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Decommissioning and Dismantling of the
Moata Reactor-
A Radiation Protection Perspective
Prashant Maharaj
Australian Nuclear Science &
Technology Organisation
A History of Moata
• Graphite
moderator /
reflector
• Cooled by light
water
• Shielding - high
density and low
density concrete
• Constructed at ANSTO in 1961
• ARGONAUT type reactor
• Built as a 10 kW reactor, but modified
in 1972 to 100 kW
The Moata Reactor
From 1961 to 1995:
– Neutron
radiography
– Soil analysis
– Cancer
treatment
research
– Quality Control
for HIFAR
Shutdown & Decommissioning
Two phases of dismantling:
– Preliminary Dismantling – the removal of the internal components of the reactor,
including the steel core structures, graphite moderator and beam line facilities
– Structural (Biological Shield) Dismantling – the cutting and removal of the concrete
shielding and the floor area below the shielding.
1995 1996 1997 1998 2009
Shutdownafter4,519start-ups
Fuelunloaded
DecommissioningProjectTeam
established
Primarycoolant(lightwater)
drained
ReactorControlSystem
removed
Planningcommencedfor
dismantling
PreliminaryDismantlingbegan
PreliminaryDismantlingcomplete
Containmenttentinstalled
2010
BiologicalShieldDismantlingbegan
BiologicalShieldDismantlingComplete
Structural (Biological Shield) Dismantling
Structural (Biological Shield) Dismantling
• Reactor housed in a building used for
other operational task
• A containment tent with HEPA filtered
extraction system built around the
reactor
Getting There…
The steps involved in planning, completing and evaluating the
success of the Biological shield Dismantling:
– Radiation Protection Plan
• Characterisation
• Radiation Management & Monitoring
• Dose Estimation & Constraints
• Personal Protective Equipment
• Final Status Surveys
– Outcomes & Lessons Learnt
Characterisation – Survey
• A radiological survey was carried out to determine
the dose rates within the empty cavity areas.
• The data from this exercise was used to prepare a
dose estimate for the Biological shield dismantling.
• This helped us estimate the maximum individual
and collective dose for this part of the project.
Measured dose rates ranged from 7-4000 Sv/hr
Dose Estimation and Constraints
TASKSET2
MainBioshield(HeavyDensityConcrete)
ActiveZone
Estimatedtimeto
performtask
Est.ExpTime
(hours)formost
exposed
individual
EstimatedDoserate
(µSv/hr)forWorker
1,2,3or4
EstimatedDose
Received(µSv)Worker
1-Cardinal
EstimatedDose
Received(µSv)Worker
2-Cardinal
EstimatedDose
Received(µSv)for
Worker3-Cardinal
EstimatedDose
Received(µSv)for
Worker4-Cardinal
EstimatedDoserate
(µSv/hr)for HPS1
EstimatedDose
Received(µSv)HPS
1
Estimated
Collectivedose
man-Sv
Machinedemolition-Remoteoperation 24 12 70 840 840
HPSMonitoringsurveys 8 8 70 560
Bobcatwasteremoval 8 4 130 520 520
Materialremovalwith5tonneexcavator 16 8 70 560
Manualfillingofwastecontainers 1 0.5 300 150
TotalForCuttingandRemovalOfMain
Bioshield(Activeconcrete) 57 840 840 520 1230 560
SummaryDose= 840 840 520 1230 560 3990
Dose Estimates:
• Collective – 10,400 man-μSv
• Av. Individual – 1156μSv (assuming 9 workers)
• Max. Individual – 1444μSv
Dose Constraints:
• Individual – 1500μSv
• Daily – 50μSv
Radiation Management &
Monitoring
Controlling exposure using distance
Radiation Management & Monitoring
Controlling exposure using shielding
Steel Plates for shielding
Radiation Management & Monitoring
Controlling exposure using shielding
Shielded containers for
activated waste:
– Specially designed
6mm steel boxes for
active concrete
Radiation Management & Monitoring
Dose Management:
– Radiological
surveys
Dose Monitoring:
– EPD System
– TLDs
– Whole Body
Monitoring
Radiation Management & Monitoring
• External gamma monitors
and air samplers were
placed close to work areas.
