Second Moscow International Nonproliferation Conference PLUTONIUM UTILIZATION IN REACTOR FUEL A. Zro - PowerPoint PPT Presentation

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Second Moscow International Nonproliferation Conference PLUTONIUM UTILIZATION IN REACTOR FUEL A. Zro

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Title: Second Moscow International Nonproliferation Conference PLUTONIUM UTILIZATION IN REACTOR FUEL A. Zro


1
Second Moscow International Nonproliferation
Conference PLUTONIUM UTILIZATIONIN REACTOR
FUEL A. Zrodnikov Director General State
Scientific Center of the Russian Federation
Institute for Physics and Power Engineering
September 18-20, 2003
2
RUSSIAS NUCLEAR POWER AT THE THRESHOLD OF THE
21st CENTURY
  • Operating nuclear power plants
  • RBMK-1000 (11)
  • VVER- 440 (6)
  • VVER-1000 (71)
  • EGP-6 (4)
  • BN-600 (1)
  • Transport power systems
  • Research reactors
  • Nuclear fuel cycle infrastructure

3
NUCLEAR POWER STRATEGY
  • Maintenance of safe and efficient functioning of
    operating NPPs and fuel infrastructure.
  • Progressive replacement of operating NPPs with
    3-rd generation traditional power units,
    a moderate increase of generating
    capacity in the first quarter of the 21st
    century
    expanding the export potential.
  • Development and introduction of innovative
    economically competitive reactor and nuclear
    fuel cycle technologies.

4
LARGE SCALE NUCLEAR POWER FOR THE 21st CENTURY
  • Liquid-metal cooled fast reactors of inherent
    safety
  • Proliferation-resistant closed fuel cycle
  • Reduce the volume and long-term toxicity of
    nuclear wastes and radiation-balanced disposal of
    radwastes
  • Technological support for non-proliferation
  • Economic competitiveness

5
SMALL AND MEDIUM REACTORS
  • No on-site refueling and sophisticated nuclear
    infrastructure, long-lived core lasting 1020
    years
  • Completely sealed reactor, transportable to
    and from the site
  • 50 to 150 MWe class, fuel enrichment ? 20
  • Simplified design, high level of passive safety
  • Cost comparable to the cost of competitive
    systems

6
SPENT FUEL MANAGEMENT CURRENT STATUS
  • Short - term storage in cooling ponds
  • Accumulation and interim wet storage for
    subsequent placement in long-term centralized
    dry storage
  • Radiochemical reprocessing with U and Pu
    separation followed by their involvement in the
    fuel cycle

7
GENERAL PRINCIPLES FOR THE USE OFPLUTONIUM
STOCKS
  • Plutonium, as a nuclear material, has a unique
    energy potential, it is a national asset, and it
    can be put to maximum effective use under
    Russias national energy strategy
  • The ultimate strategic goal is to make full use
    of plutoniums energy potential, with the waste
    converted to a state, that makes it unusable for
    subsequent weapons-production and ensures their
    secure ecological isolation
  • Once approved, plans for plutonium utilization
    must be implemented in a manner which ensures
    that it is stored, transported and handled in
    accordance with the highest national and
    international standards in terms of nuclear
    safety, ecology, physical protection, accounting
    and control

8
PLUTONIUM CONTAINED IN SPENT FUEL
  • Totals for the country
  • As of December 31, 1999
  • Plutonium contained in spent
  • fuel at civil reactor sites 47 000kg
  • Plutonium contained in spent
  • fuel at reprocessing plants 4 000kg
  • Plutonium contained in spent
  • fuel kept elsewhere 20 000kg

9
CIVIL UNIRRADIATED PLUTONIUM
  • As of December 31, 1999
  • Unirradiated separated plutonium in product
  • storage facilities at reprocessing
    plants 30 900kg
  • Unirradiated separated plutonium in
    manufacturing
  • or fabrication and the plutonium contained
    in
  • unirradiated products at fuel fabrication or
    other
  • plants or elsewhere -
  • Plutonium in unirradiated MOX fuel or other
  • fabricated products at reactor sites or
    elsewhere 200kg
  • Unirradiated separated plutonium kept elsewhere
    900kg
  • The quantities of Pu withdrawn from the
    military sphere will be declared when placed in
    storage at PA Mayak

10
EX-WEAPONS PLUTONIUM MANAGEMENT CONCEPT
  • Reliable and controllable interim storage
  • In-pile transformation, including MOX-forms,
    into spent fuel with subsequent utilization in
    the proliferation-resistant closed fuel cycle

