Source term assessment: The ARIANE programme

Marc Lippens; Danièle Boulanger; Jacques Basselier; Stefaan Van Winckel; Beat Wernli; Maria Betti

doi:10.1115/ICEM2001-1191

Source term assessment: The ARIANE programme

Marc Lippens, Danièle Boulanger, Jacques Basselier, Stefaan Van Winckel, Beat Wernli, Maria Betti

Research output › peer-review

Abstract

The prediction of the source term of actinides, fission and activation products is of major importance in numerous nuclear fields. An experimental programme of radiochemistry (called ARIANE) was carried out on MOX and UO ₂ fuels irradiated in PWR and BWR conditions, reaching burnups of 35 up to 55 GWd/tM. Besides the providing of a large set of experimental data on the irradiated fuel inventory, a second objective of the programme was to confer on these experimental results reliable and minimised uncertainties. About 50 isotopes of actinides and fission products were selected. Their contents were measured using techniques as TIMS, ICP-MS, alpha, beta and gamma spectrometry. The measurement results were crosschecked by three highly qualified laboratories and recommended values were provided after extended analysis and confrontation of the results. For most of the measured isotopes, the target uncertainties were reached and even reduced, providing a unique database for irradiated fuel characterisation and for code qualification.

Original language	English
Title of host publication	Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM
Publisher	ASME - The American Society of Mechanical Engineers
Pages	1075-1080
Number of pages	6
DOIs	https://doi.org/10.1115/ICEM2001-1191
State	Published - Sep 2001
Event	2001 - 8th International Conference on Radioactive Waste Management and Environmental Remediation - Bruges Duration: 30 Sep 2001 → 4 Oct 2001

Conference

Conference	2001 - 8th International Conference on Radioactive Waste Management and Environmental Remediation
Country/Territory	Belgium
City	Bruges
Period	2001-09-30 → 2001-10-04

ASJC Scopus subject areas

Safety, Risk, Reliability and Quality
Energy Engineering and Power Technology
Waste Management and Disposal

Access to Document

10.1115/ICEM2001-1191License: Unspecified

Cite this

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title = "Source term assessment: The ARIANE programme",

abstract = "The prediction of the source term of actinides, fission and activation products is of major importance in numerous nuclear fields. An experimental programme of radiochemistry (called ARIANE) was carried out on MOX and UO 2 fuels irradiated in PWR and BWR conditions, reaching burnups of 35 up to 55 GWd/tM. Besides the providing of a large set of experimental data on the irradiated fuel inventory, a second objective of the programme was to confer on these experimental results reliable and minimised uncertainties. About 50 isotopes of actinides and fission products were selected. Their contents were measured using techniques as TIMS, ICP-MS, alpha, beta and gamma spectrometry. The measurement results were crosschecked by three highly qualified laboratories and recommended values were provided after extended analysis and confrontation of the results. For most of the measured isotopes, the target uncertainties were reached and even reduced, providing a unique database for irradiated fuel characterisation and for code qualification.",

keywords = "MOX, Spent fuel, Gamma ray spectrometry, Spent nuclear fuel",

author = "Marc Lippens and Dani{\`e}le Boulanger and Jacques Basselier and {Van Winckel}, Stefaan and Beat Wernli and Maria Betti",

year = "2001",

month = sep,

doi = "10.1115/ICEM2001-1191",

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pages = "1075--1080",

booktitle = "Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM",

publisher = "ASME - The American Society of Mechanical Engineers",

address = "United States",

note = "2001 - 8th International Conference on Radioactive Waste Management and Environmental Remediation ; Conference date: 30-09-2001 Through 04-10-2001",

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Lippens, M, Boulanger, D, Basselier, J, Van Winckel, S, Wernli, B & Betti, M 2001, Source term assessment: The ARIANE programme. in Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM. ASME - The American Society of Mechanical Engineers, pp. 1075-1080, 2001 - 8th International Conference on Radioactive Waste Management and Environmental Remediation, Bruges, Belgium, 2001-09-30. https://doi.org/10.1115/ICEM2001-1191

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T2 - 2001 - 8th International Conference on Radioactive Waste Management and Environmental Remediation

AU - Lippens, Marc

AU - Boulanger, Danièle

AU - Basselier, Jacques

AU - Van Winckel, Stefaan

AU - Wernli, Beat

AU - Betti, Maria

PY - 2001/9

Y1 - 2001/9

N2 - The prediction of the source term of actinides, fission and activation products is of major importance in numerous nuclear fields. An experimental programme of radiochemistry (called ARIANE) was carried out on MOX and UO 2 fuels irradiated in PWR and BWR conditions, reaching burnups of 35 up to 55 GWd/tM. Besides the providing of a large set of experimental data on the irradiated fuel inventory, a second objective of the programme was to confer on these experimental results reliable and minimised uncertainties. About 50 isotopes of actinides and fission products were selected. Their contents were measured using techniques as TIMS, ICP-MS, alpha, beta and gamma spectrometry. The measurement results were crosschecked by three highly qualified laboratories and recommended values were provided after extended analysis and confrontation of the results. For most of the measured isotopes, the target uncertainties were reached and even reduced, providing a unique database for irradiated fuel characterisation and for code qualification.

AB - The prediction of the source term of actinides, fission and activation products is of major importance in numerous nuclear fields. An experimental programme of radiochemistry (called ARIANE) was carried out on MOX and UO 2 fuels irradiated in PWR and BWR conditions, reaching burnups of 35 up to 55 GWd/tM. Besides the providing of a large set of experimental data on the irradiated fuel inventory, a second objective of the programme was to confer on these experimental results reliable and minimised uncertainties. About 50 isotopes of actinides and fission products were selected. Their contents were measured using techniques as TIMS, ICP-MS, alpha, beta and gamma spectrometry. The measurement results were crosschecked by three highly qualified laboratories and recommended values were provided after extended analysis and confrontation of the results. For most of the measured isotopes, the target uncertainties were reached and even reduced, providing a unique database for irradiated fuel characterisation and for code qualification.

KW - MOX

KW - Spent fuel

KW - Gamma ray spectrometry

KW - Spent nuclear fuel

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