioprotection Studies for the Preliminary Design of the Accelerator Beam Dump

Sanz, J.; García, M.; Ogando, F.; Mayoral, A.; López, Daniel; Sauvan, P.; Brañas, B.

doi:10.13182/fst09-a8914

Cited by 18 publications

(10 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In this respect a new computational procedure was proposed [4] based on extending MCNPX to use data files for neutron (and gamma) production for deuteroninduced reactions generated by the TALYS code [5]. In this context, the second objective of this work was to test the capability of TALYS to generate these data files for neutron production and for deuteron induced activation cross sections with adequate accuracy.…”

Section: Introductionmentioning

confidence: 99%

Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF/EVEDA accelerator prototype

Blidéanu

García

Joyer

et al. 2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

In the frame of IFMIF/EVEDA activities, a prototype accelerator delivering a high power deuteron beam is under construction in Japan. Interaction of these deuterons with matter will generate high levels of neutrons and induced activation, whose predicted yields depend strongly on the models used to calculate the different cross sections. A benchmark test was performed to validate these data for deuteron energies up to 20 MeV and to define a reasonable methodology for calculating the cross sections needed for EVEDA. Calculations were performed using the nuclear models included in MCNPX and PHITS, and the dedicated nuclear model code TALYS. Although the results obtained using TALYS (global parameters) or Monte Carlo codes disagree with experimental values, a solution is proposed to compute cross sections that are a good fit to experimental data. A consistent computational procedure is also suggested to improve both transport simulations/prompt dose and activation/residual dose calculations required for EVEDA.

show abstract

Section: Introductionmentioning

confidence: 99%

Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF/EVEDA accelerator prototype

Blidéanu

García

Joyer

et al. 2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

show abstract

“…For the energy physics domain corresponding to the deuterons typically present in those facilities (lower than 40 MeV), these models are found unreliable in predicting neutron and photon generated by these low energy deuterons [8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

“…These codes were tested regarding their capability to predict neutron production for EVEDA conditions for Cu [10], as beam stop material, as well as for other typical elements of accelerator equipments [11] in an energy range from 0 to 20 MeV. Crosssections for neutron produced by deuteron reactions were calculated with the different nuclear models included in MCNPX and PHITS and compared with available experimental data.…”

Section: Introductionmentioning

confidence: 99%

“…In this context, a new computational methodological approach was proposed [10] based on the use of an extended MCNPX version capable to use evaluated deuteron libraries for neutron (and gamma) production. The Talys nuclear reaction code [14] was the first option suggested [10,11] to be explored as potential candidate to produce the evaluated data for double-differential neutron and photon emission cross-sections for incident deuterons up 40MeV.…”

Section: Introductionmentioning

confidence: 99%

“…The Talys nuclear reaction code [14] was the first option suggested [10,11] to be explored as potential candidate to produce the evaluated data for double-differential neutron and photon emission cross-sections for incident deuterons up 40MeV. The potential of Talys to produce deuteron evaluated data files for neutron production with enough quality has been explored in the range from 0 to 20MeV for several elements of interest in the EVEDA prototype accelerator [8,9].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

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:

Self Cite

View full text Add to dashboard Cite

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.

show abstract

Inverse iteration algorithm for neutron depth profiling

Cong

Xiao

Yao

et al. 2018

J Radioanal Nucl Chem

View full text Add to dashboard Cite

First IFMIF/EVEDA Radioprotection Studies for the Preliminary Design of the Accelerator Beam Dump

Cited by 18 publications

References 4 publications

Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF/EVEDA accelerator prototype

Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF/EVEDA accelerator prototype

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

Inverse iteration algorithm for neutron depth profiling

Contact Info

Product

Resources

About