lessons from windscale's nuclear legacy - Ingenia

lessons from windscale's nuclear legacy - Ingenia lessons from windscale's nuclear legacy - Ingenia

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LESSONS FROM WINDSCALE’S NUCLEAR LEGACY WEALTH CREATION LESSONS FROM WINDSCALE’S NUCLEAR LEGACY the industry can manage the legacy issues surrounding nuclear power. Indeed, the WAGR decommissioning was a European demonstration project, managed by the OECD Nuclear Energy Agency, for safe and cost-effective decommissioning of nuclear reactors. More specifically, the decommissioning has provided the industry with valuable experience in areas such as remote handling, and has underlined the importance of establishing ways to get waste out of the facility and what would happen to it after its removal. ALWAYS INNOVATING Piles 1 and 2 at Windscale were an extraordinary technological achievement for their time. Removing the reactors has also driven significant engineering innovations in nuclear clean-up. Constructed in the late 1940s, the Piles comprise two graphitemoderated, air-cooled reactors and their associated facilities. Each reactor consisted of 2,000 tonnes of graphite blocks in an octagonal stack, 15 m in diameter and 7.5 m long, surrounded by a biological shield of reinforced concrete 2 m thick. The owner of any new nuclear power station built in the UK will have to produce detailed plans for its eventual closure before construction can begin. Lessons learnt from decommissioning reactors and waste disposal at the current plants will provide valuable information for future developments. Peter Mann, formerly head of site for Babcock at Windscale in Cumbria, describes the work undertaken on the Windscale Piles and the Windscale Advanced Gas-Cooled Reactor. Part of the charge face of the Pile 1 reactor – the worker is removing the sealant from the locking device on the charge plug to inspect the fuel channels The decommissioning at Windscale has led to the development of new techniques that are directly applicable to the UK decommissioning programme. As one of the first countries to operate nuclear power stations, the UK can draw on 50 years’ experience in dealing with reactors at the end of their commercial life. Thanks to this history, the UK’s nuclear industry is now one of the leaders in decommissioning redundant nuclear facilities. The industry has already had to develop techniques to deal with three nuclear reactors at Windscale – the Windscale Advanced Gas-Cooled Reactor (WAGR) and Piles 1 and 2. While some of the challenges at Windscale are specific to those reactors, many of the techniques developed to decommission these reactors are relevant to other nuclear power stations. The expertise gained will support the decommissioning of the Magnox breed of reactors, most of which have now closed. The last four Magnox reactors, at Oldbury and Wylfa, are scheduled for closure by 2014 having been given lifetime extensions. There are a number of similarities between Magnox and the WAGR reactors. They all have a graphite core, or moderator, and a steel pressure vessel, along with CO 2 cooling with similar heat exchangers. These reactors were also built in the same era, using similar materials such as asbestos. Babcock managed the site (as UKAEA) until 2008. It was then contracted to provide senior personnel within the site management team at Windscale, working with the Nuclear Decommissioning Authority (NDA) and Sellafield. It is applying this expertise in working with Japan on an ongoing project decommissioning the Tokai gas cooled reactor. The devastation at Fukushima power station throughout the Spring of 2011 focused the world’s attention on nuclear safety. The problems posed by a burnt out reactor have already been faced in the UK owing to the fire at Windscale in the 1950s and it is too early to say whether there are relevant parallels that can be used for Fukushima. In the longer term, the experience from Windscale will help in decommissioning new nuclear power stations. In general terms, this includes reassuring the UK public that The Pile 1 reactor charge face where fuel is loaded into the reactor 34 INGENIA INGENIA ISSUE 48 SEPTEMBER 2011 35

