Neutron spatial flux profile measurement in compact subcritical system using miniature neutron detectors

Shukla, Mayank; Desai, S. S.; Roy, Tushar; Kashyap, Yogesh; Ray, Nirmal; Bajpai, Shefali; Patel, Tarun; Sinha, Alok

doi:10.1016/j.nima.2014.10.059

Cited by 8 publications

(2 citation statements)

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“…) is the neutron flux, and R(E) is any combination of sums and products of energy-dependent quantities known to MCNPX [8]. e neutron flux has been determined according to the following equation [5]:…”

Section: Calculations Mcnpx Program Has Been Usedmentioning

confidence: 99%

“…A new computational model of the JSI TRIGA-Mark II reactor was built for TRIPOLI computer code and compared with existing MCNP code model. e neutron spatial flux profile measurement in compact subcritical system using miniature neutron detectors was conducted by Shukla et al [5]. In that research, the authors presented the thermal neutron flux profile measurement in a compact subcritical system using indigenously developed miniature gas filled neutron detectors.…”

Section: Introductionmentioning

confidence: 99%

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Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors

Tien

Quoc

2021

Science and Technology of Nuclear Installations

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In this paper, the accelerator-driven subcritical reactor (ADSR) is simulated based on structure of the TRIGA-Mark II reactor. A proton beam is accelerated and interacts on the lead target. Two cases of using lead are considered here: firstly, solid lead is referred to as spallation neutron target and water as the coolant; secondly, molten lead is considered both as a target and as a coolant. The proton beam in the energy range from 115 MeV to 2000 MeV interacts with the lead to create neutrons. The neutron parameters as neutron yield Yn/p, neutron multiplication factor k, the radial and axial distributions of the neutron flux in the core have been calculated by using MCNPX program. The results show that the neutron yield increases as the energies of the proton beam increases. When using the lead target, the differences between the neutron yield are from 4.2% to 14.2% depending on the energies of the proton beam. The proportion of uranium in the mixtures should be around 24% to produce an effective neutron multiplier factor greater than 0.9. The neutron fluxes are much higher than the same calculations for the TRIGA-Mark II reactor model using tungsten target and light water coolant.

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Section: Calculations Mcnpx Program Has Been Usedmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%