Boiling water fuel element loop in FRJ-2
Boiling water fuel element loop in FRJ-2
An irradiation facility, more of a capsule than a loop, has been developed to test rod type fuel elements under pressurized boiling water conditions. An arrangement of small discs inside the in-pile pressure vessel maintain surface boiling conditions along the fuel rod and the nuclear heat is transp...
| Personal Name(s): | Neumann, M. |
|---|---|
| Reichardt, K. / Münchow, K. / Bundesmann, G. / Dehe, P. / Lehrheuer, W. | |
| Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
| Imprint: |
Jülich
Kernforschungsanlage Jülich, Verlag
1966
|
| Physical Description: |
6 p. |
| Document Type: |
Report Book |
| Research Program: |
ohne Topic |
| Series Title: |
Berichte der Kernforschungsanlage Jülich
373 |
| Link: |
OpenAccess OpenAccess |
| Publikationsportal JuSER |
|
An irradiation facility, more of a capsule than a loop, has been developed to test rod type fuel elements under pressurized boiling water conditions. An arrangement of small discs inside the in-pile pressure vessel maintain surface boiling conditions along the fuel rod and the nuclear heat is transported to the surrounding wall of the vessel. The heat is removed by low pressure low temperature secondary cooling water flowing over the pressure vessel through the outer tubes, enabling the two inch diameter in-pile section to be made in aluminium alloy thus giving very low neutron flux depression and reactivity absorption. Laboratory rneasurements exhibit high burnout lirnits and close relation between rod surface temperature and pressure. Because of the in-pile heat exchange to secondary low pressure water the out of pile equipment serves only for control and rneasurement and for meeting safety demands. Two loops of this type, different in design pressure, are just installed in the FRJ-2. |