nuclear energy planning
TRANSCRIPT
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IAEA Tools forNuclear Energy System Modelling
NESA Support Package
IAEA/INPRO group
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Part II IAEA Tools for Nuclear Energy System Modelling
Content
Introduction
Modelling of NES
Specification of the NESof NES; Modelling of NES using
IAEA codes
NES modelling code toolbox
DESAE NFCSS
MESSAGE
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Development of energy demand scenarios
National, regional, global
National, regional, global
Specification of the potential role of nuclear power
to contribute to mix of energy supply
Selection of components of NES
Modelling of NES
Assessment of NES against all INPRO methodology
criteria of economics, infrastructure, waste management,
proliferation resistance, physical protection, environment,
and safety.
All INPRO
Criteria fulfilled?
Sustainable NES
NOTechnology
Developer
Define new RD&Dor redefine RD&D
goals
Energysystem
planning
NESAusin
gtheINPRO
method
ologycvcc
Evaluation of energy supply options
National, regional, global
Assembling information needed for assessment of NES
NOTechnology
User
Modify NES
YES
Modelling of NES
DESAE,NFCSS,
MESSAGE
MAED,MESSAGE,
WASP,FINPLAN,SIMPACT,
Tools
Modelling of
NES
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4Specification of the NES ;
1.
Full scope
2.
Limitedscope
3.Awareness
a.
Technology
developers
b.
Experiencedtech. users
c.Newcomers
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Modelling of NES using IAEA codes
NES modelling activities help to select a
NES. INPRO is offering support toselect/define a NES via providing analyticalIAEA tools that can help to define a NES (or
several NESs), in particular MESSAGE,NFCSS and DESAE
These activities make sense when the NESshows a certain level of complexity
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DESAE(Dynamic of Energy System Atomic Energy created by unk groups KI)
DESAE is the interactive NFC simulation code for quantitative assessment of nuclear energy
system key indicators
NFCSS (VISTA) is Nuclear Fuel Cycle Simulation System which estimates nuclear fuel cycle
service and material requirements as well as material arising for the each stage of the nuclearfuel cycle.
NFCSS VISTA)
MESSAGEModel for Energy Supply System Alternatives and their General Environmental impacts
MESSAGE is IAEAs large-scale dynamic systems-engineering, economic optimization modelthat is used for development of medium- to long-term energy scenario and policy analysis.
NES modelling code toolbox
for MFA analysis
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Overview of DESAE code
Based on INPRO Material
Department of Nuclear Energy
International Atomic Energy Agency
Capabilities of DESAE code;
Input/output data; DESAE material flow; DESAE reactor Data Base;
Demo Cases
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The main capabilities of DESAE code
Dynamic of Energy System Atomic Energy
The main capabilities of DESAE code
Modelling of the different fuel cycle
Open fuel cycle Close fuel cycle U-Pu fuel cycle U-Th fuel cycle Pu-Th fuel cycle
Calculations of material flow Tracing of isotopes Calculation of economic parameters
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DESAE code input/output DATA
INPUT DATA
Reactor Types
ReactorThermal/ElectricityCapacities(as a function of time)
Technical and economicdata of reactors and fuelcycles
DESAEMAIN OUTPUT DATA
Natural parameters:
- Energy production;- Natural Uranium requirements;-Enrichment-Depleted Uranium
-Fuel fabrication-Spent Fuel;
- Isotopes tracing ;-Radio toxicity-Decay heat;
Economics:-Required Investments-Fuel cycle costs;
DESAE_2.2.lnk
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10DESAE Flow sheet
Natural U
Natural The
Reactors
(7 types)
ReactorStorage*.
Long timeStorage.
YM Storage
Back End.
