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COST AND RADIOLOGICAL IMPACT OF REACTOR WASTE IN BELOW-GROUNDS VAULTS.

Objective

AS PART OF THE JOINT STUDY AIMING AT ASSESSING MANAGEMENT ROUTES ON THE BASIS OF ECONOMIC AND RADIOLOGICAL CRITERIA, INITEC WILL FOCUS ON THE COST AND RADIOLOGICAL IMPACT ASSESSMENT FOR THE FINAL DISPOSAL PHASE OF REACTOR WASTES IN BELOW GROUND VAULTS.

THE MAIN GOALS OF THIS PROJECT ARE:
- TO DETERMINE THE RADIOLOGICAL IMPACT BOTH SHORT-TERM AND LONG-TERM ASSOCIATED TO A STORAGE FACILITY OF THE BELOW GROUND TYPE FOR REACTOR WASTES. THE FOLLOWING MAIN RELEASE PATHWAYS WILL BE TAKEN INTO ACCOUNT: GROUND WATER MIGRATION OF RADIOACTIVE ELEMENTS, SURFACE WATER RELEASES AND ATMOSPHERIC RELEASES. THESE DIFFERENT STAGES WILL BE CONSIDERED IN THE LIFE OF THE INSTALLATION: OPERATION OF THE FACILITY, INSTITUTIONAL CONTROL PHASE AND FREE USE OF THE LAND AFTER TERMINATION OF THE LICENSE. DIFFERENT SCENARIOS WILL BE ASSUMED FOR EACH OF THE DIFFERENT STAGES, INCLUDING NORMAL OPERATION SCENARIOS AS WELL AS ACCIDENTAL SCENARIOS.

- TO DETERMINE THE RADIOLOGICAL BURDEN TO THE FACILITY OPERATORS.

- COST ASSESSMENT RELATED TO THE DISPOSAL OF LWR WASTE PRODUCTS IN BELOW GROUND VAULTS, INCLUDING CAPITAL AND OPERATING COSTS.
As part of the joint study aiming at assessing management routes on the basis of economic and radiological criteria this work focuses on the cost and radiological impact assessment for the final disposal phase of reactor wastes in below ground vaults.

The lower level of the disposal site is assumed to be located 5 meters above the water table and to be capable of accepting 120000 m{3} of conditioned wastes in 68 concrete vaults of 2 different types to accomodate weakly and highly active packages. The waste streams considered consist of ion exchange resins, filters, core components, technological wastes and trash. Total capital cost of the facility per unit waste volume in 1993 Ecus is 899 (37%) and operating cost 1585 (63%). Major contributors to total costs are site works with 17%, direct labour with 32% and vault construction with 15%.

The approach adopted for estimating the occupational exposure was based on a per shipment basis and most significant data have been adapted to the specific design. Annual average individual doses range from 1.05E-2 to 3.27E-2 Sv per annum and 2.62E-6 to 8.18E-5 sv/m{3}. Maximum individual and collective doses to members of the public during the stage of operation of the facility and in the long term have also been estimated.
2.2. WASTE ACCEPTANCE CRITERIA WILL BE ESTABLISHED IN TERMS OF SPECIFIC ACTIVITY LIMITS, MATRIX TYPES, LEACHING RATES, MECHANICAL PROPERTIES, DRUM SIZES ETC... SO AS TO ACCOMPLISH PROTECTION GOALS FOR THE PUBLIC.

2.3. DRAWING UP OF STORAGE FACILITY LAYOUT AND DESCRIPTION OF THE OPERATIONS TO BE CARRIED OUT (SORTING OF THE WASTE PRODUCTS, WASTE CONDITIONING PROVISIONS, GENERAL LAYOUT ETC...) AS DETAILED AS NEEDED FOR THE COST AND RADIOLOGICAL IMPACT ASSESSMENT.

2.5. THE IMPACT OF THE PACKAGE TYPE (RETRIEVABLE OR NOT) ON THE VOLUMES OF WASTE TO BE DISPOSED OF WILL BE ASSESSED, AS WELL AS THE IMPACT OF VARYING BOTH THE VOLUMES AND CATEGORIES OF LWR WASTES.

2.6. A COST ASSESSMENT RELATED TO DISPOSAL OF LWR WASTE PRODUCTS IN BELOW GROUND VAULTS WILL BE CARRIED OUT, INCLUDING A RELATIONSHIP BETWEEN DISPOSAL COST AND QUANTITIES OF VARIOUS CATEGORIES OF WASTE PRODUCTS, AND SCALING COST VARIATIONS OF THE NUCLEAR PARK SIZE.

2.7. THE OCCUPATIONAL EXPOSURE (ANNUAL INDIVIDUAL DOSE AND COLLECTIVE DOSE) WILL BE DETERMINED FOR NORMAL AND ABNORMAL DISPOSAL OPERATIONS, FOR THE LATTER CASE EXPRESSED AS PROBABILITY OF OCCURENCE, FOR EACH WORKING PLACE AND 30 YEARS OF OPERATION.

2.8. THE RADIOLOGICAL IMPACT TO THE PUBLIC WILL BE ASSESSED AND INDIVIDUAL AND COLLECTIVE DOSES WILL BE CALCULATED. THE DISPOSAL SITE ENVIRONMENT WILL BE DEFINED AS WELL AS PATHWAYS AND SCENARIOS CONSIDERED.

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

Empresa Nacional de Ingeniería y Tecnología SA
Address
17,Padilla
28006 Madrid
Spain