safran upgraded to support the implementation of the borehole disposal concept rodolfo avila,...
TRANSCRIPT
SAFRAN
Upgraded to support the implementation of the Borehole Disposal Concept
Rodolfo Avila, Facilia AB
Outline
• Description of SAFRAN• Adaptation to support the implementation of the
BDC.
• Generic Operational Safety Assessment (GOSA)
What is SAFRAN
• SAFRAN is a software package for safety assessment in pre-disposal waste management.
• It implements the methodology developed within the IAEA project SADRWMS (2005-2010)
SADRWMS methodology
Assessment Context
Description of Facility or Activity and the Waste
Identification of Hazards
Development and Justification of Scenarios
Identification of Scenarios
Formulation of Models and Identification of Data Needs
Evaluation of Results
Analysis of Safety Measures
Analysis of Engineering
Performance of Calculations
Comparison with Assessment Criteria
Engineering design, Safety measures,
Other relevant information (management systems, operational
experience, site data …)
Models and computer codes; Generic / site specific data
Purpose, Regulations, Standards …
PIE lists, Expert judgements
Screening of Hazards
Review and
modify Adequate? Accept
Independent verification
Yes Yes No
No
Adequate?
Provides detailed guidelines for safety assessment.
Based on the IAEA safety guide DS284: The Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste
The SADRWMS methodology
• Provides detailed advice for each step of the Safety Assessment
• Describes the different types of assessments that might be required
• Provides methods for Hazard identification and screening
• Provides methods for performing qualitative and quantitative assessments for different scenarios
Disposal Borehole Design & Construction
Borehole Diameter – 260mmLength – variable
CasingDiameter – 160mmLength - variable
Disposal ContainerDiameter – 115mmLength – 250mm
CapsuleDiameter - 21/48mmLength – 110/121mm
Disposal container (with concrete insert) and container lid. Bottom row: sealed capsules in two sizes.
BoreholeID 260 mm
Borehole casingOD 160 mm
Borehole backfill
Deflection plate
Waste packageOD 114 mm
Borehole plug
Casing grout
Centralisers
Casing backfill
Closure zoneMinimum 30 m
Disposal zone
Casing split
Emplacement and Borehole Closure
SAFRAN components
System descriptionSite features, waste producers,
waste streams
Regulatory Framework
Safety AssessmentNormal Operation,
Accidents
SAFREQ
SAFCALC DATABASE
Report
Report
System Description
For each configuration
• Site • Facilities
– Rooms
» Areas (Storage or Processing)
Safety elements
• Waste Management Activities– Processes
– Check for clearance
• Waste Producers– Primary Waste Components
» Waste Streams
Safety elements
• Site selection
• Safety functions
• Limits and conditions
• Mantainance requirements
• Operational procedures
• Emergency procedures
• Management systems
Can be linked to physical elements and assessments
Waste management activities
• Description
• Output(s) from activities
• Reduction factors
• One and only one WMA can be assigned to an area
A process is a sequence of WMAs which can be used in defition of Waste Streams (WS)
Waste Streams
• Waste streams represent the fate of waste components through different steps of processing, storing and clearing of wastes
• Accounting for changes in waste properties by waste management activities at each step.
Additions for BDC
• The user can define that one or more boreholes will be considered at a Site
• A library of safety elements of relevance for BOSS will be added
• A library of pre-disposal waste management activities relevant for BOSS
• A library of processes
Additions for BDC
• A library of sources
• SIMBOD – tool for management of the Borehole Disposal process
• Typical waste streams – resulting from application of Typical Processes to different Types of Sources
Sources – Conditioned - Packaged
SAFRAN components
System descriptionSite features, waste producers,
waste streams
Regulatory Framework
Safety AssessmentNormal operation,
accidents
SAFREQ
SAFCALC DATABASE
Report
Report
Assessment types
• For normal operation and accidents.
• Doses to workers and members of the public.
• Radiological impacts indoors and outdoors.
Graded approach to the assessments
Impacts
Screening or Hazards
Dose Assessment
Calculations of Hazard Quotients (HQ) for standardized conservative exposure situations
calculations for specified endpoints and expecific exposure conditions
Assessments for accidents
Impact 1
PIE Type
PIE 1 PIE n
Scenario 1 Scenario n
Impact n
Endpoint 1 Endpoint n
Ass Case 1
Ass Case n
Scenario m
Impact m
Screening of hazards
Example of Probability-Consequence plots
HQ/Prob Very Low
Low Medium High Very High
<0.1 SC3
0.1- 1 SC4
1-10 SC2
10-100
>100 SC1
Additions for BDC
• Update of the PIE database
• Library of typical scenarios
• Library of generic safety assessments
SAFRAN components
System descriptionSite features, waste producers,
waste streams
Regulatory Framework
Safety AssessmentNormal operation,
accidents
SAFREQ
SAFCALC DATABASE
Report
Report
Models available in SAFCALC
• IAEA SR-19 models: screening models for routine releases to the atmosphere, lakes, rivers, estuarines and coastal areas.