Reprocessing
Plant
(4 types)
Isotopes of fuel cycles
Th-230, Th-232
U-232, U-233,U-234,U-235,U-236,U-238
Np-237
Pu-238,Pu-239,Pu-240,Pu-241,Pu-242
Am-241,Cm-244,
I-129, Tc-99
xx- users isotope
Back End
fission products
Fabrication
Enrichment U
Depleted U
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11DESAE Reactor Data Base
DESAE_2.2.lnk
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12Input data
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13Demo Cases
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Demo Cases
Base variant
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15Selected output data
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Selected output data
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Selected output data
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Selected output data
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Selected output data
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DESAE: short description
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21DESAE materials: manual
(working materials)
DESAE_2.2.lnk
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22DESAE application in IAEA Member states and in INPROglobal vision studies on nuclear capacity growth and
material flowsNuclear Energy Development in the 21st Century: Global Scenarios and Regional Trends
IAEA Nuclear Energy Series No. NP-T-1.8, STI/PUB/1476 (2010)
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23Overview ofNuclear Fuel Cycle Simulation System
(NFCSS)
Based on Material of Nuclear Fuel Cycle and Materials Section
Department of Nuclear Energy
International Atomic Energy Agency
NFCSS Background;
NFCSS Material Flow; Reactor Module, CAIN;
NFCSS Web Site;
NFCSS TECDOC (TECDOC-1535).
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NFCSS, Background
Developed in 1997 for the Int. Symp. On Nuclear
Fuel Cycle and Reactor Strategies: Adjusting to New
Realities. Previous tools were too simple or too complex.
Purpose was to analyse the nuclear fuel cycle service
and material requirements for once-through and
recycling options.
Optimum mixture of simplicity, accuracy and speed.
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NFCSS, Main Characteristics
Scenario based simulation system
Estimation of long-term fuel cycle material and service
requirements Calculation of actinide accumulations
Current state: suitable for commercially existing reactor and fuel
types Two fuel cycle options: once-through and thermal recycle
New reactor and fuel types can also be studied by providing
necessary information and modelling appropriately Developed in MS Excel, currently available as web based
application
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NFCSS, Information Flow
Input Output
NFCSS
Strategy Parameters Nuclear power projections
Reprocessing-recyclingstrategies
Reactor mixtures
Load factors
Fuel Parameters Avg. discharge burnup
Avg. initial enrichment Avg. tails assay
Control Parameters Share of MOX fuel in core
Lead and lag times for
different processes
# of reprocessing cycles
Natural uranium requirements
Conversion requirements
Enrichment requirements
Fresh fuel requirements
Spent fuel arisings
Plutonium accumulation
Minor Actinide accumulation
Reprocessing requirements
MOX fuel fabrication
requirementsCAINCalculation of
Actinide
Inventory
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NFCSS Nuclear Material Flow Model
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NFCSS Reactor Model (CAIN)
Initial Composition of Fuel
(initial fissile content)
Average Discharge Burnup
Cooling Time
Fission, Capture and n2n
Cross Sections (burnup
average, one group)
Half Lives
Average Neutron Flux
(burnup average, one group)
Specific power
CAIN Isotopic Composition
User Input
From Library
Output
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NFCSS, Calculation Process
Nuclear Power
Discharge Burnup
Load Factor
Thermal Efficiency
Cooling and
process times
Init. Enrichment
Tails Assay
Fresh Fuel
SF Discharged (*)
SF to be
reprocessed (*)
SF to be stored (*)
SF reprocessed (*)
Enrichment
Conversion
Uranium Tails
Natural
Uranium
(*) CAIN module calculates isotopic composition
Fuel residence
timesMOX
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30INFCIS (The Integrated Nuclear Fuel
Cycle Information System) web site(http://wwwnfcis.iaea.org/).
