Monte Carlo simulations for design of the KFUPM PGNAA facility

Naqvi, A.A.; Nagadi, M.M.; Khateeb-ur-Rehman,; Maslehuddin, Mohammed; Kidwai, S.

doi:10.1016/s0969-806x(02)00331-6

Cited by 28 publications

(11 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…According to the simulation results, we set the thicknesses of t1, t2, t3 to 1 cm, 20 cm, and 15 cm respectively. The materials of W, WC, W 2 C and Cu had a better effect compared with other materials, but their weight and price were higher, so we chose lead as the material of the reflector [29][30][31][32].…”

Section: Reflector and Moderator Calculationsmentioning

confidence: 99%

Simulation of the cement measurement based on the pulse DT neutron generator: A Monte Carlo study

Gao

et al. 2021

PLoS ONE

View full text Add to dashboard Cite

The PGNAA system for the cement measurement was simulated based on Monte Carlo method. The sizes of the moderator and reflector for the 14 MeV DT neutron generator were optimized for fast and thermal neutron outputs. The DT neutron generator was simulated at the pulse mode, and the gamma-ray detector was set as LaBr3(Ce) scintillator. The characteristic peaks of the major elements (Ca, Si, Al, Fe) can be identified from the gamma-ray spectra which induced at the different time intervals of the neutron radiation. For the different thicknesses of the cement sample the ratios of the gamma-ray peaks were observed, and the result showed that when the thickness was between 20 to 30 cm, the ratios became stable. With the ratios, we can calculate the iron modulus, silica modulus and lime saturation factor.

show abstract

Section: Reflector and Moderator Calculationsmentioning

confidence: 99%

Simulation of the cement measurement based on the pulse DT neutron generator: A Monte Carlo study

Gao

et al. 2021

PLoS ONE

View full text Add to dashboard Cite

show abstract

“…The elemental analysis of large samples of bulk materials in the KFUPM accelerator-based PGNAA setup is carried out via prompt gamma-rays excited through the capture of thermal neutrons (Naqvi et al, 2003b). Thermal neutrons are produced in the specimen through moderation from external moderator surrounding the cylindrical specimen.…”

Section: The Kfupm Pgnaa Setupmentioning

confidence: 99%

“…The moderator is placed between a 2.8 MeV neutron target (D(d,n) reaction target). The design of the moderators was obtained from the Monte Carlo simulations carried out using the procedures described earlier (Naqvi et al, 2003b). The cylindrical (Naqvi et al, 2003a-b;2004b) as well as rectangular (Naqvi et al, 2005;2006a-b;2008) moderators were tested in the PGNAA setup.…”

Section: The Kfupm Pgnaa Setupmentioning

confidence: 99%

“…The design of the moderators was obtained from the Monte Carlo simulations carried out using the procedures described earlier (Naqvi et al, 2003b). The neutron shielding was made of a mixture of paraffin and lithium carbonate mixed in equal weight proportion (Naqvi et al, 2003b). The rectangular moderator, made of paraffin wax, has a 49 cm × 49 cm (width × height) cross-sectional area and a 20 cm length.…”

Section: The Kfupm Pgnaa Setupmentioning

confidence: 99%

See 1 more Smart Citation

Non-destructive analysis of concrete for corrosion studies using nuclear technique

Naqvi

Nagadi

Garwan

et al. 2010

AFP

View full text Add to dashboard Cite

Chloride-induced reinforcement corrosion is the principal cause of deterioration of concrete structures in the Arabian Gulf and the world over. Preventive measures against corrosion require maintaining the chloride and sulphate concentration in concrete below the threshold limits specified by the standards. This requires monitoring the chloride and sulphate concentration in concrete, and a nondestructive technique is preferable for this purpose. The Prompt-Gamma Neutron Activation Analysis (PGNAA) technique can be used to monitor the concentration of corrosive elements in concrete specimens. An accelerator-based PGNAA setup has been developed to measure the chloride and sulphate concentration in concrete. The PGNAA technique has been utilised successfully to measure the elemental composition of concrete. A.A. Naqvi et al.In this regard, several studies were undertaken to determine the calcium, silicon, chloride and sulphate concentration in the concrete specimens. Furthermore, the concentration of compounds, such as lime and silica was also determined. The results of these studies along with a description of the facility are presented in this paper.Reference to this paper should be made as follows: Naqvi, A.A., Nagadi, M.M., Garwan, M.A., Al-Amoudi, O.S.B., Maslehuddin, M., Khateeb-ur-Rehman and Raashid, M. (2010) 'Non-destructive analysis of concrete for corrosion studies using nuclear technique', Atoms for Peace

show abstract

“…The PGNAA is based on prompt-gamma rays produced by neutron capture reactions within the sample elements and they are detected by appropriate gamma-ray spectrometry In this scenario, the establishment of PGAA at CDTN would be a possibility to expand not only the use of the TRIGA reactor, but also the NAA. Besides, PGAA is a rapid, non-destructive and powerful multi-elemental analysis technique [3,10,11].…”

Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulations for a Preliminary Design of TRIGA IPR-R1 PGAA Facility

Guerra¹,

Leal²,

Pereira³

et al. 2016

JCCE

View full text Add to dashboard Cite

Abstract:In this paper, the evaluation of a preliminary design of a PGAA (prompt gamma activation analysis) facility based on Monte Carlo simulations is presented and discussed. The implementation of the PGAA method at the CDTN (nuclear technology development centre) would increase the applications of the TRIGA reactor. The preliminary design is based on a quasi vertical hollow cylinder (called neutron extractor) in the reactor pool to extract the neutron flux. This study evaluates the neutron flux in the upper position of the cylinder in the suggested position of the samples to be analyzed by the PGAA. The calculations of the radioactive capture reaction rates and of the detection limits for some isotopes were performed. Through all these calculations, the feasibility of the application of the PGAA method at the IPR-R1 installations was evaluated. According to the obtained results, it can be concluded that is possible to apply the PGAA method at the IPR-R1 reactor, even with its design restrictions.

show abstract

Monte Carlo simulations for design of the KFUPM PGNAA facility

Cited by 28 publications

References 8 publications

Simulation of the cement measurement based on the pulse DT neutron generator: A Monte Carlo study

Simulation of the cement measurement based on the pulse DT neutron generator: A Monte Carlo study

Non-destructive analysis of concrete for corrosion studies using nuclear technique

Monte Carlo Simulations for a Preliminary Design of TRIGA IPR-R1 PGAA Facility

Contact Info

Product

Resources

About