• Barrier and exit monitoring
equipment were used to
ensure that no
contamination was taken
out of the classified areas.
Personal Protective Equipment
• Since there was a high potential of
generating dust while cutting and
demolishing the active concrete it was
decided to start from the highest level
of PPE which included ;
 Respiratory protection with
particulate cartridge)
 Tyveks
 Overshoes and gloves
• This was than downgraded as we
gained operational understanding of
the project risks.
Final Status Survey
• Dose rate surveys were carried out on
marked survey points (grid survey)
• Acceptance criteria of 0.5uSv/hr was
met to ensure a brown-field condition
was met
• Samples were taken in and around the
foundations of the reactor and analysed
for activity.
• The following guides were also used to
determine the exemption and clearance
criteria for the site
 IAEA No. RS-G.1.7
 ARPANSA Reg 1999, Schedule 2,
Part 2
Outcomes & Lessons Learnt
– Estimated doses vs. actual doses:
Dose
ANSTO
Estimated
ARPANSA
Constraint
ANSTO
Constraint
Actual
Collective
10,400 person-
μSv
13,000 person-
μSv
10,400 person-
μSv
1,679 person-
μSv
Max.
Individual
1444 μSv 1750 μSv 1500 μSv 252 μSv
Daily - - 50μSv 46μSv (max)
Outcomes & Lessons Learnt
• From a radiation protection perspective the Biological Shield
Dismantling was completed safely and without incident.
– Dose estimates were higher than those recorded by staff.
This was attributed to being overly conservative and some
of the contributing factors were;
• Self shielding by the dismantled concrete
• Time taken to dismantle and remove the active concrete was
less than anticipated.
– No surface or airborne contamination was detected
throughout the project
– There were no personal contamination events
Decommissioning and dismantling of the moata reactor  a radiation protection perspective- maharaj
Decommissioning and dismantling of the moata reactor  a radiation protection perspective- maharaj

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Decommissioning and dismantling of the moata reactor a radiation protection perspective- maharaj

  • 1. Decommissioning and Dismantling of the Moata Reactor- A Radiation Protection Perspective Prashant Maharaj Australian Nuclear Science & Technology Organisation
  • 2. A History of Moata • Graphite moderator / reflector • Cooled by light water • Shielding - high density and low density concrete • Constructed at ANSTO in 1961 • ARGONAUT type reactor • Built as a 10 kW reactor, but modified in 1972 to 100 kW
  • 3. The Moata Reactor From 1961 to 1995: – Neutron radiography – Soil analysis – Cancer treatment research – Quality Control for HIFAR
  • 4. Shutdown & Decommissioning Two phases of dismantling: – Preliminary Dismantling – the removal of the internal components of the reactor, including the steel core structures, graphite moderator and beam line facilities – Structural (Biological Shield) Dismantling – the cutting and removal of the concrete shielding and the floor area below the shielding. 1995 1996 1997 1998 2009 Shutdownafter4,519start-ups Fuelunloaded DecommissioningProjectTeam established Primarycoolant(lightwater) drained ReactorControlSystem removed Planningcommencedfor dismantling PreliminaryDismantlingbegan PreliminaryDismantlingcomplete Containmenttentinstalled 2010 BiologicalShieldDismantlingbegan BiologicalShieldDismantlingComplete
  • 6. Structural (Biological Shield) Dismantling • Reactor housed in a building used for other operational task • A containment tent with HEPA filtered extraction system built around the reactor
  • 7. Getting There… The steps involved in planning, completing and evaluating the success of the Biological shield Dismantling: – Radiation Protection Plan • Characterisation • Radiation Management & Monitoring • Dose Estimation & Constraints • Personal Protective Equipment • Final Status Surveys – Outcomes & Lessons Learnt
