The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified the MOX fuel manufacturing process as an area in which there is a need for additional integral benchmark data. The specific need focused on damp MOX powders. The WPNCS was ultimately asked by the NEA Nuclear Science Committee (NSC) to provide the framework for the selection and performance of new experiments that fill the identified need. A set of criteria was established to enable uniform comparison of experimental proposals with generic MOX application data. Criteria were established for five general characteristics: (1) neutronic parameters, (2) type of experiments, (3) financial aspects, (4) schedule, and (5) other considerations. Proposa...
Fast reactor driver fuels are based on MOX with a high Pu content. They can be prepared by classical...
One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high...
The international Expert Group on Reactor-Based Plutonium Disposition (TFRPD) has been established a...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
International audienceIn the framework of the WPNCS Expert Group on Uncertainty Analysis for Critica...
International audienceMolybdenum plays an important role in nuclear criticality-safety as it is a fi...
Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a bu...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
Reducing the number of actinide separation streams in a spent fuel recovery process would reduce the...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC) expe...
The applicability of proposed critical experiments for the criticality code validation of a series o...
International audienceAn important RandD program on reprocessing of MOX nuclear fuels is on-going at...
This paper presents a new method for calculating the burnup of nuclear reactor fuel, the MCWO-MS met...
Fast reactor driver fuels are based on MOX with a high Pu content. They can be prepared by classical...
One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high...
The international Expert Group on Reactor-Based Plutonium Disposition (TFRPD) has been established a...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
International audienceIn the framework of the WPNCS Expert Group on Uncertainty Analysis for Critica...
International audienceMolybdenum plays an important role in nuclear criticality-safety as it is a fi...
Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a bu...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
Reducing the number of actinide separation streams in a spent fuel recovery process would reduce the...
Simulations were performed using ORIGEN-ARP to investigate ¹³⁷Cs and ¹⁰⁶Ru-¹⁰⁶Rh as suitable fission...
In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC) expe...
The applicability of proposed critical experiments for the criticality code validation of a series o...
International audienceAn important RandD program on reprocessing of MOX nuclear fuels is on-going at...
This paper presents a new method for calculating the burnup of nuclear reactor fuel, the MCWO-MS met...
Fast reactor driver fuels are based on MOX with a high Pu content. They can be prepared by classical...
One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high...
The international Expert Group on Reactor-Based Plutonium Disposition (TFRPD) has been established a...