The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4In 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...
The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting ...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...
AbstractIn the development of JENDL-4.0, the thermal and resonance capture cross section of 241Am wa...
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
Proposal: Radiative capture on 242Pu for MOX fuel reactorsThe use of MOX fuel (mixed-oxide fuel made...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
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 ...
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 ...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
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 ...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...
AbstractIn the development of JENDL-4.0, the thermal and resonance capture cross section of 241Am wa...
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the...
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined ...
Proposal: Radiative capture on 242Pu for MOX fuel reactorsThe use of MOX fuel (mixed-oxide fuel made...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
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 ...
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 ...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
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 ...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...