  • 8. Characterisation – Survey • A radiological survey was carried out to determine the dose rates within the empty cavity areas. • The data from this exercise was used to prepare a dose estimate for the Biological shield dismantling. • This helped us estimate the maximum individual and collective dose for this part of the project. Measured dose rates ranged from 7-4000 Sv/hr
  • 9. Dose Estimation and Constraints TASKSET2 MainBioshield(HeavyDensityConcrete) ActiveZone Estimatedtimeto performtask Est.ExpTime (hours)formost exposed individual EstimatedDoserate (µSv/hr)forWorker 1,2,3or4 EstimatedDose Received(µSv)Worker 1-Cardinal EstimatedDose Received(µSv)Worker 2-Cardinal EstimatedDose Received(µSv)for Worker3-Cardinal EstimatedDose Received(µSv)for Worker4-Cardinal EstimatedDoserate (µSv/hr)for HPS1 EstimatedDose Received(µSv)HPS 1 Estimated Collectivedose man-Sv Machinedemolition-Remoteoperation 24 12 70 840 840 HPSMonitoringsurveys 8 8 70 560 Bobcatwasteremoval 8 4 130 520 520 Materialremovalwith5tonneexcavator 16 8 70 560 Manualfillingofwastecontainers 1 0.5 300 150 TotalForCuttingandRemovalOfMain Bioshield(Activeconcrete) 57 840 840 520 1230 560 SummaryDose= 840 840 520 1230 560 3990 Dose Estimates: • Collective – 10,400 man-μSv • Av. Individual – 1156μSv (assuming 9 workers) • Max. Individual – 1444μSv Dose Constraints: • Individual – 1500μSv • Daily – 50μSv
  • 11. Radiation Management & Monitoring Controlling exposure using shielding Steel Plates for shielding
  • 12. Radiation Management & Monitoring Controlling exposure using shielding Shielded containers for activated waste: – Specially designed 6mm steel boxes for active concrete
  • 13. Radiation Management & Monitoring Dose Management: – Radiological surveys Dose Monitoring: – EPD System – TLDs – Whole Body Monitoring
  • 14. Radiation Management & Monitoring • External gamma monitors and air samplers were placed close to work areas. • Barrier and exit monitoring equipment were used to ensure that no contamination was taken out of the classified areas.
  • 15. Personal Protective Equipment • Since there was a high potential of generating dust while cutting and demolishing the active concrete it was decided to start from the highest level of PPE which included ;  Respiratory protection with particulate cartridge)  Tyveks  Overshoes and gloves • This was than downgraded as we gained operational understanding of the project risks.
  • 16. Final Status Survey • Dose rate surveys were carried out on marked survey points (grid survey) • Acceptance criteria of 0.5uSv/hr was met to ensure a brown-field condition was met • Samples were taken in and around the foundations of the reactor and analysed for activity. • The following guides were also used to determine the exemption and clearance criteria for the site  IAEA No. RS-G.1.7  ARPANSA Reg 1999, Schedule 2, Part 2
  • 17. Outcomes & Lessons Learnt – Estimated doses vs. actual doses: Dose ANSTO Estimated ARPANSA Constraint ANSTO Constraint Actual Collective 10,400 person- μSv 13,000 person- μSv 10,400 person- μSv 1,679 person- μSv Max. Individual 1444 μSv 1750 μSv 1500 μSv 252 μSv Daily - - 50μSv 46μSv (max)
  • 18. Outcomes & Lessons Learnt • From a radiation protection perspective the Biological Shield Dismantling was completed safely and without incident. – Dose estimates were higher than those recorded by staff. This was attributed to being overly conservative and some of the contributing factors were; • Self shielding by the dismantled concrete • Time taken to dismantle and remove the active concrete was less than anticipated. – No surface or airborne contamination was detected throughout the project – There were no personal contamination events