LESSONS FROM WINDSCALE’S NUCLEAR LEGACY<br />

WEALTH CREATION<br />

LESSONS FROM<br />

WINDSCALE’S<br />

NUCLEAR LEGACY<br />

the industry can manage the<br />

<strong>legacy</strong> issues surrounding<br />

<strong>nuclear</strong> power. Indeed, the<br />

WAGR decommissioning was a<br />

European demonstration project,<br />

managed by the OECD Nuclear<br />

Energy Agency, for safe and<br />

cost-effective decommissioning<br />

of <strong>nuclear</strong> reactors. More<br />

specifically, the decommissioning<br />

has provided the industry with<br />

valuable experience in areas<br />

such as remote handling, and<br />

has underlined the importance<br />

of establishing ways to get waste<br />

out of the facility and what would<br />

happen to it after its removal.<br />

ALWAYS INNOVATING<br />

Piles 1 and 2 at Windscale were<br />

an extraordinary technological<br />

achievement for their time.<br />

Removing the reactors has also<br />

driven significant engineering<br />

innovations in <strong>nuclear</strong> clean-up.<br />

Constructed in the late 1940s,<br />

the Piles comprise two graphitemoderated,<br />

air-cooled reactors<br />

and their associated facilities. Each<br />

reactor consisted of 2,000 tonnes<br />

of graphite blocks in an octagonal<br />

stack, 15 m in diameter and 7.5 m<br />

long, surrounded by a biological<br />

shield of reinforced concrete<br />

2 m thick.<br />

The owner of any new <strong>nuclear</strong> power station built in the UK will<br />

have to produce detailed plans for its eventual closure before<br />

construction can begin. Lessons learnt <strong>from</strong> decommissioning<br />

reactors and waste disposal at the current plants will provide<br />

valuable information for future developments. Peter Mann,<br />

formerly head of site for Babcock at Windscale in Cumbria,<br />

describes the work undertaken on the Windscale Piles and the<br />

Windscale Advanced Gas-Cooled Reactor.<br />

Part of the charge face of the Pile 1 reactor – the worker is removing the sealant <strong>from</strong> the locking device on the charge plug to inspect the fuel channels<br />

The decommissioning<br />

at Windscale has led to<br />

the development of new<br />

techniques that are directly<br />

applicable to the UK<br />

decommissioning programme.<br />

As one of the first countries<br />

to operate <strong>nuclear</strong> power<br />

stations, the UK can draw on<br />

50 years’ experience in dealing<br />

with reactors at the end of<br />

their commercial life. Thanks<br />

to this history, the UK’s <strong>nuclear</strong><br />

industry is now one of the<br />

leaders in decommissioning<br />

redundant <strong>nuclear</strong> facilities.<br />

The industry has already had<br />

to develop techniques to deal<br />

with three <strong>nuclear</strong> reactors<br />

at Windscale – the Windscale<br />

Advanced Gas-Cooled Reactor<br />

(WAGR) and Piles 1 and 2.<br />

While some of the challenges<br />

at Windscale are specific to<br />

those reactors, many of the<br />

techniques developed to<br />

decommission these reactors<br />

are relevant to other <strong>nuclear</strong><br />

power stations.<br />

The expertise gained will<br />

support the decommissioning<br />

of the Magnox breed of<br />

reactors, most of which have<br />

now closed. The last four<br />

Magnox reactors, at Oldbury<br />

and Wylfa, are scheduled for<br />

closure by 2014 having been<br />

given lifetime extensions.<br />

There are a number of similarities<br />

between Magnox and the<br />

WAGR reactors. They all have a<br />

graphite core, or moderator, and<br />

a steel pressure vessel, along<br />

with CO 2 cooling with similar<br />

heat exchangers. These reactors<br />

were also built in the same era,<br />

using similar materials such as<br />

asbestos. Babcock managed<br />

the site (as UKAEA) until 2008. It<br />

was then contracted to provide<br />

senior personnel within the site<br />

management team at Windscale,<br />

working with the Nuclear<br />

Decommissioning Authority<br />

(NDA) and Sellafield. It is<br />

applying this expertise in working<br />

with Japan on an ongoing<br />

project decommissioning the<br />

Tokai gas cooled reactor.<br />

The devastation at Fukushima<br />

power station throughout the<br />

Spring of 2011 focused the<br />

world’s attention on <strong>nuclear</strong><br />

safety. The problems posed by<br />

a burnt out reactor have already<br />

been faced in the UK owing to<br />

the fire at Windscale in the 1950s<br />

and it is too early to say whether<br />

there are relevant parallels that<br />

can be used for Fukushima.<br />

In the longer term, the<br />

experience <strong>from</strong> Windscale<br />

will help in decommissioning<br />

new <strong>nuclear</strong> power stations.<br />

In general terms, this includes<br />

reassuring the UK public that<br />

The Pile 1 reactor charge face where fuel is loaded into the reactor<br />

34 INGENIA INGENIA ISSUE 48 SEPTEMBER 2011 35


LESSONS FROM WINDSCALE’S NUCLEAR LEGACY<br />

WEALTH CREATION<br />

The use of epoxy resin to encapsulate fuels<br />

and radioactive waste has been trialled<br />

and attracted significant industry interest<br />

which could pave the way for its use in future<br />

decommissioning projects<br />

POLYMERS TO HOLD NUCLEAR WASTES<br />

As part of the decommissioning of the Windscale Piles, Babcock, on behalf of Sellafield Ltd, has<br />

conducted trials on the use of epoxy resin to immobilise fuel and radioactive waste. While the civil<br />

