Validation of the Monte Carlo model developed to assess the activity generated in control rods of a BWR

Ródenas, J.; Abarca, A.; Gallardo, S.; Sollet, E.

doi:10.1016/j.nima.2009.10.084

Cited by 8 publications

(5 citation statements)

References 2 publications

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“…The sample has cylindrical shape with a radius of 1 cm and a length of 7 cm. It has a volume of 21.99 cm 3 and a density ρ= 7.9 g/cm 3 . Thus it has a mass of 173.73 g. The composition of the sample is listed in …”

Section: Experimental Measurementsmentioning

confidence: 99%

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Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

Ródenas¹,

Gallardo²,

Weirich³

et al. 2014

Radiation Physics and Chemistry

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ElsevierRódenas Diago, J.; Gallardo Bermell, S.; Weirich, F.; Hansen, W. (2014) Abstract: All materials present in the core of a nuclear reactor are activated by neutron irradiation. The activity so generated produces a dose around the material. This dose is a potential risk for workers in the surrounding area when materials are withdrawn from the reactor. Therefore, it is necessary to assess the activity generated and the dose produced. In previous works, neutron activation of control rods and doses around the storage pool where they are placed have been calculated for a Boiling Water Reactor using the MCNP5 code based on the Monte Carlo method. Most of the activation is produced indeed in stainless steel components of the nuclear reactor core not only control rods. In this work, a stainless steel sample is irradiated in the Training Reactor AKR-2 of the Technical University Dresden. Dose measurements around the sample have been performed for different times after the irradiation.Experimental dosimetric values are compared with results of Monte Carlo simulation of the irradiation.Comparison shows a good agreement. Hence, the activation Monte Carlo model can be considered as validated.

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Section: Experimental Measurementsmentioning

confidence: 99%

“…In previous works [1][2][3][4][5], neutron activation of control rods and doses around the storage pool where control rods are placed have been calculated for a Boiling Water Reactor using the MCNP5 code [6] based on the Monte Carlo method.…”

Section: Introductionmentioning

confidence: 99%

Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

Ródenas¹,

Gallardo²,

Weirich³

et al. 2014

Radiation Physics and Chemistry

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“…Furthermore, high uncertainties are associated with these measurements. Fortunately, the uncertainty was lower for the highest dose and activity, found in the handle (Ródenas et al, 2010b).…”

Section: Stainlessmentioning

confidence: 98%

“…A Monte Carlo model has been developed using MCNP5 to simulate the activation process (Ródenas et al, 2010b(Ródenas et al, , 2010d. The interaction rate Qj (Eq.…”

Section: Monte Carlo Modelsmentioning

confidence: 99%

“…Neutron activation of control rods in a BWR and doses around the storage pool for irradiated fuel of the plant where the control rods are placed after withdrawn from the reactor were calculated using the MCNP5 code. Calculations were performed following the guidelines exposed in the previous point (Ródenas et al, 2010b(Ródenas et al, , 2010d.…”

Section: Bwr Control Rodsmentioning

confidence: 99%

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Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor

Ródenas

2017

Radiation Physics and Chemistry

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All materials exposed to some neutron flux can be activated independently of the kind of the neutron source. In this study, a nuclear reactor has been considered as neutron source. In particular, the activation of control rods in a BWR is studied to obtain the doses produced around the storage pool for irradiated fuel of the plant when control rods are withdrawn from the reactor and installed into this pool. It is very important to calculate these doses because they can affect to plant workers in the area. The MCNP code based on the Monte Carlo method has been applied to simulate activation reactions produced in the control rods inserted into the reactor. Obtained activities are introduced as input into another MC model to estimate doses produced by them. The comparison of simulation results with experimental measurements allows the validation of developed models. The developed MC models have been also applied to simulate the activation of other materials, such as components of a stainless steel sample introduced into a training reactors. These models, once validated, can be applied to other situations and materials where a neutron flux can be found, not only nuclear reactors. For instance, activation analysis with an Am-Be source, neutrography techniques in both medical applications and non-destructive analysis of materials, civil engineering applications using a Troxler, analysis of materials in decommissioning of nuclear power plants, etc.

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Analysis of dose rates received around the storage pool for irradiated control rods in a BWR nuclear power plant

Ródenas

Abarca

Gallardo

2011

Applied Radiation and Isotopes

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Validation of the Monte Carlo model developed to assess the activity generated in control rods of a BWR

Cited by 8 publications

References 2 publications

Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor

Analysis of dose rates received around the storage pool for irradiated control rods in a BWR nuclear power plant

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