MYRRHA Multi-purpose HYbrid Research Reactor for High-tech Applications 2

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MYRRHA, the Multi-purpose hYbrid Research

Reactor for High-tech ApplicationsDidier De Bruyn, Hamid At Abderrahim, Peter Baeten,

Rafal Fernandez & Jeroen Engelen

SCKCEN

SILER Training Course

Verona, 21-25 May 2012

Copyright 2012

SCKCEN

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Table of contents

Purpose of the MYRRHA project

Plant layout & reactor building

Primary system

Way ahead to construction

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Global issues for nuclear energy

Common needs

Reducing cost of

ultimate waste

Burning legacy

of the past

Better use ofresources

Enhance Safety

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Fission generates High-Level Nuclear Waste

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U235

n

Pu Np Am Cm

Actinides MinorActinides

Neutron

Uranium Fission

Fuel

U238

n

n

n

U235

U238Plutonium Neptunium Americium Curium

Minor Actinides

high radiotoxicity long lived waste

that are difficult to store due to:

Long lived (>1,000 years)

Highly radiotoxic

Heat emitting


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spent fuel

reprocessingno

reprocessing

Uranium

naturel

Time (years)

Relativeradio

toxicity

transmutation

of spent fuel

Duration Reduction

1.000x

Volume Reduction

100x

Motivation for Transmutation

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ReactorSubcritical mode

65 to 100 MWth

Accelerator

(600 MeV - 4 mA proton)

Fast

Neutron

Source

Spallation Source

Lead-Bismuth

coolant

Multipurpose

Flexible

Irradiation

Facility

MYRRHA - Accelerator Driven System

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MYRRHA should be a multipurpose facility

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MultipurposehYbridResearchReactor forHigh-tech

ApplicationsWaste

Fission GEN IV Fusion

Fundamental

research

Silicon

doping

Radio-

isotopes

50 to 100 MWth

FFast= ~1015 n/cm.s

(En>0.75 MeV)

F= 1 to 5.1014 n/cm.s

(ppm He/dpa ~ 10)

in medium-large volumes

Material research

FFast= 1 to 5.1014 n/cm.s

(En>1 MeV) in large volumes

Fuel research

tot= 0.5 to 1.1015n/cm.s

Fth= 0.5 to 2.1015 n/cm.s

(En


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Continuity: SCKCENhas a long traditionof first of a kind

Inventor of

innovative nuclear

fuel (MOX fuel)

1st pressurized water

reactor (PWR)

outside of US (BR3)

World first underground

laboratory for R&D on HL

waste disposal (HADES)

World premiere project

for transmutation of

nuclear waste

Highest performing

material testing reactor

in Europe (BR2)

World first

lead based ADS

(GUINEVERE)

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The place of MYRRHA within Generation IV

9http://www.gen-4.org/GIF/

Sodium F ast ReactorSodium F ast Reactor

Lead Fast Reactor

Molten Salt ReactorMolten Salt Reactor

Gas Fast ReactorGas Fast Reactor

Supercr iti cal Water-cooled ReactorSupercr iti cal Water-cooled ReactorVery High Temperatur e ReactorVery High Temperatur e Reactor


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ALLEGROExperimental reactor

(GFR)

ASTRID

Prototype

(SFR)

2008 2012 2020

SFR

Supporting infrastructures, research facilities

MYRRHAETPP European

demonstration reactor(LFR)

Reference

technology

Alternative technology

LFR

GFR

The place of MYRRHA in ESNIIEuropean Sustainable Nuclear Industrial Initiative

MYRRHAFast spectrum

irradiation facility

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Objective of MYRRHA : replace the existingBR2 as a Multipurpose Irradiation Facility

Material

Testing Reactor

(fission)

Fuel testing

for LWR &

GEN II/GEN III

Irradiation

Services:- Medical RI

- Silicium Doping

- Others

Fast Neutron

Material

Testing Reactor

(fission + fusion)

ADS-Demo

+

P&T Testing

(Partitioning &Transmutation)

Irradiation

Services:- Medical RI

- Silicium Doping- Others

Fuel testing for

LFRGEN IV

LFR European Technology Pilot Plant (ETPP)

1962

BR2

2024

MYRRHA

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MYRRHA is an international project

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http://www.ciemat.es/portal.do


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Part 2

Plant layout & reactor building

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Evolution of the reactor building& layout concept

Before 2000: a building concept was sketched,

when the accelerator was still a cyclotron;

MYRRHADraft 2 (2005):

OTL (UK) performed a conceptual study;

Tractebel (BE) did stability and costs estimates.

FP6 EUROTRANS (2005-2009):

building concept of 2005 was kept as such,

but the plant layouthas been developed.

FP7 CDT (20092012):

Both building shape and plant layout optimized.

