The results of in-pile irradiation tests of PWR fuel materials with particular regard to the chemical and radiochemical aspects are reported. These tests were conducted to study the difference of fission product release from defected fuel specimens containing UO/sub 2/ fuel materials of two different specific densities; also, one test included a comparatively high oxygen concentration in the loop water to study the effect of an accidental oxygen addition on the rate of fission product release. No firm deduction could be drawn as to the effect of different fuel densities on the emanation of fission products from defected specimens, and the high oxygen concentration had practically no effect on the rate of fission product release. (auth
A series of fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Hald...
The Materials Management and Minimization (M3) Program intends to qualify a new high‑density low‑enr...
During normal operation, some parts of the fission product in the defective fuel rods can release in...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
In this irradiation test, the performance safety of (Th,Pu)O2 fuel was evaluated. The fuel pellets w...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
International audienceOne objective of the FPT2 test of the PHEBUS FP Program was to study the degra...
Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, an...
Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing h...
International audienceExperiments on nuclear fuels and materials in MTRs are a mandatory step for su...
The objective of this work is to experimentally investigate the effect of the oxygen potential on th...
International audienceThe present study describes the in-situ electrochemical modifications which af...
A series of fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Hald...
The Materials Management and Minimization (M3) Program intends to qualify a new high‑density low‑enr...
During normal operation, some parts of the fission product in the defective fuel rods can release in...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
In this irradiation test, the performance safety of (Th,Pu)O2 fuel was evaluated. The fuel pellets w...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
A commercial PWR fuel sample with a local burn-up of about 240 MWd/kgHM was annealed in a Knudsen ce...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
International audienceOne objective of the FPT2 test of the PHEBUS FP Program was to study the degra...
Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, an...
Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing h...
International audienceExperiments on nuclear fuels and materials in MTRs are a mandatory step for su...
The objective of this work is to experimentally investigate the effect of the oxygen potential on th...
International audienceThe present study describes the in-situ electrochemical modifications which af...
A series of fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Hald...
The Materials Management and Minimization (M3) Program intends to qualify a new high‑density low‑enr...
During normal operation, some parts of the fission product in the defective fuel rods can release in...