Comparative Measures of Radionuclide Containment in the Crystalline Geophere
Creators
- 1. Royal Institute of Technology (Sweden)
- 2. Southwest Research Institute (United States)
- 3. Swedish Nuclear Fuel and Waste Management Company (Sweden)
Description
A probabilistic model for assessing the capacity of a fractured crystalline rock volume to contain radionuclides is developed. The rock volume is viewed as a network of discrete fractures through which radionuclides are transported by flowing water. Diffusive mass transfer between the open fractures and the stagnant water in the pore space of the rock matrix allow radionuclides access to mineral grains where physical and chemical processes - collectively known as sorption - can retain radionuclides. A stochastic Lagrangian framework is adopted to compute the probability that a radionuclide particle will be retained by the rock, i.e., the probability that it will decay before being released from the rock volume. A dimensionless quantity referred to as the 'containment index' is related to this probability and proposed as a suitable measure for comparing different rock volumes; such a comparative measure may be needed, for example, in a site selection program for geological radioactive waste disposal. The probabilistic solution of the transport problem is based on the statistics of two Lagrangian variables: τ, the travel time of an imaginary tracer moving with the flowing water, and β, a suitably normalized surface area available for retention. Statistics of τ and β may be computed numerically using site-specific discrete fracture network simulations. Fracture data from the well-characterized Aespoe Hard Rock Laboratory site in southern Sweden are used to illustrate the implementation of the proposed containment index for six radionuclides (126Sn, 129I, 135Cs, 237Np, 239Pu, and 79Se). It is found that fractures of small aperture imply prolonged travel times and hence long tails in both beta and tau. This, in turn, enhances retention and is favorable from a safety assessment perspective
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 142
- Journal Issue
- 3
- Journal Page Range
- p. 292-304
- ISSN
- 0029-5639
- CODEN
- NSENAO
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37106981
- Subject category
- S58: GEOSCIENCES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CESIUM 135; CONTAINMENT; FRACTURES; IGNEOUS ROCKS; IODINE 129; METAMORPHIC ROCKS; PLUTONIUM 239; PROBABILISTIC ESTIMATION; PROBABILITY; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; RISK ASSESSMENT; SELENIUM 79; SITE SELECTION; SURFACE AREA; TIN 126; WATER
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CESIUM ISOTOPES; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FAILURES; HEAVY NUCLEI; HYDROGEN COMPOUNDS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IODINE ISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MINUTES LIVING RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; PLUTONIUM ISOTOPES; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; ROCKS; SELENIUM ISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; SURFACE PROPERTIES; TIN ISOTOPES; WASTE DISPOSAL; WASTE MANAGEMENT; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/