Zeitliche Entwicklung der Radiotoxizität
PUREX-Verfahren
(Plutonium and Uranium extraction)
Fizeau, 11 kt, Oberfläche
http://www.cddc.vt.edu/host/atomic/images/fizeau1b.jpg Nevada Test Site, 14.Sep.1957
Langlebige Spaltprodukte
Nuklid t
1/2(ka) Ausbeute (%) σ (barn)
Tc-99 211 6,14 23
Sn-126 235 0,11
Se-79 480 0,04
Zr-93 1610 5,46 <4
Cs-135 2300 6,91 8,3
Pd-107 6500 1,25 1,8
I-129 15700 0,84 31
Relevante minore Aktiniden
Nuklid t
1/2(ka) σ (barn) σ
f(barn)
Np-237 2144 170 0,020
Am-241 0,432 700 3,15
Am-242m 0,141 1700 5900
Am-243 7,37 80 0,0079
Cm-242 0,00045 20 5
Cm-244 0,0181 15 1,1
Cm-245 8,5 350 2100
σ : Wirkungsquerschnitt für Neutroneneinfang (thermische Neutronen)
σ
f: Wirkungsquerschnitt für Spaltung (thermische Neutronen)
MYRRHA: Multi-purpose hybrid research reactor for high-tech
applications
(Multi-purpose hYbrid Research Reactor for High-tech Applications)
SCK•CEN, the Belgian Nuclear Research Centre in Mol has been working for several years on the design of a multi-purpose irradiation facility in order to replace the ageing BR2 reactor, a multi- functional materials testing reactor (MTR), in operation since 1962.
MYRRHA, a flexible fast spectrum research reactor (50-100 MWth) is conceived as an accelerator driven system (ADS), able to operate in sub-critical and critical modes. It contains a proton accelerator of 600 MeV, a spallation target and a multiplying core with MOX fuel, cooled by liquid lead-bismuth (Pb-Bi).
Agenda of implementation
MYRRHA will be operational at full power around 2025. During the 2010-2014 period the following items will be accomplished:
•
The Front End Engineering Design (FEED) and the associated R&D programme.
•
The licensing process.
•
The set‐up of the international consortium.
Construction of the facility and assembly of the components is foreseen in the period 2017-2021.
Three years (2022-2024) are foreseen for the full commissioning of the facility. The total investment cost is currently estimated at M€ 960 (€ 2009).