<strong>nuclear</strong> industry makes widespread use of cement to contain higher activity wastes, this material<br />

cannot easily encapsulate some wastes, such as reactive metal or ion-exchange resins. The work on<br />

polymers to encapsulate <strong>nuclear</strong> wastes has reached an advanced stage and has attracted significant<br />

interest in the UK, where the use of polymers has been limited to small volume waste streams at<br />

Trawsfynydd and Harwell.<br />

The high-level waste <strong>from</strong> the Windscale Piles includes a significant proportion of metallic uranium<br />

in finned aluminium cartridges, graphite boats, aluminium isotope cartridges containing a variety<br />

of known compounds and fuel debris. Work was undertaken to develop a polymeric encapsulation<br />

system, including trials with inactive and active wastes, to assess the ability of the polymers to<br />

produce an acceptable wasteform. The aim of the work was to support the process leading up to the<br />

Radioactive Waste Management Directorate’s (RWMD) issuance of a Letter of Compliance (LoC) and to<br />

gain the directorate’s endorsement for encapsulating the waste.<br />

The work included selection of suitable polymers and studies of how they would interact with<br />

other materials in the wastes. The project also looked into the performance of the materials during<br />

processing and their behaviour when exposed to radiation and to heat generated by radioactive<br />

decay. Further trials demonstrated that the materials could be handled safely and could comply<br />

with the standards set out<br />

in the LoC for geological<br />

disposal. These trials have<br />

shown that the polymers<br />

can meet the requirements<br />

for RWMD acceptance of<br />

the wasteform for geological<br />

disposal.<br />

Research so far has<br />

concentrated on the use of<br />

polymers to withstand high<br />

doses of radiation. The NDA<br />

Direct Research Portfolio<br />

has funded further work at<br />

lower dose rates of radiation,<br />

similar to those experienced<br />

as a waste encapsulant, and<br />

under the kind of conditions<br />

they would experience in a<br />

repository. These tests will<br />

also investigate the long term<br />

performance of the polymers.<br />

If successful, the polymer will<br />

be applicable to the widest<br />

Section of Windscale liner containing simulated waste <strong>from</strong> Pile 1, including<br />

graphite, metal fines, fuel cartridges and isotope cartridges encapsulated in<br />

