nuclear energy planning

7/22/2019 Nuclear Energy Planning

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IAEA Tools forNuclear Energy System Modelling

NESA Support Package

IAEA/INPRO group


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WS NESA Kazakhstan, 2011

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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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3

Development of energy demand scenarios

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


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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6

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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7

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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14

Demo Cases

Base variant


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15Selected output data


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16

Selected output data


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17



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20

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



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

30


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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



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


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


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

nuclear energy planning

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