INDUSTRIAL EXPERIENCE ON RECOVERY AND
DECONTAMINATION OF ALPHA WASTE - UCD

M-F. Debreuille, A. Lavenu, B. Kniebihli
COGEMA
2-4 rue Paul Dautier 78140 Vélizy, FRANCE

J-C. Broudic
CEA
BP 171 30207 Bagnols/Cèze, FRANCE

Ph. Bretault
SGN
1 rue des Hérons 78182 Saint Quentin cedex, FRANCE

ABSTRACT

Generation of scraps and waste are inherent in any nuclear activity. They can be minimized but not totally avoided. The plutonium handling facilities generate solid waste that are difficult to decontaminate due to the resistance of plutonium oxide to the conventional dissolution processes.

Using silver II dissolution is an elegant and efficient method for treatment of scraps and plutonium bearing waste. The Centralized Alpha Waste Treatment unit (UCD) has recently started active operation on COGEMA La Hague site. It has already yielded encouraging results in decontamination of solid waste. Today, UCD Facility demonstrates that the leaching process using electrogenerated Silver II ions for the decontamination of alpha solid waste has reached its operational dependability. This unit is part of the solid waste management implemented in COGEMA facilities in accordance with the ALARA principle.

INTRODUCTION

Generation of radioactive waste is the unavoidable consequence of any nuclear activity. In addition, the specifications of the end-products of this industry are so stringent that generation of rejected products (scraps) can not be avoided either.

The final disposal of solid waste containing long-life radio-elements has become one of the key issues of the nuclear industry from both technological and economical point of view. Long term storage in deep repositories, although very expensive, appears to be the only suitable solution. It is therefore of major interest to reduce the volume and radiotoxicity of waste to be disposed of in deep repositories. In that way, decontamination of solid waste to enable their surface storage is very attractive.

Plutonium handling facilities such as conversion or MOX fuel fabrication generate solid waste and scraps that are difficult to treat by conventional leaching and dissolution processes.

Since the beginning of the eighties, the silver II dissolution process has been developed in France for both:

SILVER II DISSOLUTION PROCESSES IN FRANCE

Process principle and common features

Since 1981, more than 10 units using silver II dissolution process have been implemented either in CEA (Atomic Energy Commission) research centers or in COGEMA plants. A distinction has to be made according to the function of the process:

In both cases, a suitable pretreatment has to be implemented according to the feed characteristics. All the applications of the silver II process have common features:

Fig. 1. Mechanism of the silver II electrolytic dissolution

- 100 Amperes for small capacity units,

- 400 Amperes for higher capacity units.

Dissolution

Several pilot electrolysers were designed and operated by CEA, leading to the construction of the industrial applications presented hereafter. Two industrial dissolution processes are implemented on La Hague site.

UP3/T4/PuO2 Dissolution Unit

In UP3 plant, dedicated to the reprocessing of foreign spent fuels (Japanese, German, Swiss, Belgian, Dutch...), T4 is the plutonium purification/conversion building. The silver II dissolution unit includes a small size dissolver designed to recover plutonium from off-specification PuO2 batches, PuO2 sample excess and PuO2 powder from glove-box sweeping. Its capacity is 1 kg of PuO2/batch. Since the active start-up of UP3 in 1989, 30 kg of PuO2 have been dissolved in this unit.

UP2-800/R1/Pu Dissolution Unit (URP)

In UP2-800 plant, dedicated to the reprocessing of French spent fuels, R1 is the shearing/dissolution building. The URP unit has a dual purpose:

Decontamination of waste

The application of silver II dissolution to the decontamination of solid waste has been developed by CEA during the eighties in ELISE and PROLIXE Facilities (Fontenay-aux-Roses Research Center). These units are still currently used for the decommissioning of the radiochemistry building. Today, CEA uses a new unit for leaching and embedding alpha solid waste (LEDA) in its new ATALANTE Facility on Marcoule site.

After this development work, the process was industrially applied on COGEMA La Hague site:

ELISE

The ELISE Facility is designed to decontaminate solid alpha waste and has a capacity of 10 to 20 kg of waste per batch. It is installed in glove boxes. Following the silver II leaching process, the waste are rinsed, dried and conditioned for surface storage. Since the active commissioning in 1987, ELISE has processed more than 4 tons of solid waste.

PROLIXE

The PROLIXE Facility is designed to treat alpha, beta, gamma waste. It has the same capacity as ELISE but is installed in a shielded hot-cell. Since the active commissioning, in 1988, PROLIXE has processed more than 4 tons of solid waste.

LEDA

This unit has the same function as PROLIXE. It is used to decontaminate the solid waste generated in ATALANTE Facility. PROLIXE has also played an important part in the Research and Development works for the UCD unit.

UTD

This unit has been designed recently for the specific needs of UP3/T4 building. It will be able to decontaminate plastic waste (after shredding if necessary), metallic waste and specially metallic PuO2 filters. This unit is now under commissioning, active start-up is expected in the near future.