epoxy resin<br />

possible range of wastes<br />

within the UK’s inventory of<br />

<strong>nuclear</strong> wastes.<br />

Following a serious fire in 1957,<br />

both Windscale reactors were<br />

shut down. All of the fuel was<br />

removed <strong>from</strong> Pile 2 while only<br />

a very small proportion of fuel<br />

remains in the fire-damaged<br />

parts of Pile 1. In the 1990s,<br />

Babcock, then UKAEA, began to<br />

decommission, disassemble and<br />

clean up both reactors.<br />

Phase 1 of decommissioning<br />

ended in 1999. The work<br />

included putting dams in the<br />

original water ducts, previously<br />

used to transfer fuel <strong>from</strong> the<br />

reactor to the cooling pond, and<br />

in the inlet and exhaust air ducts<br />

to seal the massive concrete<br />

biological shield surrounding<br />

the core. This allowed the<br />

installation of a ventilation and<br />

monitoring system to replace<br />

the existing natural circulation<br />

which had been difficult to<br />

monitor. The clean-up team also<br />

installed monitoring systems in<br />

and around the core to measure<br />

temperatures, levels of radiation<br />

and the amount of radioactive<br />

material in the core and airflow.<br />

Outside the core, the clean-up<br />

team removed accumulations of<br />

old fuel and isotope cartridges,<br />

used to irradiate materials in the<br />

reactor, in the water and air ducts.<br />

Clearing the water ducts<br />

was particularly challenging: it<br />

involved removing fuel debris<br />

<strong>from</strong> the fire as well as sludge<br />

submerged in 750 m 3 of water.<br />

To achieve this, Babcock and its<br />

contractors adapted technologies<br />

developed for the North Sea oil<br />

industry. They deployed remotely<br />

operated vehicles on existing rails<br />

in the ducts, manoeuvring them<br />

<strong>from</strong> a control console. In this<br />

way, the decommissioning team<br />

could explore the underwater<br />

areas where there might have<br />

been radioactive material. The<br />

operation provided the tools<br />

needed to handle and clear the<br />

solids and sludge. This approach<br />

not only ensured safe operations<br />

but was also highly cost-effective.<br />

Completion of Phase 1 of<br />

the clean up left the plant in<br />

a safe condition until further<br />

decommissioning could begin.<br />

Subsequent work has focused on<br />

developing a remote retrieval and<br />

handling system that can remove<br />

the main hazardous materials,<br />

remains of fuel and isotope<br />

cartridges, <strong>from</strong> Pile 1’s damaged<br />

core, while work on Pile 2 has<br />

included removing the reactor’s<br />

last remaining isotope cartridges.<br />

An important achievement<br />

in the work on Pile 1 has<br />

involved gaining approval <strong>from</strong><br />

the <strong>nuclear</strong> regulators for the<br />

safety case to allow the team<br />

to look inside the reactor’s fireaffected<br />

zone for the first time<br />

since the fire. The team used an<br />

endoscope to inspect this area<br />

and take pictures. The surveys<br />

gave the clean-up team a better<br />

understanding of the condition<br />

of the area. They used the<br />

results to design and develop<br />

techniques to remove fuel and<br />

other radioactive isotopes, and<br />

to devise a strategy for waste<br />

treatment, storage and disposal.<br />

RETRIEVING<br />

THE WASTE<br />

The decommissioning engineers<br />

developed specialist retrieval<br />

