Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay

Research output: Report/bookER - External report

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Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay. / Yu, Li; Weetjens, Eef.

Studiecentrum voor Kernenergie, 2016. 40 p. (SCK•CEN Reports; No. ER-294).

Research output: Report/bookER - External report

Bibtex - Download

@book{2f658ee5bf214a21a26636f60f6283e7,
title = "Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay",
abstract = "This report focuses on the modelling assumptions of radionuclide release from a spent fuel (SF) repository from performance assessment (PA) point of view. Radionuclides dissolved in the crystalline UO2 grains of the spent fuel matrix constitute the vast majority of the radionuclide source term and their release will be governed by the matrix dissolution rate. In previous PA studies, fuel matrix dissolution is modelled as a predefined constant-rate process, i.e, all the radionuclides (RNs) are released from the matrix at the same constant rate as the fuel matrix dissolution rate, followed by an independent transport process of RNs which can be solubility limited.",
keywords = "spent fuel, modelling assumptions, radionuclide release, performance assessment",
author = "Li Yu and Eef Weetjens",
note = "Score=2",
year = "2016",
month = "1",
day = "1",
language = "English",
series = "SCK•CEN Reports",
publisher = "Studiecentrum voor Kernenergie",
number = "ER-294",

}

RIS - Download

TY - BOOK

T1 - Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay

AU - Yu, Li

AU - Weetjens, Eef

N1 - Score=2

PY - 2016/1/1

Y1 - 2016/1/1

N2 - This report focuses on the modelling assumptions of radionuclide release from a spent fuel (SF) repository from performance assessment (PA) point of view. Radionuclides dissolved in the crystalline UO2 grains of the spent fuel matrix constitute the vast majority of the radionuclide source term and their release will be governed by the matrix dissolution rate. In previous PA studies, fuel matrix dissolution is modelled as a predefined constant-rate process, i.e, all the radionuclides (RNs) are released from the matrix at the same constant rate as the fuel matrix dissolution rate, followed by an independent transport process of RNs which can be solubility limited.

AB - This report focuses on the modelling assumptions of radionuclide release from a spent fuel (SF) repository from performance assessment (PA) point of view. Radionuclides dissolved in the crystalline UO2 grains of the spent fuel matrix constitute the vast majority of the radionuclide source term and their release will be governed by the matrix dissolution rate. In previous PA studies, fuel matrix dissolution is modelled as a predefined constant-rate process, i.e, all the radionuclides (RNs) are released from the matrix at the same constant rate as the fuel matrix dissolution rate, followed by an independent transport process of RNs which can be solubility limited.

KW - spent fuel

KW - modelling assumptions

KW - radionuclide release

KW - performance assessment

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/12057003

M3 - ER - External report

T3 - SCK•CEN Reports

BT - Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom Clay

PB - Studiecentrum voor Kernenergie

ER -

ID: 878997