+ All Categories
Home > Documents > International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7...

International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7...

Date post: 18-Dec-2015
Category:
Upload: ami-mcdonald
View: 231 times
Download: 4 times
Share this document with a friend
Popular Tags:
17
Transcript
Page 1: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.
Page 2: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

International Conference for Spent Fuel Management

from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage”

Meet the Challenges of Spent Fuel Interim Storage by using intensive Innovation

Justo GARCIA

31 May – 4 June 2010

Vienna, Austria

TN INTERNATIONAL

Page 3: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -3-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Interim Storage technologies2 technologies

Dry Interim StorageWet Interim Storage

Metallic casks: Dual-purpose casks Passive system, and independent to the plant Germany, Belgium, Switzerland, Spain, Japan, USA AREVA Solutions: TN®24 family

Canister systems: The fuel is stored in a metallic canister, stored inside an overpack To transport the fuel, the canister is inserted in a transport cask Passive system, and independent to the plant USA, Spain, Republic of Armenia AREVA Solutions: NUHOMS® System

Spent fuel storage pool

Spent fuel stored inside racks

AREVA Solutions: Racks and Pools

Page 4: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -4-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

To meet all these challenges, the Logistics BU engaged a step of innovation to develop competitive, efficient and relevant transport and storage solutions & underwater storage racks

Innovation within AREVA Logistics BU

Dry Storage innovative Solutions

Innovation – a key driver within the Logistics Business Unit

Recent increase of massive forged pieces demand in the industry

Nuclear Renaissance

Tough Competition

Need to anticipate regulatory evolutions

Adaptation to the dry storage market internationalization

Be ready for higher enrichment, burn-up…

Offer competitive casks with larger capacity

An increasing market for fuel management solutions

worldwide

Design casks compatible with decommissioning strategies

New Rack Designs

Page 5: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -5-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®DUO,The new line of dual purpose casks

TN®DUO concept The massive shell is composed by

several forged pieces neutron shielding surrounding the

forged shell Aluminum heat exchanger basket mainly based on aluminum with

boron

Robust to aircraft crash

Retrievability of stored components

Passive system

Same or similar operating procedures as TN24 family TN®DUO in Transport configuration

& in Storage configuration

Page 6: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -6-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®DUO Basic ConceptShielding of radiation

Vessel in forged steel providing the main gamma shielding An external layer of neutron shielding resin covered by an outer steel shell

Safe enclosure of radio-active material: the forged steel body and the lids equipped with metallic gaskets make the containment

Leak tightness Permanent monitoring system demonstrates the high efficiency of the containment barrier

Subcriticality of the package Basket made of boronated aluminium and/or stainless steel

Removal of decay heat Aluminium heat exhanger between the cask body and the cask external surface

Mechanical strength The shock absorbing covers provide the protection required for transport licensing. Anti-aircraft crash cover provides the protection against an airplane crash on the storage

facility (if required by storage regulation)

Page 7: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -7-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®DUO contentBWR version

Cask availability 2015

Capacity:

52 to 68 BWR Intact Fuel Assemblies

Fuel:

Max Burnup: 70 GWd/MTU

Max Initial Enrichment: 5 wt % U235

PWR versionCask availability 2015

Capacity:

24 to 37 PWR Intact Fuel Assemblies

Fuel:

Max Burnup: 65 GWd/MTU

Max Initial Enrichment: 5 wt % U235

Page 8: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -8-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®DUO Advantages

The result of an intensive innovation process

TN®DUO Cost effectiveness

Simplification of the cask assembly New and innovative formed aluminum heat exchangers Shock absorbing covers are constituted of steel sheets

Security of supply and manufacture and standard manufacturing process

Use of common forged pieces

Time of supply and manufacturing is reduced

Same operating procedures and tools as TN®24 cask family

Page 9: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -9-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®NOVA system, The new line of canister system

TN®NOVA System Spent fuel stored inside a canister Metallic storage overpack Storage in vertical position Horizontal transfer mode + cask uprighted in a vertical position

for storage : no critical lift outdoors. Robust to aircraft crash Retrievability of stored components Passive system

CanisterTransport cask Storage Overpack

Page 10: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -10-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®NOVA Basic ConceptStorage system The welded canister is transported in a transport/transfer cask to the storage site The canister is then pushed into the TN®NOVA overpack in horizontal position The TN®NOVA overpack is then uprighted in a vertical position for storage.

