Reactor Pressure Vessel Neutron Dosimetry Assessments for UK PWR Plant

Thornton, D. A.; Lewis, T.A.; Mossop, JR; Page, CJ; Haddock, SA

doi:10.1520/stp13577s

Cited by 8 publications

(2 citation statements)

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“…Let's call the time integral of the neutron source as the effective source for neutron fluence and the time integral of the time-weighted neutron source as the effective source for detector activity [2][3][4][5]. The advantage of the effective source method is the demand of only one forward transport calculation for the time dependent neutron source (time-weighted neutron source) through the whole cycle.…”

Section: The Effective Source Methods and Applicationmentioning

confidence: 99%

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The Activation Detector Activity Calculations Using the Effective Source Method and Measurement

et al. 2017

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Abstract. In the paper the application of effective source to the solution of activation detector activities in the reactor pressure vessel cavity of the VVER-1000 reactor is presented. The effective source method applies the Boltzmann transport operator to time integrated source data to obtain detector activities. Weighting the source data by time dependent depletion of the detector activity, the result of the calculation is the detector activity. The approach works because of the inherent linearity of radiation transport in non-multiplying time-invariant media. Integrated in this way, the source data are referred to as the 'effective source'. The effective source method thereby enables the analyst to replace numerous intensive transport calculations with a single transport calculation in which the time dependence and magnitude of the source are correctly represented. Detailed description of the effective source method is presented in previous works. First, there were performed neutron-physical calculations of few real VVER-1000 cycles using MOBY-DICK macrocode. Second, there follows 3-D transport calculation using the deterministic code TORT and the cross section library BUGLE-B7 and obtained results are presented. These calculation results of activation detector activities in the reactor cavity are compared with relevant activation detectors results of the ex-vessel measurement. The comparison between calculation and measurement of activation detectors activity in the reactor cavity is necessary to the calculation quality verifying for further fast neutron fluence onto the reactor pressure vessel credible calculation. The activation detectors positions are evident from Figs 1, 2, 3.

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Section: The Effective Source Methods and Applicationmentioning

confidence: 99%

“…3 and no. 4 and approximately 26 degree sector on RPV surface (sector C in Fig. 1 and green sector in Fig.…”

Section: The Measurement Arrangementmentioning

confidence: 99%

The Activation Detector Activity Calculations Using the Effective Source Method and Measurement

et al. 2017

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A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors

Morgan

Robinson

Allen

et al. 2012

Journal of ASTM International

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This paper describes the development of a three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition (or nuclear heating) throughout the graphite cores of the UK’s Advanced Gas-cooled Reactors. Advances in the development of the Monte Carlo radiation transport code MCBEND have enabled the efficient production of detailed fully three-dimensional models that utilise three-dimensional source distributions obtained from Core Follow data supplied by the reactor physics code PANTHER. The calculational approach can be simplified to reduce both the requisite number of intensive radiation transport calculations, as well as the quantity of data output. These simplifications have been qualified by comparison with explicit calculations and they have been shown not to introduce significant systematic uncertainties. Simple calculational approaches are described that allow users of the data to address the effects on neutron damage and nuclear energy deposition predictions of the feedback resulting from the mutual dependencies of graphite weight loss and nuclear energy deposition.

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Dosimetry Assessments for the Reactor Pressure Vessel and Core Barrel in UK Pressurized Water Reactor (PWR) Plant

Thornton

Allen

Huggon

et al. 2012

Journal of ASTM International

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Specimens for the Sizewell B reactor pressure vessel (RPV) in-service steels surveillance program are irradiated inside eight capsules located within the reactor pressure vessel and loaded prior to commissioning. The periodic removal of these capsules and testing of their contents provides material properties data at intervals during the lifetime of the plant. Neutron activation measurements and radiation transport calculations play an essential role in assessing the neutron exposure of the specimens and RPV. Following the most recent withdrawal, seven capsules have now been removed covering nine cycles of reactor operation. This paper summarizes the dosimetry results of the Sizewell B surveillance program obtained to date. In addition to an overview of the calculational methodology it includes a review of the measurements. Finally, it describes an extension of the methodology to provide dosimetry recommendations for the core barrel and briefly discusses the results that were obtained.

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Reactor Pressure Vessel Neutron Dosimetry Assessments for UK PWR Plant

Cited by 8 publications

References 0 publications

The Activation Detector Activity Calculations Using the Effective Source Method and Measurement

The Activation Detector Activity Calculations Using the Effective Source Method and Measurement

A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors

Dosimetry Assessments for the Reactor Pressure Vessel and Core Barrel in UK Pressurized Water Reactor (PWR) Plant

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