[en] The fissile mass in radioactive waste drums filled with compacted metallic residues (spent fuel hulls and nozzles) produced at AREVA NC La Hague reprocessing plant is measured by neutron interrogation with the Differential Die-away measurement Technique (DDT). In the next years, old hulls and nozzles mixed with Ion-Exchange Resins will be measured. The ion-exchange resins increase neutron moderation in the matrix, compared to the waste measured in the current process. In this context, the Nuclear Measurement Laboratory (LMN) of CEA Cadarache has studied a matrix effect correction method, based on a drum monitor, namely a 3He proportional counter located inside the measurement cavity. After feasibility studies performed with LMN's PROMETHEE 6 laboratory measurement cell and with MCNPX simulations, this paper presents first experimental tests performed on the industrial ACC (hulls and nozzles compaction facility) measurement system. A calculation vs. experiment benchmark has been carried out by performing dedicated calibration measurements with a representative drum and "2"3"5U samples. The comparison between calculation and experiment shows a satisfactory agreement for the drum monitor. The final objective of this work is to confirm the reliability of the modeling approach and the industrial feasibility of the method, which will be implemented on the industrial station for the measurement of historical wastes. (authors)

[en] Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the "1"3"7Cs and "1"3"4Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a "1"3"7Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional "3He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

[en] Radioactive waste drums filled with compacted metallic residues (spent fuel hulls and nozzles) produced at AREVA La Hague reprocessing plant are measured by neutron interrogation with the Differential Die-away measurement Technique (DDT). The purpose is to assay fissile material quantities present in radioactive waste packages. In the future, old hulls and nozzles containing Ion-Exchange Resin (IER) will be measured. IERs provide moderating properties to the matrix, not encountered during the current measurement. In this context, the Nuclear Measurement Laboratory (NML) of the CEA Cadarache has been asked by AREVA NC to explore the possibility of implementing a matrix effect correction method, based on internal monitor (³He proportional counter) signal correlated to the matrix effect. In order to validate this method, a benchmark was performed with PROMETHEE 6 R and D measurement cell at the NML, with a similar cavity configuration to that of the industrial station. An experience design on two main factors regarding the matrix effect (absorbing and moderating ratios) has been studied. Considering the variation range of both factors for old waste measurement, 5 test matrices have been defined. They have been measured in PROMETHEE 6 and simulated using the particle transport code MCNP. Tests have been carried out experimentally using ²³⁵U platelets. Results show that the experimental internal monitor is sensitive to the matrix but not to the fissile material presence and location. In addition, differences between experiment and model are satisfactory (<10%), in terms of prompt calibration coefficient (useful signal of fissile materials) and internal monitor signal, considering the complexity of the measurement method and numerical model, and the large range of moderator and absorption ratios. The relationship between the prompt calibration coefficient and the internal monitor signal observed in PROMETHEE 6, both for experience and model, can be fitted with a similar function as the industrial measurement cell, the correlation of which being established by numerical simulation. Regressions from experimental and modelling are almost superimposed. (authors)