• Model for accidental releases to the atmosphere.
• Model for accidental releases inside a room.
• Simple dosimetry models: point source, disc, cylinder, cube (with and without shielding)
SAFRAN components
System descriptionSite features, waste producers,
waste streams
Regulatory Framework
Safety AssessmentNormal operation,
accidents
SAFREQ
SAFCALC DATABASE
Report
Report
Database
• Radionuclide half lives.
• Clearance levels.
• Gamma constants – dose rates at 1 m from a point source.
• Screening dose rates for Normal and accidental situations.
• Screening release rates for Normal operation.
• Screening releases for accidental situations.
• Release Fractions.
• Dispersion factors.
• Dose Conversion Factors for Normal and accidental situations.
Additions for BOSS
• Models and calculation methods used in Generic Operational Safety Assessment (GOSA).
• Parameter values required for GOSA.
SAFRAN components
System descriptionSite features, waste producers,
waste streams
Regulatory Framework
Safety AssessmentNormal operation,
accidents
SAFREQ
SAFCALC DATABASE
Report
Report
SPECIALIZED LIBRARIES FOR BOSS
SAFREQ
• Tool for assistance in developing the safety case by assessing compliance with Safety Requirements and Safety Guidelines.
Additions for BOSS
• Going from a prototype to a Released version
• Specific guidelines for safety case of BDC
Assessment Context
• The assessment context of the GOSA should be consistent with the generic safety assessment (GSA) for borehole disposal (IAEA Safety Series Report: Generic Post-Closure Safety Assessment for Borehole Disposal of Disused Sealed Sources)
Purpose
• The purpose of the GOSA is to demonstrate that the proposed pre-disposal waste management activities are done in a safe manner, as required by the regulatory framework. The safety of operators (workers) and members of the public will be assessed, both for normal operations and for potential accidental situations.
Scope
• The starting point for the GOSA is that the Disused Sealed Sources (DSSs) have arrived at the site and a decision has been taken to “dispose” the DSS by borehole disposal
• Activities of the original producer [e.g. hospital] and transport to site are beyond the scope of the current project).
• Other disposal options (e.g. disposal in a near-surface or deep facility) and management options (long-term storage) are beyond the scope of this GOSA.
Inventory to be considered
• The inventory (Bq) and number of sources to be assessed in the GOSA need to be representative of what is found in practice in different countries.
• An initial proposal is to consider two cases: a country (Ghana being an example) with a low to medium inventory of relatively low level activity sources that do not require the use of hot cells, and a country (South Africa being an example) with a medium to large inventory which includes high activity sources that will
require the use of hot cells.• Different initial states of the sources should be considered,
including sources in the original devices, in a transport package,
in the working container, and conditioned in cement.
Regulatory Framework
• IAEA Safety Standards will be used as the basis for the regulatory framework.
• This will include normal operation and accidental situations, taking into account dose constraints as well as dose limits.
• One issue currently under evaluation is whether to include assessment of doses to the eye, extremities, etc., in addition to whole body doses.
Inventory of sources
Sources for Disposal
Sources for Decay Store
Classification of sources
Other Disposal Options
Sources for BDC
Screening on total
inventory
Several Boreholes might be required
Number of capsules required for one borehole
Allocation of Sources to capsules
Use SAFCALC to obtain operational activity limits for capsules
WMA, etc
IAEA databases, SIMBOD, etc
Temporary Storage at Site
Prepare for Introduction into Cell
Remove Source and Characterise
Lift original Source Shield into Cell
Close Cell
Encapsulation and Testing
Condition into Disposal Container
Lower into Borehole
Borehole Backfilling
Transfer Container to Transfer Cask
Lower into Borehole
Borehole Backfilling
Operational activitiesDuration
(Minutes)
1) Prepare for Introduction into hot cell 15
2) Lift Original Source Shield into the hot cell 5
3) Close the hot cell 20
4) Remove the source 60
5) Characterise the source 20
6) Encapsulation and test of the capsule 20
7) Place capsule in disposal container and NDT 20
8) Transfer disposal container to the transfer cask 10
9) Disengage and prepare the transport cask for transport
15
10) Emplacement of the disposal container in borehole 15
11) Backfilling of the borehole 15
Typical activities and their duration
Examples of accidental scenarios (hot cell)
• The situation where the operation team is unaware that the source has an activity greater than the value for what the facility was designed for and the team proceeds with standard operations.
• Error during the determination of the density of the shielding material (sand) in the hot cell and the operation proceeds with a sand density below design requirements.
• Situation with the ZnBr2 window density below design requirements being used by the operation team.
• Source is dropped after being removed from the original source shield.
• The source is found to be leaking when removed from the original source shield inside the hot cell. (Could have been damaged during removal).
• The manipulators malfunction whilst the source is inside the hot cell.
• The biological shield is damaged while bringing in the original source shield.
• Power outage in the hot cell.
• Lights are not operational in the hot cell.