Published May 26, 2016 | Version v1
Miscellaneous Open

Process-level modelling related to geological disposal of the spent nuclear fuel

Creators

  • 1. Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Bratislava (Slovakia)

Description

In this paper, the concentration profiles in a bentonite block calculated by the simulation tool GoldSim were verified through comparison to an analytical solution of non-steady state diffusion equation which was derived based on the certain initial and boundary conditions. The impact of bentonite buffer discretization on the release rates (from the near field) of modelled radionuclides was also evaluated. The size of discretization has influenced mainly the release rate of 242Pu which is highly sorptive radionuclide. In this case the simulation tool GoldSim was also used. (authors)

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Part of:
Proceedings of the 22nd International Conference on Applied Physics of Condensed Matter (APCOM 2016)

Additional details

Identifiers

URL
http://kf.elf.stuba.sk/~apcom/apcom16/proceedings/;

Publishing Information

Publisher
Slovak University of Technology
Imprint Place
Bratislava (Slovakia)
ISBN
978-80-227-4572-7
Imprint Title
Proceedings of the 22nd International Conference on Applied Physics of Condensed Matter (APCOM 2016)
Imprint Pagination
366 p.
Journal Page Range
p. 121-125
Report number
INIS-SK--2018-014

Conference

Title
22. International Conference on Applied Physics of Condensed Matter
Acronym
APCOM 2016
Dates
22-24 Jun 2016
Place
Strbske Pleso (Slovakia)

INIS

Country of Publication
Slovakia
Country of Input or Organization
Slovakia
INIS RN
49052638
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BENTONITE; CHLORINE 36; COMPUTERIZED SIMULATION; DIFFUSION BARRIERS; DIFFUSION EQUATIONS; EXPERIMENTAL DATA; PLUTONIUM 242; RADIOACTIVE WASTE DISPOSAL; RADIONUCLIDE MIGRATION; RADIUM 226; SPENT FUEL STORAGE; SPENT FUELS; THERMAL DIFFUSION; UNDERGROUND DISPOSAL
Descriptors DEC
ACTINIDE NUCLEI; ALKALINE EARTH ISOTOPES; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BETA-PLUS DECAY RADIOISOTOPES; CARBON 14 DECAY RADIOISOTOPES; CHLORINE ISOTOPES; CLAYS; DATA; DIFFERENTIAL EQUATIONS; DIFFUSION; ELECTRON CAPTURE RADIOISOTOPES; ENERGY SOURCES; ENVIRONMENTAL TRANSPORT; EQUATIONS; EVEN-EVEN NUCLEI; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; INFORMATION; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; ISOTOPES; LIGHT NUCLEI; MANAGEMENT; MASS TRANSFER; MATERIALS; MINERALS; NUCLEAR FUELS; NUCLEI; NUMERICAL DATA; ODD-ODD NUCLEI; PARTIAL DIFFERENTIAL EQUATIONS; PLUTONIUM ISOTOPES; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; RADIUM ISOTOPES; REACTOR MATERIALS; SILICATE MINERALS; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; STORAGE; WASTE DISPOSAL; WASTE MANAGEMENT; YEARS LIVING RADIOISOTOPES

Optional Information

Contract/Grant/Project number
Grant VEGA-1/0796/13
Notes
1 tab., 4 figs., 4 refs. Imprint:Published also on CDROM 44 MBytes in PDF format