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NFCSS, Web Site, Background
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NFCSS, Web Site, Description
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NFCSS, Web Site, Modeling
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NFCSS, Web Site, Example
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NFCSS, Web Site, Calculation
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NFCSS, Web Site, Full Version
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NFCSS, Full Version, Program Operation
Scenario Preparation
1. Creating a New Scenario or Selecting Existing Scenario to work
2. Selecting reactor and fuel types for the current scenario
3. Editing scenario description
4. Editing scenario data for each of the reactor and fuel types in the
current scenario
Calculations and Results
5. Calculating isotopic compositions for each fuel type in each reactor
type in the current scenario or providing isotopic composition table
6. Calculating material flow for each reactor type in the current scenario
7. Calculating overall material flow for all reactor types in the current
scenario
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O ll M i l Fl R l i T bl F
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WS NESA Kazakhstan, 2011Material Flow Table
Overall Material Flow Result in Table Form
See result in
chart
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O ll M t i l Fl R lt i Di
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Material Flow Diagram
Overall Material Flow Result in Diagram
See result in chart
Result year
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NFCSS TECDOC
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NFCSS, TECDOC
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Code was successfully used for modelling of
the NES selected for GAINS Code had to further elaborate its capacities
and update its databases to perform the
study
NFCSS application in IAEA INPRO/GAINS study
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IAEA D t b R l t d t th N l F l C l
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Member States
(Contact Points)
Consultants
IAEA Meetings
Reliable
Publications
Information
Sources
http://www-nfcis.iaea.org
Navigation through
facilities/deposits/records
Search capabilities
Summary reports for country specific
or worldwide
Country nuclear fuel cycle profiles
Long term nuclear fuel cycle
requirements for different scenarios
Nuclear power
projections
Nuclear fuelcycle options
Reactor physics
calculations
Inputs
NFCIS : Nuclear Fuel Cycle Information System
UDEPO : World Distribution of Uranium Deposits
PIE : Post Irradiation Examination Facilities Database
NFCSS : Nuclear Fuel Cycle Simulation System
MADB : Minor Actinide Property Database (in preparation)
IAEA Databases Related to the Nuclear Fuel Cycle
43MESSAGE capabilities
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MESSAGE capabilities
for modelling of NE scenariosBased on Material of Planning and Economic Studies Section
Department of Nuclear Energy
International Atomic Energy Agency
Once-through nuclear fuel cycle;
Partly closed NFC based on thermal reactors withplutonium mono-recycling ;
Closed NFC based on thermal and fast reactors with Pu
multirecycling
44Global Nuclear Energy System based on
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LWR and HWR with once-through
nuclear fuel cycle.
The reactors and fuelsto be consideredare:
HWR using naturaluranium fuel;
LWR using UOXfuel,
ALWR using UOX fuel.Fabrication
HWR
Dep U
Enrichmentplant
Conversion U
FabricationLWR fuel
LWR
HWR SF
LWR SF
HWR
Conversion U
Enrichmentplant
FabricationALWR fuel
ALWR ALWR SFConversion U
FabricationHWR
Dep U
Enrichmentplant
Conversion U
FabricationLWR fuel
LWR
HWR SF
LWR SF
HWR
Conversion U
Enrichmentplant
FabricationALWR fuel
ALWR ALWR SFConversion U
MESSAGE energy chain of NES
45Demand structure
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Demand structure
46Mass flow MESSAGE outputs for open fuel cycle
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Mass flow MESSAGE outputs for open fuel cycle
Natural uranium consumption (file cumNatU)Fresh fuel requirements (file FF)
SWU consumption (file SWU)Spent nuclear fuel in storages (file SF)
47Economic results of MESSAGE modelling for
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Economic results of MESSAGE modelling for
once-through fuel cycle
Annual Investments inNPP
Annual expenditure onFuel Cycle and annualexpenditure on O&M ofNPP
LUAC&LUOM (LevelizedUnit Amortization Cost andLevelized Unit Operationand Maintenance cost.)
48Global Nuclear Energy System based on LWR
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and HWR with partly closed nuclear fuel cycle
Rep U
Pu UMA
FP
LWR MOXSF
LWR_MOX
FabricationHWR fuel
FabricationLWR MOXfuel
Dep U
Enrichmentplant
Conversion U
Fabrication
LWR fuel LWR&
HWR SF
LWR SF
HWR
LWR MOXReprocessing
plant
Conversion U LWRReprocessing
plant
Pu
HWR using natural uranium fuel;
LWR using UOX fuel,LWR using UOX and MOX fuels.