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Todays concept of plant layout

REACTORBUILDING

FRONT-END

ACCELERATOR

LINAC +RF GALLERY

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General layout

REACTOR

BUILDING

LINAC

VITO SCK-CEN

RF

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Vertical section in the Reactor building

SECTION BB17


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Horizontal section in the Reactor building

LEVEL 0018


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Horizontal section in the Reactor building

LEVEL 9119


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Vertical section in the Reactor building

SECTION AA20


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Some logistical flows that we consider

Entrance of new components & experiments in the reactor hall;

Entrance of equipment elsewhere;

Evacuation of experiments after irradiation;

Evacuation of solid, liquid & gaseous wastes; Evacuation of bending magnet;

Entrance & evacuation of silicon & isotopes;

Pumping of LBE reactor vessel reserve tank;

Replacement of diaphragm & reactor cover; Personnel inside reactor building.

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Illustration n1:entrance new components & experiments

Level 00

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Illustration n2: evacuation of experimentsafter irradiation (1/3)

From: level 00

To: level 92

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From: level 92

To: level 00

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From: level 00

To: outside

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Workflow experiments in other direction

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Illustration n3:evacuation of waste (1/4)

From: level 00

To: level 92

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From: level 92

To: level 93

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From: level 93

To: level 00

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Workflow waste in other direction

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Part 3

Primary systems


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Reactor Vessel Reactor Cover

Core Support Structure

Core Barrel

Core Support Plate

Jacket

Core

Reflector Assemblies

Dummy Assemblies

Fuel Assemblies

Spallation Target Assembly and Beam Line

Above Core Structure

Core Plug

Multifunctional Channels

Core Restraint System

Control Rods, Safety Rods, Mo-99 production units

Primary Heat Exchangers

Primary Pumps Si-doping Facility

Diaphragm

IVFS

IVFHS

IVFHM

Reactor layout

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Reactor Vessel

Main dimensions

Height: about 12.200 m

Inner diameter: 8 m

Wall thickness: 80 mm

MaterialAISI 316L

Weight

About 320 ton

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Reactor Cover

Main dimensions

Height: 2 m

Outer diameter: 9.3 m

Material

AISI 316L Concrete

Weight

About 340 ton

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Reactor Cover

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Core Support Structure

Core barrel

Main dimensions

Height: about 9.5 m

Outer diameter: about 1600 mm

Material

AISI 316L

Core support plate

Main dimensions

Outer diameter: about 1530 mm

Thickness: 200 mm

Material

T91

Total weight

About 15 ton

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Above Core Structure

Main dimensions

Height: about 7.750 m

Outer diameter: about 1520

mm

37 Multi-functional Channels

Material AISI 316L

Total weight

About 20 ton

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Primary Heat Exchangers

Main dimensions

Shell and Tube

Power: 27,5 MW

Double walled design

About 700 tubes Shroud: about 860 mm

Total length: about 8.1 m

Internal pressure: 16 bar

Weight: about 7 ton

MaterialAISI 316L

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Primary Pumps

Main dimensions

Mass flow: about 4750 kg/s per

pump

Pressure head: 2,8 m

External diameter: ~ 1100 mm

Rotating speed: 225 rpm

Length: about 12 m

Axial type of pump

Material

AISI 316L Impeller: TBD

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Diaphragm

Main dimensions

Double plate design

Baffle

In-vessel fuel storage

Height: about 9.8 m Inner diameter: 7.7 m

Wall thickness: 50 mm

Lower plate thickness: 80 mm

Upper plate thickness: 50 mm

MaterialAISI 316L

Weight

About 190 ton

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Core and Fuel Assemblies

151 positions & 37 multifunctional plugs

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Control/Safety rods

Buoyancy driven control rods Insertion


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Control/Safety rods

Gravity driven safety rods Insertion


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Spallation Target Assembly

Produces about 1017neutrons/s at the reactormid-plane to feed subcritical core @ keff=0.95

Fits into a central hole in core Compact target

Remove produced heat

Accepts megawatt proton beam

600 MeV, 3.5 mA~2.1 MW heat Cooling of window is feasible

Material challenges Preferential working temperature: 450500C

Service life of at least 3 full power months (1

cycle) is achievable

Dimensions Length: about 12.5 m

Diameter: about 105 mm

Weight: about 250 kg

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Part 4

Way ahead to construction


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The project schedule

20102014: Front End Engineering Design; file for the Belgian

Government

2015: Tendering & Procurement

20162018: Civil Engineering & construction of components

2019: On site assembly

20202022: Commissioning at progressive power

2023: Progressive start-up

202420??: Full exploitation

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Copyright notice

Copyright 2012 - SCKCEN

All property rights and copyright are reserved.

Any communication or reproduction of this document, and any

communication or use of its content without explicit authorization is

prohibited. Any infringement to this rule is illegal and entitles to claim

damages from the infringer, without prejudice to any other right in case

of granting a patent or registration in the field of intellectual property.

SCKCEN

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Centre d'Etude de l'Energie Nuclaire

Stichting van Openbaar Nut

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Foundation of Public Utility

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Operational Office: Boeretang 200BE-2400 MOL

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MYRRHA Multi-purpose HYbrid Research Reactor for High-tech Applications 2