equipment to remove the fuel and<br />

isotopes <strong>from</strong> Pile 1. The so-called<br />

Fuel Channel Retrieval Tool (FCRT)<br />

can remove fuel elements and<br />

isotope cartridges remotely and<br />

transfer them to a processing<br />

facility next to Pile 1, where the<br />

debris will be segregated, put<br />

into waste liners and the radiation<br />

measured for the records.<br />

To achieve this, an access<br />

slot will be cut in the top of the<br />

reactor, the concrete pile cap,<br />

within a containment area. An<br />

overhead crane and manipulator<br />

gantry will deploy the FCRT.<br />

Cutting the access slot – using<br />

a combination of standard<br />

industrial techniques and remote<br />

operations involving core drills<br />

and diamond wire equipment –<br />

will allow the decommissioning<br />

team to dismantle and remove<br />

redundant steel structures and<br />

components within the void,<br />

followed by remotely operated<br />

deployment of the FCRT.<br />

A carbon fibre telescopic mast<br />

– carbon fibre minimises weight<br />

and avoids compromising the<br />

strength of structural components<br />

– is installed through the access<br />

slot so that the FCRT can be<br />

positioned anywhere in the<br />

discharge void to retrieve fuel and<br />

debris <strong>from</strong> channels within the<br />

graphite core. A combination of<br />

‘end effecters’ (grabs, scoops and<br />

loosening tools) operated using<br />

camera signals and controls sent<br />

through the telescopic tubes, will<br />

unblock channels, retrieve fissile<br />

material and collect the cartridges<br />

and debris in containers. A<br />

slightly smaller Isotope Channel<br />

Retrieval Tool (ICRT) will remove<br />

isotopes in the same way.<br />

The retrieved waste will go<br />

to the waste separation cell for<br />

encapsulation in an epoxy-based<br />

polymer to contain the waste<br />

for safe disposal. The use of<br />

epoxy resin to encapsulate fuels<br />

and radioactive waste has been<br />

trialled and attracted significant<br />

industry interest which could<br />

pave the way for its use in future<br />

decommissioning projects (see<br />

panel Polymeric Encapsulation).<br />

Once the fuel and isotopes<br />

have been removed, subsequent<br />

stages will include using<br />

remotely operated hydraulic<br />

grippers to remove the control<br />

and shutdown rods, followed<br />

by construction of a modular<br />

containment structure, gaining<br />

access to the core and removal<br />

of the graphite blocks. This<br />

will be done using a variety of<br />

industry-proven mechanical and<br />

thermal cutting tools, including<br />

hydraulically or electrically<br />

driven devices such as shears,<br />

diamond wire band saws<br />

and grinders, thermal cutting<br />

technologies such as plasma<br />

arc and oxy-propane torches,<br />

and gripping and lifting tools.<br />

Ultimately, this will be followed<br />

by demolition of the bioshield,<br />

once the remaining material<br />

and internal surfaces of the<br />

reactor have been removed or<br />

decontaminated.<br />

A schematic representation of Windscale Pile reactors. This shows the reactor<br />

building and the chimney with its filter gallery, <strong>from</strong> which the air was<br />

discharged having passed through the reactor. It also shows the air ducts<br />

through which air was drawn into the reactor and the water ducts which<br />

provided the export route to the adjacent cooling pond for the discharged fuel<br />

