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Studier av acceleratordrivna system för transmutation av kärnavfall
- Publication Year :
- 2006
- Publisher :
- Institutionen för kärn- och partikelfysik, 2006.
-
Abstract
- Accelerator-driven systems for transmutation of nuclear waste have been suggested as a means for dealing with spent fuel components that pose potential radiological hazard for long periods of time. While not entirely removing the need for underground waste repositories, this nuclear waste incineration technology provides a viable method for reducing both waste volumes and storage times. Potentially, the time spans could be diminished from hundreds of thousand years to merely 1.000 years or even less. A central aspect for accelerator-driven systems design is the prediction of safety parameters and fuel economy. The simulations performed rely heavily on nuclear data and especially on the precision of the neutron cross section representations of essential nuclides over a wide energy range, from the thermal to the fast energy regime. In combination with a more demanding neutron flux distribution as compared with ordinary light-water reactors, the expanded nuclear data energy regime makes exploration of the cross section sensitivity for simulations of accelerator-driven systems a necessity. This fact was observed throughout the work and a significant portion of the study is devoted to investigations of nuclear data related effects. The computer code package EA-MC, based on 3-D Monte Carlo techniques, is the main computational tool employed for the analyses presented. Directly related to the development of the code is the extensive IAEA ADS Benchmark 3.2, and an account of the results of the benchmark exercises as implemented with EA-MC is given. CERN's Energy Amplifier prototype is studied from the perspectives of neutron source types, nuclear data sensitivity and transmutation. The commissioning of the n_TOF experiment, which is a neutron cross section measurement project at CERN, is also described.
- Subjects :
- Nuclear physics
burnup
accelerator-driven systems
FLUKA
Subatomär fysik
benchmark
sensitivity analysis
EADF
Subatomic Physics
fission products
MCNP
spallation target
cross section measurement
Monte Carlo simulation
nuclear waste
actinides
EA-MC
Energy Amplifier
neutron cross sections
subcritical reactors
transmutation
nuclear data
neutron time-of-flight
TRADE
neutron source
n_TOF experiment
Kärnfysik
MCNP-X
Subjects
Details
- Language :
- English
- Database :
- OpenAIRE
- Accession number :
- edsair.dedup.wf.001..595dc76249172f2164e99840bbc14ca8