UCD

The Centralized Alpha Waste Treatment unit is composed of three lines which have the following functions:

line A

:recovery of plutonium from incineration ashes to be produced by the alpha incinerator of the MELOX MOX fuel fabrication plant. This line mainly includes:

  • crushing of the ashes,
  • dechlorination to prevent precipitation of silver chloride (AgCl)
  • silver II dissolution
  • separation of the undissolved ashes by filtration

lines B and C

: decontamination of metallic and plastic waste.

The design of lines B and C is identical. In a first step, only line B has started active operation. In the next part of the paper, the process and the results collected after one year of active operation are described.

DECONTAMINATION OF SOLID WASTE IN UCD

Description of the process

Line B of the Centralized Alpha Waste Treatment unit is composed of three main parts:

Sorting and pretreatment are gathered in a single large size cell fitted with two opposite working faces:

In this cell, the 120-liter-waste-drums are received through an air-lock and the waste are sorted into two categories:

at first, waste unsuitable for the leaching process are sorted out. They are taken out and put into new drums which can be routed to a more adapted treatment: incineration or compaction. This category of waste, which represents only a small part of the alpha contaminated waste, is mainly composed of:

waste suitable for the leaching process are then prepared to improve the efficiency of the decontamination:

Silver II leaching is performed in a 200-liter-vessel connected to the electrolyser where silver II ions are continuously regenerated. The initial leaching solution is a mix of nitric acid and silver nitrate (AgNO3). The leaching solution is circulated between the leaching vessel and the electrolysis cell by means of a turbine in the circulation pot. Decontaminated waste are then rinsed, dried and packaged in new 120-liter-drums.

Fig. 2. Centralized Alpha Waste Treatment Unit - line B(Place Fig. 2 here)

Counting of the plutonium content is performed for every drum entering and leaving the unit. According to the French regulation for long term storage, the maximum alpha activity in final package for surface storage is 0.1 Ci/t (0.37 1010 Bq/t). This limit corresponds to about 200 mgPu. As a consequence, every drum leaving UCD with more than 200 mgPu are not suitable for surface storage. The global efficiency of UCD line B can therefore be estimated with the following ratios:

 

 

First results of active operation

UCD unit was licensed for active operation in July 1996. Line B of UCD started active operation in February 1997. Up to now, six decontamination campaigns have been performed. This first year of active operation was considered by the operator as a training and a learning period. The main objective was to demonstrate the ability of UCD to decontaminate a wide range of alpha contaminated waste liable to be generated on a reprocessing site. Over this period, almost 100 drums containing various types of alpha solid waste have been treated. Figure 3 shows that the capacity has steadily increased over that period.

Fig. 3. Main results of UCD - line B operation.

Today, the experience gained with UCD line B can be summarized with the following figures:

  • total number of drums treated:

95

  • total mass of solid waste treated:

1300 kg

  • total amount of inlet plutonium:

more than 500 g

  • number of leaching operations:

119

Following lessons were learnt from the first year of active operation:

It appeared that a significant portion of the plastic waste suitable for leaching was not contaminated or very slightly contaminated. This particularly applies to the multiple wrapping vinyl bags and plastic bins used as putting in/taking out devices. It is wise to isolate this third category of waste that can be downgraded to non alpha waste without leaching. As a result, only the most contaminated waste are now treated by the silver II leaching process.This procedure allows to reduce the total amount of waste to be leached and increases the R2 ratio by limiting cross contamination.

Among the waste that are actually decontaminated, a distinction has to be made between metallic waste and plastic waste:

- average Pu recovery rate of the leaching process: 95%,

- R1 ratio < 1,

- R2 ratio > 90 %.

It has to be noted that the decontamination efficiency may decrease when the metallic parts show a particular geometry (i.e. with powder retention). For instance, it is difficult to decontaminate filtering media made of sintered stainless steel. Decontamination of this kind of waste might be improved by circulating the silver II solution through the filtering media.

- Shredding of hard plastic material is quite easy. For this type of waste, the decontamination efficiency is same as for metallic waste.

- Shredding of soft material and rubber type material is more difficult. In that case, plastic agglomerates may appear during shredding which decreases the decontamination efficiency.

As far as non metallic waste are concerned, the average results obtained since the active start-up of UCD line B are as follows:

- R1 ratio < 1,

- R2 ratio > 50 %.

For the next campaigns, it is intended to improve the sorting of the plastic waste and the shredding of the soft material. Higher performances are then expected in terms of volume and radiotoxicity reduction.

CONCLUSION

Thanks to the extensive Research and Development work on silver II processes performed by CEA, an innovative and comprehensive management for any kind of alpha solid waste issuing from Pu handling facilities has been implemented by COGEMA. The industrial applications of silver II dissolution in URP and UCD units, designed by SGN, are the key components of this new system. UCD unit is now able to reduce volume and radiotoxicity of alpha solid waste which are either accumulated or to be generated in COGEMA facilities. This perfectly meets the objectives of the ALARA principle applied to solid waste.

Fig. 4. ALARA principle applied to alpha solid waste management

The first year of active operation of UCD has demonstrated the industrial feasibility and the efficiency of the silver II leaching process. This experience has also confirmed the necessity of sorting and pretreatment operations and their influence on the global performances.

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