Evaluation of the thermal neutron flux in samples of Al–Au alloy irradiated in the carrousel channels of the TRIGA MARK I IPR-R1 reactor using MCNP code

Salomé, Jean Anderson Dias; Guerra, Bruno Teixeira; Pereira, Cláubia; Menezes, M. A. B. C.; Silva, C.A.M. da; Dalle, H.M.

doi:10.1016/j.nucengdes.2014.03.020

Cited by 4 publications

(7 citation statements)

References 6 publications

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“…For all calculations estimated in each isotope, the relative code error was < 5%, which is acceptable [15][16][17]. The detection limit is the lowest amount of an isotope that can be identified in the sample, i.e., the Detection Limit (g) 58 …”

Section: Reaction Ratementioning

confidence: 88%

“…To set up a preliminary model of the PGAA method at the IPR-R1 reactor and estimate the calculations at PGAA facility, in this work was used the models of previous studies [12,[15][16][17] that were validated through the MCNP5 code.…”

Section: Geometry Of the Pgaa Setupmentioning

confidence: 99%

“…All calculations estimated in this study through MCNP5 [15][16][17] were carried out with the 5. For the calculations it was used the cluster CENAPAG-MG [6,[12][13][14]18].…”

Section: Monte Carlo Calculationsmentioning

confidence: 99%

“…In the position chosen to insert the sample into the PGAA facility, a thermal neutron flux of 5.97 × 10 According to MCNP manual [15][16][17], a relative error < 10% is acceptable. For all neutron fluence rates estimated by MCNP5, the relative errors were below 10%.…”

Section: Neutron Fluence Ratementioning

confidence: 99%

“…Along the years, the TRIGA IPR-R1 reactor has been studied and modeled using the MCNP (Monte Carlo N-Particle) code. Several studies using the MCNP code have developed theoretical methods to calculate neutron flux in the sample's irradiation devices of the IPR-R1 reactor (central thimble, rotary rack, and two pneumatic tubes) and compare their results with experimental data in order to validate these models [15][16][17].…”

Section: Introductionmentioning

confidence: 99%

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

Guerra¹,

Leal²,

Pereira³

et al. 2016

JCCE

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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.

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Section: Reaction Ratementioning

confidence: 88%

Section: Geometry Of the Pgaa Setupmentioning

confidence: 99%

“…All calculations estimated in this study through MCNP5 [15][16][17] were carried out with the 5. For the calculations it was used the cluster CENAPAG-MG [6,[12][13][14]18].…”

Section: Monte Carlo Calculationsmentioning

confidence: 99%

Section: Neutron Fluence Ratementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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