Main technical features Radiation Shielding during storage

TN®NOVA overpack surrounds the canister with steel plates and neutron shielding Safe enclosure of radioactive material

Canister makes the containment with welded closures Leak tightness

By multiple welded barriers of the canister / No monitoring required Subcriticality of the package

Basket made of boronated aluminum and stainless steel Removal of decay heat during storage

Air circulation by natural convection

Operations: the TN®NOVA overpack is equivalent in terms of function and operational sequence of the NUHOMS® storage module.

Page 11: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -11-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Dry Shielded Canisters (DSC)69 BTH DSC

License availability 2010 (Part71)

Available 2013

Capacity:

69 BWR Intact Fuel Assemblies w/ Control Components

Fuel:

Max Burnup: 70 GWd/MTU

Max Initial Enrichment: 5 wt % U235

37PTH DSCLicense availability 2010 (Part71)

Capacity:

37 PWR Intact Fuel Assemblies w/ Control Components

Fuel:

Max Burnup: 65 GWd/MTU

Max Initial Enrichment: 5 wt % U235

Page 12: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -12-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

TN®NOVA Advantages

The result of an intensive innovation process

TN®NOVACost effectivenessSeparating transport and storage functions:

flexibility to spent fuel strategySimple and proven loading procedureNo thermal constraints on the TN®NOVA

storage overpackHigh loading flexibilitySecurity of supply and manufacture with

common raw goods and standard manufacturing process

Page 13: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -13-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Underwater Fuel storage RacksThe fuel racks design enables to store fuel assemblies in a spent fuel storage pool

The racks are consisted of stainless steel and poison materials

The heart of the solution is the poison containing plates situated between the spent fuel elements.

Page 14: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -14-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Underwater Fuel storage Rack Design

The European design consists in: A stainless steel structure defining

adjacent cells (“central structure”),

“Individual tubular structures” (called “sleeves”) inserted in these adjacent cells.

The sleeves are composed of the main elements:

Four angle beams which define the lodgement in which one the fuel assembly is inserted,

Borated plates placed behind the corner beams linked to these beams by stainless steel mounting brackets welded onto the angle beams.

Page 15: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -15-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Thanks to a specific technology developed for the dual purpose cask high capacity baskets, AREVA Logistics BU developed in 18 months 3 rack designs:

European & Chinese Markets Designs using BSS or boron MMC as poison material

US Market Design using boron MMC as poison material (NUSTOR™)

AREVA Logistics BU has prepared the most comprehensive rack models in the industry using the state-of-the-art computer codes and analysis techniques.

The criticality analysis for the racks is also state-of-the-art and includes:

The latest international AREVA fission product experimental data which provides the backup for the burn-up credit analysis for the most versatile and dense racks

The use of qualified poison material for criticality protection assurance. The use of the same readily available poison material used with the Dual purpose

casks and Dry Storage Systems designed by AREVA BUL

Racks for Wet Interim Storage

Page 16: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -16-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Cost effectiveness with the use of high performance neutron absorbing material “boron MMC”

Significant reduction of weight of the racks that simplify the operations of transportation and handling

Flexibility design: MMC or BSS as poison material

AREVA Logistics BU Racks Advantages

Rack manufactured by AREVA Logistics BU & View of MMC plates

Page 17: International Conference for Spent Fuel Management from Nuclear Power Reactor Session 7 “Technological Innovations for Spent Fuel Storage” Meet the Challenges.

Meet the Challenges of Spent Fuel Interim Storage – J. Garcia – IAEA 31 May – 4 June 2010 – Vienna, Austria -17-

TN INTERNATIONAL

Th

is d

ocu

me

nt

an

d a

ll i

nfo

rma

tio

n c

on

tain

ed h

ere

in i

s in

telle

ctu

al p

rop

rie

tary

to

TN

In

tern

ati

on

al.

Th

ey

sh

all

no

t b

e d

isc

lose

d,

in w

ho

le o

r in

pa

rt,

wit

ho

ut

its

au

tho

ris

atio

n.

Conclusion

A step of innovation has been engaged in order to develop new products and

services.

The AREVA Logistics Business Unit is ready to accompany customers

challenges and to respond to the future needs …


Recommended