49Mass flow MESSAGE outputs for partly closed
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fuel cycle
Nuclearelectricity
generationstructure
Fresh fuel
requirements Natural uranium
consumption
Reprocessingrequirements
50Economic results of MESSAGE modelling for
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g
partly closed fuel cycle
Annual Investments inNPP
Annual expenditure onFuel Cycle and annualexpenditure on O&M of
NPP LUAC&LUOM (LevelizedUnit Amortization Costand Levelized Unit
Operation andMaintenance cost.)
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Global Nuclear Energy System based on thermal and fast
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Global Nuclear Energy System based on thermal and fast
reactors with recycling of Pu recovered from LWR andmultiple recycling of Pu recovered from FRs
Rep U
Pu
U
MAFP
Pu loses
FR_MOX&blSFFR_MOX
FabricationHWR
Fabrication bl.Fuel
Dep U
Enrichmentplant
Conversion U
FabricationLWR&ALWR
fuel
ALWR
HWR SF
LWR SF
HWR
FR&blReprocessing
plant
Conversion U LWRReprocessing
plant
Pu
FabricationMOX Fuels
LWR
ALWR SF
Rep U
Pu
U
MAFP
Pu loses
FR_MOX&blSFFR_MOX
FabricationHWR
Fabrication bl.Fuel
Dep U
Enrichmentplant
Conversion U
FabricationLWR&ALWR
fuel
ALWR
HWR SF
LWR SF
HWR
FR&blReprocessing
plant
Conversion U LWRReprocessing
plant
Pu
FabricationMOX Fuels
LWR
ALWR SF
HWR using natural uranium fuel;LWR using UOX fuel,ALWR using UOX fuel.FR using MOX fuels for core and depleted uranium for blankets.
52Selected MESSAGE outputs for closed fuel cycle
i h l i l i li
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Fresh fuel requirements;Enrichment requirements;Nuclear electricity generation structure; Natural uranium consumption;
with plutonium multi-recycling
Reprocessing requirements;Spent fuel accumulation.Annual Investments in NPP and FC
Annual expenditure on Fuel Cycle and annual expenditure on O&M of NPP
53MESSAGE materials: Users Guide for ModellingN l E S t ith MESSAGE
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Nuclear Energy Systems with MESSAGE
(Draft)
Users Guide provides a step-by-step guidance tocreate mathematical models representing nuclear
energy systems to the level of detail as necessary.
The User Guide presents three demonstrationcases including modelling a nuclear energy systembased on thermal and fast reactors with fully closed
fuel cycle.