11
HISTORY
  • BR-5 (1959) BR-10 Obninsk
  • BOR-60 (1966) Dimitrovgrad
  • BN-350 (1972) Kazakhstan
  • BN-600 (1980) Urals
  • BN-800 (1992, design)

12
120 REACTOR/YEARS EXPERIENCE BR-10, BOR-60,
BN-350, BN-600
  • Major technological problems have been already
    solved
  • 5000 MOX fuel rods have been irradiated
  • Closed fuel cycle is realized for BOR-60
  • Pyrochemical technology and vibro-compacted MOX
    can significantly decrease cost and terms
  • Advanced design of BN-800 is available

13
BN-600 NUCLEAR POWER REACTOR
Electricity to the consumer
Transformer
Control rods
Steam generator
Generator
Turbine
Cooling water pond
Condenser
Circulation pump
Feedwater pump
Fuel
Main coolant pump of the secondary circuit
Main coolant pump of the primary circuit
14
BN-800 REACTOR
1 - primary pump 2 - large rotating plug 3 -
refueling mechanism 4 - small rotating plug 5 -
central rotating column with control and
scram system mechanism 6 - upper stationary
shield 7 - reactor vessel 8 - guard vessel 9 -
heat exchanger 10 - core
15
BN-600 CURRENT STATUS
  • Hybrid core as the first stage,
  • 280 kg Pu/year
  • 100 MOX fueled core,
  • 1250 kg Pu/year
  • Some features of MOX fuel

16
BN-600 CURRENT STATUS (cont.)
  • Radiation characteristics of fuels
  • Neutron radiation rate, Gamma radiation rate,
  • Fuel n/s SA
    ?/s SA
  • fresh irrad. fresh
    irrad.
  • UO2 4.8 ? 102 1.2 ? 105
    2.9 ? 109 4.5 ? 1014
  • MOX (wPu) 6.7 ? 105 1.3 ? 106 1.1 ?
    1012 5.2 ? 1012

17
SCENARIOS OF THE EX-WEAPON PU STOCK-PILE
REDUCTION IN RUSSIA
18
PLUTONIUM NON-PROLIFERATION ISSUES
  • Storage and management
  • Reliable security measures
  • Safeguards and control
  • Minimum personnel with authorized access
  • Minimum handling operations
  • Minimum transportation
  • Minimum sites with plutonium handling
  • Conversion into spent fuel
  • Dilution in MOX fuel
  • Cladding and assembling
  • Irradiation in nuclear reactors

19
PLUTONIUM NON-PROLIFERATION ISSUES (cont.)
  • Unified models for non-proliferation analysis
    ISTC project and bilateral collaboration
  • Is closed cycle potentially less protected to
    proliferation than open one?
  • How does BN-800 minimize the proliferation risk?
  • Development of an internationally
  • recognized methodology for the
  • quantitative assessment of the
  • proliferation risk

20
CLOSED NUCLEAR CENTER CONCEPT
  • Russian specific features
  • - rather large territory
  • - many sparsely populated regions
  • MAYAK site in South Urals
  • - RT-1 reprocessing plant, in operation
    now
  • - 30 t of civil Pu are stored
  • Complex-300 MOX fuel fabrication plant
  • BN-800 fast reactor

21
OPTIONS FOR TRANSPORTATION AND STORAGE OF MOX
FUEL
22
INTERNATIONAL COOPERATION
  • Russian - US cooperation
  • Russian - French - German Research Program
  • Russian - Canadian collaboration
  • Russian - Japanese cooperation

23
Conclusions
  • The use of existing fast BN-600 reactor and,
    subsequently, fast BN-800 reactor (to be
    constructed) makes it possible to consume 50MT of
    weapons plutonium by the year 2020 and to reduce
    the cost of the Russian Ex-W Pu disposition
    Program.
  • Dual-use BN-800 reactor (Ex-W Pu utilization and
    the new electricity production) opens
    opportunities for potential investment options.
  • There are no proliferation concerns with the fast
    reactor technology at the stage of final
    disposal elimination of the breeding zones in
    both BN-600 and BN-800 could be the first step to
    a more self-protected fast reactor technology.
  • Closed nuclear centers are the best way to ensure
    the non-proliferation of fissile materials,
    especially ex-weapons plutonium in Russia.
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