Status of reliability in determining SDDR for manual maintenance activities in ITER: Quality assessment of relevant activation cross sections involved

García, Raquel; García, Manuel García; Pampin, R.; Sanz, J.

doi:10.1016/j.fusengdes.2016.08.016

Cited by 4 publications

(11 citation statements)

References 10 publications

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“…Finally, Sect. 5 summarizes the main conclusions jointly considering previous [11] and present work, emphasizing the percentage of the SDDR calculated with validated XS, for each of the materials.…”

Section: Introductionmentioning

confidence: 72%

“…The above-listed materials are subjected to reference neutron spectra from both PC and PI. Such neutron flux spectra and the compositions for the different materials are described in [11]. Secondly, the quality of each of the XS is analyzed following the EAF procedure for validating and testing the successive versions since 2001.…”

Section: Methodsmentioning

confidence: 99%

“…The aim is to extend this study providing a more complete list of dominant nuclides and pathways. Also, in [11] the sum of the different nuclide contributions to the SDDR produced by the activation of each of the considered materials was, in the worst case 86% and in most of the cases above 90%; now, a sum of 95% is achieved for the worst case and, in most of the cases, above 98%. Finally, Sect.…”

Section: Introductionmentioning

confidence: 91%

“…a e-mail: rgarciam@ind.uned.es Section 2 describes the methodology procedure used. Section 3 is devoted to compile and systematize previous work carried out in this field [11], where relevant XS pathways for the production of those radionuclides responsible of >4% of the SDDR (produced by the activation of each of the considered materials), were taken into account. Section 4 goes in depth into the XS for the pathways leading to radionuclides contributing 1-4% to the SDDR produced by the activation of each particular material.…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Reliability of activation cross sections for estimation of shutdown dose rate in the ITER port cell and port interspace

García

Ogando

et al. 2017

EPJ Web Conf.

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Abstract. This paper explores the quality of available activation cross section (XS) data for accurate Shutdown Dose Rate (SDDR) prediction in the ITER Port Cell and Port Interspace areas, where different maintenance activities are foreseen. For this purpose the EAF library (2007 and 2010 versions) has been investigated, as it is typically used by the ITER community.Based on both reports/papers on SDDR in ITER and own calculations, major nuclides contributing to the SDDR coming from the activation of i) relevant materials placed in ITER and ii) candidate materials for the bioshield plug as L2N and barite concretes, are identified. Then, relevant production pathways are obtained.EAF XS quality for all pathways is checked following the procedure used for validating and testing the successive EAF versions. Also, possible improvements from using the TENDL-2015 library are assessed by comparing EAF and TENDL XS with available differential experimental data from EXFOR. Results point out that most of the activation XS related to materials currently placed in ITER are reliable, and only a few need improvement. Also, many of the XS related to both L2N and barite concretes need further work for validation.

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Section: Introductionmentioning

confidence: 72%

Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 91%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Reliability of activation cross sections for estimation of shutdown dose rate in the ITER port cell and port interspace

García

Ogando

et al. 2017

EPJ Web Conf.

View full text Add to dashboard Cite

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“…Previously to this paper, we have evaluated the reliability of the relevant activation cross-sections for the calculation of the Shutdown Dose Rate (SDDR) in ITER (International Thermonuclear Experimental Reactor) [1,2].…”

Section: Introductionmentioning

confidence: 99%

Study of concrete activation with IFMIF-like neutron irradiation: Status of EAF and TENDL neutron activation cross-sections

et al. 2017

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Abstract. The aim of this paper is to check the performance of last versions of EAF and TENDL libraries (EAF2007, EAF2010, and TENDL2014) in the prediction of concrete activation under the neutron irradiation environment expected in IFMIF, an accelerator-based neutron source conceived for fusion materials testing. For this purpose Activity and dose rate responses of three types of concrete (ITER-Bioshield kind, barite and magnetite concretes) have been studied.For these quantities, dominant nuclides and production pathways have been determined and, then, a qualitative analysis of the relevant activation cross-sections involved has been performed by comparing data from mentioned libraries with experimental data from EXFOR database.Concrete activation studies have been carried out with IFMIF-like neutron irradiation conditions using the ACAB code and EAF and TENDL libraries. The cooling times assessed are related to safety and maintenance operations, specifically 1 hour, 1 day and 12 days. Final conclusions are focused on the recommendations for the activation library to be used among those analyzed and cross-section data to be improved.

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Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket

Palermo

García

et al. 2017

Fusion Engineering and Design

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Status of reliability in determining SDDR for manual maintenance activities in ITER: Quality assessment of relevant activation cross sections involved

Cited by 4 publications

References 10 publications

Reliability of activation cross sections for estimation of shutdown dose rate in the ITER port cell and port interspace

Reliability of activation cross sections for estimation of shutdown dose rate in the ITER port cell and port interspace

Study of concrete activation with IFMIF-like neutron irradiation: Status of EAF and TENDL neutron activation cross-sections

Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket

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