| Hauptseite > Publikationsdatenbank > Neutronenphysikalische und thermohydraulische Untersuchungen zur Spaltstoffproduktion mit Spallationsneutronen |
| Book/Report | FZJ-2018-02262 |
1983
Kernforschungsanlage Jülich, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/17964
Report No.: Juel-1835
Abstract: In case of an enhanced utilisation of nuclear energy from fission reactors it is necessary to preserve the natural deposits of fissile material. One possibility for this preservation could be the breeding of synthetic fuel by the means of spallation neutrons. The configuration discussed here consists of an integral spallation target/breeding blanket pebble bed of hollow Thorium spheres, which is cooled alternatively with helium gas or liquid sodium or lithium. With helium cooling the neutron yield is 35 neutrons par initial proton and the breeding gain is 775 kg U-233/a . With sodium as coolant the n-yield is 25 n/p, and the fuel production is520 kg U-233/a . lf liquid lithium is used as coolant the neutron yield is 30 n/p with a production of 440 kg Uranium-233 per year. Supposing a fuel requirement of a high converting HTR of 90 kg U-233/GW$_{e}$ -a, 5 to 9 1-GW$_{e}$-reactors could be supplied depending an tRe coolant
|
The record appears in these collections: |