54GAINS Fuel Cycle Options modelled with
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MESSAGE
BAU, Business as usual : NES based on thermal reactors with once-through nuclear fuel cycle (OT-NFC) without spent fuel reprocessing;
FR Introduction in BAU: NES based on thermal and fast reactors withinclusion of plutonium multi-recycling in fast reactors (BR ~1.0, ) withmixed oxide fuels;
FR12 Introduction in BAU:NES based on thermal and fast reactorswith inclusion of plutonium multi-recycling in fast reactors (BR ~1.2, )with mixed oxide fuels
FRMA Introduction in BAU:NES based on thermal and fast reactorswith inclusion of plutonium and MA multi-recycling in fast reactors (BR~1.2, ) with MOX&MA fuels
Th Introduction in BAU:Thorium Fuel Cycle based on Thermal andFast Reactors with spent fuel reprocessing and Pu/U233 recycling
MSR IntroductionFuel continuous feeding and discharge(reprocessed)One half of the fuel in the core, while the second one out of the coreFeeding fuel - Np, Am and Cm from LWR, ALWR and FR spent fuelv
55Analysis of Other NES Issues with MESSAGE
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Non-geographicalgroup model
Conversion
SFEnrichm
entplant
De
p
U
Fabrication
plant
TR
U
OX
Separeted
Pu
MA,
FP
FR
Fabrication
plantM
OX
Conversion
SF
Reprocessin
gplant
Enrichmentpla
nt
De
p
U
Fabrica
tionplant
TR
UOX
Convers
ion
SFEn
richmentpl
ant
Dep
U
Fa
bricationplant
TR
UOX
SeparatedPu
MA, FP
FR
Fabricationplant
MOX
Conversion
SF
Reprocessingplant
Enrichment
plant
Dep U
Fabricationplant TR UOX
ConversionSF
Enrichmentplant
Dep U
Fabricationplant
TR UOX
FR
RD&D cost in
transition to aNES CNFC-FR
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Summary
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y
MESSAGE model has capability for simulation and optimization of : Nuclear Energy System based on LWR and HWR with once-
through nuclear fuel cycle,
Nuclear Energy System based on thermal and fast reactorswith Pu multi-recycling
scenarios with the introduction of MSR systems, scenarios based on Thorium Nuclear Fuel Cycle,
Global and Non-geographical group approach, RD&D cost for introduction of innovative reactor technology
It allows to assess: Optimal Schedule for introduction various reactor technologies
and fuel cycle options Infrastructure facilities Nuclear material flows and wastes Investments, RD&D and other costs
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Application of IAEA modelling codes for INPRO
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Preliminary computer analysis of scenarios by usingDESAE , MESSAGE and NFCSS codes No single tool can be expected to respond well to all modelling requirements for NES
assessment. Various models can be used as a package for assessment purposes. DESAE&NFCSS&MESSAGE can be linked and used in tandem to perform some relevant
analysis required for NES assessment.
The same NES can be modelled with DESAE&NFCSS&MESSAGE codes in order to usestrengths of each code and obtained necessary results for NES assessment.
Evaluation of the tools
DESAE, MESSAGE, NFCSS for modelling scenarios identified inJS, GAINS, FINITE, ThFC collaboration projects.
Application of IAEA modelling codes for INPRO
assessment studies
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Thank you for your attention
www.IAEA.org/INPRO
59Brief code information
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NFCSS MESSAGE DESAE
Software Availability To interested people fromIAEA MS upon a
registration andauthorization at the sitehttp://www-nfcis.iaea.org.
Via Responsible officer(below) Via Responsible officer(below)
Responsible officer Tulsides Harikrishnan
Nucl. Fuel Cycle &Materials Section/NEFWTel.: +43 1 2600-22758E-mail:
[email protected]://www-nfcis.iaea.org
Jalal Ahmed Irej
Department of NuclearEnergyPlanning & EconomicStudies Section
Telephone: (+431)2600-222780E-mail: [email protected]
Peter Gowin
INPRO group,Division of Nuclear Power,NETel.: +43 1 2600-22848
E-mail: [email protected]
Manual IAEA TECDOC 1535 Manual Within the modelsoftware
Manual ( working material)
Training Yes (regular) Yes (regular) Yes (on request)
Tutorial/Demo cases Yes Distance Learning Packagetogether with Demo Cases
Yes
Familiarization/ Casecreation time
One week Two weeks for training and3-4 months for a real casestudy
One-Two weeks
Flexibility for case creation Middle Very High Middle
Optimisation capabilities No (variant simulation) Yes No (variant simulation)
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DESAE code in INPRO methodology
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gy
Economics
Environment
Safety
Proliferation
Resistance
Infrastructure
Investments NPP&NFC,
current prise,
discounting cost
Uranium consumption,
Spent fuel, Isotopes quantity,
Waste activity, Minor actinide
quantity & activity
Recycling fuel quantity, Pu&U3 in
spent fuel,
Pu&U3 after recycling, SWU
quantity
WasteManagement
Expert place