36 INGENIA INGENIA ISSUE 48 SEPTEMBER 2011 37


LESSONS FROM WINDSCALE’S NUCLEAR LEGACY<br />

WEALTH CREATION<br />

Removal of one of four 190 tonne heat exchangers <strong>from</strong> the Windscale<br />

Advanced Gas-Cooled Reactor<br />

Pressure vessel<br />

and insulation<br />

Hot box<br />

Loop tubes<br />

Neutron shield<br />

Fuel channels<br />

Graphite core and steel<br />

restraint structure<br />

Thermal shield<br />

Diagrid, Ring Beam etc<br />

A cross-section through the WAGR bio-shield and reactor vessel showing<br />

the graphite core and other structural and operational components<br />

WAGR<br />

The Windscale Advanced<br />

Gas-Cooled Reactor (WAGR)<br />

was a prototype for the UK’s<br />

second generation of <strong>nuclear</strong><br />

power stations, the AGRs,<br />

which followed on <strong>from</strong><br />

Magnox stations. WAGR started<br />

operations in 1962, shutting<br />

down in 1981. A forerunner<br />

of a family of 14 reactors on<br />

seven sites in the UK, the WAGR<br />

was CO 2 -cooled, graphitemoderated<br />

and fuelled with<br />

uranium dioxide in stainless<br />

steel cans. The reactor consisted<br />

of a graphite moderator, the<br />

structural core, 4.6 m diameter<br />

and 4.3 m high, housed in a<br />

cylindrical reactor vessel with<br />

hemispherical ends. The reactor<br />

and its heat exchangers sat in a<br />

steel containment building that<br />

was 40.8 m high and 41.1 m in<br />

diameter, the easily recognisable<br />

‘golf ball’ that came to symbolise<br />

<strong>nuclear</strong> power in the UK.<br />

The WAGR decommissioning<br />

programme had several<br />

objectives. It set out to<br />

demonstrate the feasibility of<br />

dismantling a <strong>nuclear</strong> reactor<br />

safely and at acceptable cost.<br />

The programme was also<br />

designed to establish a route<br />

and appropriate authorisation<br />

procedures for disposing of<br />

the radioactive waste. Another<br />

important task was to acquire<br />

and record the information,<br />

data and expertise that would<br />

support the design and<br />

subsequent decommissioning<br />

of <strong>nuclear</strong> power plants,<br />

especially gas-cooled<br />

reactors (see Information<br />

for Posterity).<br />

The programme has been<br />

managed through a series of<br />

one- to two-year campaigns<br />

that commenced in the 1990s.<br />

The campaigns followed a<br />

‘top down’ approach, dealing<br />

with the various structures and<br />

materials that made up the<br />

reactor’s core.<br />

These were principally:<br />

• the hot box – located above<br />

the reactor, this structure<br />

received the gas coolant and<br />

channelled it to four<br />

heat exchangers<br />

• the neutron shield –<br />

constructed of graphite and<br />

steel, this absorbed radiation<br />

to protect workers on the<br />

operating floor<br />

• the graphite core and<br />

reflector – 230 tonnes of<br />

interlocking blocks of<br />

graphite that formed a matrix<br />

to position the fuel elements<br />

• the diagrid and tundish –<br />

support structures for the<br />

graphite core, made up of<br />

90 tonnes of steel<br />

• pressure vessel – a cylindrical<br />

vessel, weighing 118 tonnes,<br />

with hemispherical ends.<br />

These components sat within<br />

the reactor’s pressure vessel<br />

which was itself supported<br />

inside a concrete bioshield (a<br />

massive structure providing<br />

structural integrity and<br />

personnel protection <strong>from</strong><br />

radiation). The sequence of<br />

campaigns was:<br />

1 install remote dismantling<br />

machine<br />

2 remove operational waste<br />

<strong>from</strong> the 253 fuel channels<br />

3 dismantle the hot box<br />

4 remove the six loop tubes<br />

5 dismantle the neutron<br />

shield<br />

6 remove the graphite core<br />

and steel restraint structure<br />

7 dismantle the thermal shield<br />

8 reduce the size of the lower<br />

structures and remove them<br />

<strong>from</strong> within the reactor’s<br />

pressure vessel<br />

9 remove the steel pressure<br />

vessel which housed<br />

the reactor core, and its<br />

surrounding insulation<br />

10 remove the two thermal<br />

columns and the outer<br />

ventilation membrane <strong>from</strong><br />

within the reactor vault.<br />

Working <strong>from</strong> the control room, the<br />

operators can use the hoist to deploy<br />

various tools, such as grabs, oxy-propane<br />

torches, shears and grinders.<br />

Hoist maintenance room<br />

8 tonne waste hoist<br />

Retractable shield door<br />

Sentencing cell<br />

slew beam<br />

Operator<br />

viewing<br />

position<br />

Carousel floor<br />

racks and baskets<br />

Existing heat exchanger<br />

raised by appox 12 m<br />

SENTENCING<br />

CELL<br />

WASTE<br />

ROUTE OUT<br />

Mast<br />

Reeling drums<br />

REACTOR<br />

VESSEL<br />

This final part of the<br />

decommissioning of WAGR<br />

was completed in the summer<br />

of 2011.<br />

The Remote Dismantling<br />

Machine (RDM) constructed<br />

for the project has played a<br />

vital role in dismantling WAGR.<br />

Operated <strong>from</strong> a purpose-built<br />

control room in a building next<br />

to WAGR, the RDM consists of an<br />

extendable mast supporting a<br />

remotely controlled manipulator.<br />

Suspended crane rails enable<br />

a three-tonne hoist to travel<br />

across the reactor vault into the<br />

adjacent cells. Working <strong>from</strong><br />

Upper containment<br />

Platform lift winch<br />

Transfer hoist cable<br />

feed system<br />

(accumulator)<br />

Lower containment<br />

and entrylock<br />

Rotating floor shield<br />

Rotating floor<br />

shield slew bearing<br />

Transfer hoist slew<br />

beam bearing<br />

To hoist and grab<br />

maintenance cell<br />

Transfer hoist<br />

slew beam<br />

3 tonne transfer<br />

hoist and grab<br />

Manipulator platform<br />

and service feeds<br />

Manipulator<br />

Concrete reactor<br />

bio-shield<br />

Diagram showing the WAGR buildings following adaptation for decommissioning. It shows the rotating Remote<br />

Dismantling Machine mounted centrally above the reactor vessel and the manipulators and hoists used to remove the<br />

components during dismantling. The route through which the waste is exported is also shown<br />

