AbstractIn the development of JENDL-4.0, the thermal and resonance capture cross section of 241Am was increased by about 8-9% to reduce the overestimation of criticality observed in the MOX-Fueled light-water-moderated cores using 241Am-rich plutonium-fuel.The revised data gives the better results of criticality prediction for those cores than that with JENDL-3.3. The Pu ageing problem was also investigated using the revised data. This problem is that the calculated k-effs for critical MOX cores with different experiment dates showed the tendency of increase with time. The change of k-eff in seven years was about 0.2%dk/k with JENDL-3.3 and it was reduced to about 0.1%dk/k with JENDL-4.0. These results show that the revision of 241Am captur...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting ...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...
The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4In the development of...
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the...
Proposal: Radiative capture on 242Pu for MOX fuel reactorsThe use of MOX fuel (mixed-oxide fuel made...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
International audienceMolybdenum plays an important role in nuclear criticality-safety as it is a fi...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting ...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...
The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4In the development of...
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the...
Proposal: Radiative capture on 242Pu for MOX fuel reactorsThe use of MOX fuel (mixed-oxide fuel made...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
International audienceMolybdenum plays an important role in nuclear criticality-safety as it is a fi...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting ...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...