h1

TY  - THES
AU  - Volmert, Benjamin
TI  - Plutoniumfingerabdrücke und Brennstoffzyklusstudien für thermische Reaktorkonzepte
CY  - Aachen
PB  - Publikationsserver der RWTH Aachen University
M1  - RWTH-CONV-208162
SP  - IV, 140 S. : graph. Darst.
PY  - 2003
N1  - Prüfungsjahr: 2003. - Publikationsjahr: 2004
N1  - Aachen, Techn. Hochsch., Diss., 2003
AB  - The nuclide build-up mechanism of long-lived actinides for thermal reactor concepts and different fuel cycles are investigated by using the reactor simulation code VSOP. The fuel cycles of LEU (Low-Enriched Uranium), MOX (Mixed Oxide Fuel), ThHEU (Thorium High-Enriched Uranium) and ThPu (Thorium-Plutonium) as well as the reactor concepts of LWR, MAGNOX, CANDU, RBMK and HTR are considered within this thesis. For each combination of fuel and reactor type an individual VSOP reactor core burn-up model is developed. By these burn-up models it is possible to simulate the heavy metal build-up history - averaged over the core - of each reactor concept. The nuclide inventory analysis of the different fuel assemblies after discharge is performed with regard to the question whether the Plutonium(Pu)-vector of the burned fuel would prove to be a characteristic "fingerprint" of both the originating fuel cycle and the underlying reactor concept. The results of the investigation lead to the fact that the Pu-vector is indeed reactor specific not only at the end of the normal burn-up but even during the whole burn-up process inside the reactor core. Finally, a methodology to investigate a Pu-vector of unknown origin and to prove a potential relation to a certain reactor concept is developed. The methodology is successfully verified by the calculated discharged nuclide vectors of the simulated concepts as well as by nuclide vectors found in the literature. Thus, it is possible to exclude a questionable relation of a given Pu-vector to the majority of existing reactor concepts or even - at best - to determine with a certain probability its specific origin (i. e. the parent reactor concept).
KW  - Kernreaktor (SWD)
KW  - Abbrand <Kerntechnik> (SWD)
KW  - Prozessimulation (SWD)
KW  - Abgebrannter Kernbrennstoff (SWD)
KW  - Actinoide (SWD)
KW  - Radionuklid (SWD)
KW  - Zusammensetzung (SWD)
KW  - Plutoniumisotop (SWD)
KW  - Isotopenh (SWD)
LB  - PUB:(DE-HGF)11
DO  - DOI:10.18154/RWTH-CONV-208162
UR  - https://publications.rwth-aachen.de/record/59378
ER  -