the control room, the operators<br />

can use the hoist to deploy<br />

various tools, such as grabs,<br />

oxy-propane torches, shears and<br />

grinders. A hydraulic manipulator<br />

allows these tools to move in<br />

all directions and to reach the<br />

full depth of the reactor vessel.<br />

During the programme, the<br />

decommissioning team designed<br />

specialist tools so that the RDM<br />

could perform specific tasks<br />

during the various campaigns.<br />

LESSONS LEARNT<br />

While new <strong>nuclear</strong> power stations<br />

will have decommissioning<br />

‘designed-in’, the work on WAGR<br />

has highlighted that it will still be<br />

important to take an adaptable<br />

approach to decommissioning.<br />

Technology, legislation and<br />

policy will inevitably change<br />

over the operational life of a<br />

<strong>nuclear</strong> reactor. For example, we<br />

can expect to see considerable<br />

advances in remotely operated<br />

vehicles, mobile cranes, modular<br />

and mobile plant and equipment,<br />

and the ability to decontaminate<br />

equipment. After all, there has<br />

been plenty of progress in these<br />

areas since WAGR was built,<br />

allowing the decommissioning<br />

teams to work in ways that were<br />

not possible when the engineers<br />

designed the reactors.<br />

It is also important to consider<br />

the costs of the technologies<br />

used in decommissioning. On<br />

this front, off-the-shelf equipment<br />

can often prove economically<br />

advantageous. For example, the<br />

decommissioning operators used<br />

commercial CCTV cameras on<br />

WAGR. Unlike radiation-hardened<br />

cameras. commercial cameras<br />

may not last as long, but they are<br />

considerably cheaper and the<br />

total cost is lower.<br />

Work on the WAGR also<br />

demonstrated the value of<br />

being able to adapt existing<br />

systems and structures to<br />

avoid the need to build new<br />

structures for decommissioning.<br />

38 INGENIA INGENIA ISSUE 48 SEPTEMBER 2011 39


LESSONS FROM WINDSCALE’S NUCLEAR LEGACY<br />

For example, the waste was<br />

removed <strong>from</strong> the reactor<br />

through two of the bioshields<br />

for the heat exchangers so that<br />

the decommissioning team<br />

could benefit <strong>from</strong> the shielding<br />

concrete. To achieve this, the<br />

team had to raise the heat<br />

exchangers 12 m to make space<br />

available. The operators used<br />

diamond drilling to create the<br />

openings into the reactor vault<br />

to provide access for the RDM<br />

hoist’s transport system.<br />

A further lesson learnt has<br />

been in significantly reducing<br />

the number of waste packages.<br />

Cutting the waste to appropriate<br />

sizes and careful packing ensured<br />

efficient use of the space in<br />

the waste box. It also proved<br />

beneficial to take advantage<br />

of radioactive decay to allow<br />

disposal as low-level waste rather<br />

than intermediate-level waste.<br />

The self-shielded waste package<br />

also hugely simplified handling<br />

and on-site storage.<br />

LOOKING AHEAD<br />

Having demonstrated that<br />

it is possible to manage the<br />

decommissioning of the Piles,<br />

completing their clean up is now<br />

a lower priority for the NDA than<br />

other <strong>legacy</strong> issues at Sellafield.<br />

The Piles can now move into<br />

a period of surveillance and<br />

maintenance, based on the<br />

extensive work done on the<br />

safety case, allowing the NDA and<br />

Sellafield to allocate resources to<br />

projects that have higher priority.<br />

The decommissioning of<br />

WAGR has successfully met<br />

significant challenges. This work<br />

puts the UK’s engineering sector<br />

in a strong position to contribute<br />

to the growing demand for<br />

decommissioning the many<br />

<strong>nuclear</strong> power stations that will<br />

reach the ends of their working<br />

lives over the coming years.<br />

BIOGRAPHY<br />

Peter Mann is Director PBO Support with Babcock International<br />

Group’s <strong>nuclear</strong> business. He is a chartered engineer with<br />

over 30 years’ experience in the <strong>nuclear</strong> industry, the last 15<br />

of which have been directly involved with management of<br />

decommissioning programmes, notably at Windscale where<br />

he was head of site for some 10 years, and previously at<br />

Hunterston A where he was Magnox site director.<br />

The author would like to thank Michael Kenward OBE for his help in the<br />

writing of this article.<br />

Removal of the WAGR reactor pressure vessel top dome<br />

INFORMATION FOR POSTERITY<br />

An important aspect of the work on the Windscale Piles has<br />

been in collecting and managing information. This is particularly<br />

important given the protracted timescales involved, which can<br />

run into decades. Babcock’s state-of-the-art computer-based<br />

interactive tool will enable the project to retain knowledge for the<br />

future, while aiding daily use of the documentation.<br />

The first ‘document’ to use this approach was the Interactive<br />

Safety and Environment Overview Report. This internal<br />

management and communication tool sets out the strategy, or<br />

roadmap, for the safety case and its justification. The document<br />

makes extensive use of drawings, video and animation to illustrate<br />

decommissioning concepts and schemes. In some 15,000 pages,<br />

it presents information in layers, so that users can navigate the<br />

documentation at an appropriate level of detail.<br />

The decommissioning team used similar interactive<br />

electronic techniques to develop the Decommissioning Safety<br />

Case. The user can navigate the document quickly and easily,<br />

using interactive screens. They can search the entire suite of<br />

documents for keywords, and can view videos and animations.<br />

The technique offers significant advantages in document<br />

management that could have wider future application.<br />

The UK now has a thriving <strong>nuclear</strong> decommissioning market<br />

– the Nuclear Decommissioning Authority (NDA) has successfully<br />

fostered an environment where many companies <strong>from</strong> the UK<br />

and USA compete for decommissioning work. Much of the work<br />

completed to date has intellectual proprty owned by UK and<br />

USA government agencies and is available to all, with the private<br />

sector organisations bringing further innovation to complete the<br />

hazard reduction faster and at lower cost.<br />

40 INGENIA

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