ADVANCE IN THE RA-10 REACTOR PROJECT · ADVANCE IN THE RA-10 REACTOR PROJECT H ... RA-6 MTR, pool type, 1 MW Bariloche/CNEA Teaching/BNCT/NAA RA-3 MTR ... Detailed Design is …

IGORR 2014

S. C. de Bariloche, Argentina – 17 th Nov. – 21st Nov, 2014

ADVANCE IN THE RA-10 REACTOR

PROJECT

H. Blaumann, A. Vertullo

Nuclear Engineering Department

National Atomic Energy Commission

Argentina

IGORR 2014


Background

Design features

Siting and Licensing

Project execution

Project schedule

Conclusions

Contents

IGORR 2014


Present Nuclear Facilities

Reactor Type Location Main Application

RA-0 RA-1 critical facility Córdoba

University

Human resources for

nuclear industry

Promote nuclear

energy applications RA-4 Siemens SUR 100 critical

facility

Rosario

University

RA-1 UO2-graphite fuel rods,

water cooled and

moderated, tank reactor,

40 kW

Buenos Aires

/CNEA

Long term material

irradiations, nuclear

instrumentation testing,

training

RA-6 MTR, pool type, 1 MW Bariloche/CNEA Teaching/BNCT/NAA

RA-3 MTR, pool type, 10 MW Buenos

Aires/CNEA

RI production

Atucha I PHWR Lima/NASA 357 Mwe

CNE CANDU Embalse/NASA 648 Mwe

IGORR 2014


Current Nuclear Projects

NPP TYPE POWER

Atucha II PHWR 745 MWe

CNE+ life extension and power

upgrade

656 MWe

CAREM 25 prototype for an Argentinean

PWR reactor

25 MWe

RA-10 multipurpose RR 30 MW

IGORR 2014


Argentinian Research Reactors

REACTOR POWER LOCATION CRITICALITY

RA-6 500 kW Argentina 1982

RP-10 10 MW Perú 1988

NUR 1 MW Algeria 1989

ETRR-2 22 MW Egipt 1997

OPAL 20 MW Australia 2007

IGORR 2014


To provide a replacement for the RA-3 reactor (1967)

To increase the RI production in order to support the local and

regional future demand

2500 Ci/w molybdenum-99

to increase the production of lutecium-177 and iridium-192 and to try the

generation of new RI such us bismut-213

together with the Brazilian RMB, it will play a key role in LA self sufficient

supply of RI providing a mutual natural back up

Why the RA-10 Project?

IGORR 2014


To consolidate the national capabilities related to nuclear fuel

production

to implement facilities for testing the development of new fuel

elements including miniplates, MTR and NPP fuel elements.

to implement facilities for materials testing, focused on radiation

damage and corrosion evaluation

To offer the scientific and technological system new

capabilities based on neutron techniques

to develop thermal and cold neutrons facilities for the application of

neutronic techniques to nuclear technology, material science and

biology.

Why the RA-10 Project?

IGORR 2014


Design Goals and Project Main Guidelines

A multipurpose facility suitable for RI production, material

and fuel irradiation, neutron techniques applications and

silicon doping production.

Based on LEU fuel elements

Based on Argentinian Safety Regulations and IAEA

Standards

Systematic approach to Safety Management (following

IAEA NS-R-4, 2005)

Dynamic interaction between Design and Safety

Analysis

IGORR 2014


Design objectives: RI production

Application Spectrum Flux Irradiation

conditions

Section Length Positions

Mo-99 Thermal 1.0-1.5

x1014

* Continuous loading

5.2cm

(diam.) 30cm

* 10 positions

(up to 8 miniplates each one)

Ir-192

(Industrial)/

ORI

Thermal 1.0-1.5

x1014

* 2-3 cycles 5.2cm

(diam.)

12cm 4

Ir-192

(medicinal)/

Lu-177

Thermal >1,8 x1014 * 2-3 cycles 5.2cm

(diam.)

12cm 4

IGORR 2014


Design objectives: materials irradiation


conditions


Structural

materials

irradiation

Fast

>3 x1014

(E>1

MeV)

Rig

5cm

(diam.) 12cm 2

MTR

miniplates

and fuel

elements

irradiations

Thermal >1 x1014 8x8 cm 65cm 2

NPP vessel

material Reactor

1x1013

(máx) Rig

5cm

(diam.) 12cm 2

IGORR 2014


Design objectives: NPP fuel irradiation


Conditions


NPP fuel

elements

irradiation

PWR

1-1.3 x1014

(base mode)

up to

2.5 x1014

(power ramp

mode)

* Loop 10cm

(diam.)

40cm 1

IGORR 2014


Design objectives: NPP fuel irradiation

Burnup build-up

tests

Transient tests

• base irradiation at

constant power

• 1 to 3 fuel rods

• up to 500 W/cm

• up to 60000

Mwd/tonU

• 3 FPY

• power ramp with slope

10-50 W/cm min

• 1 fuel rod

• 300 to 600 W/cm

• up to 10% enrichment

IGORR 2014


Design objectives: neutron beams


conditions

Section Positions

Cold

source Thermal

D2, cryogenic

power < 5 kW

18 lts 1

Cold

beams

E< 0.01

eV

>109 (neutron

hall) in-pile guide 2

Cold

beams

E< 0.01

eV

>4 109

(reactor face)

in-pile guide 2

Thermal

beams E<0.1 eV

>109 (neutron

hall)

in-pile guide 2

Thermal

beams E<0.1 eV

>1010

(reactor face)

in-pile guide 1

IGORR 2014


Design objectives: other facilities


Conditions

Section

(Ø, cm)

Length

(cm) Positions

NTD Thermal 1 x1013-

4x1013

With rotator

and flux

flatter

devices

15.24(2) /

20.32(2) /

25.4(1)

60 5

Long and short

residence time

irradiation

Thermal+

Epithermal

2 x1014

Pneumatic

Transport

system

≈ 3 ≈ 10 14

Under water NR Thermal > 1 x108 L/D>150 15 - 1

Surveillance

programme Reactor

Maximum

flux

capsule ≈ 5 12 3

IGORR 2014


General Characteristics

Open pool type

30 MW power

Low enrichment MTR fuel elements

D2O reflector

H2O moderator – coolant

Upward coolant direction

2 independent shutdown systems: hafnium plates and

D2O reflector tank emptying

29.5 days continuous operation cycle

IGORR 2014


Reactor Core

Thermal Flux

Irradiation Facilities

Fast Flux


Control

Rods

Fuel Elements

European Research Reactor Conference

Ljubljana, Eslovenia – 30th March – 3rd April, 2014

Mo-99 (10 positions)

PNEUMATIC DEVICE (7 X 2 positions)

NTD (5 positions)

Ir-192 MED/ Lu-177 (up to 4 positions)

Ir-192 IND/ ORI (up to 4 positions)

LOOP


IGORR 2014


RA-10 Siting: Centro Atómico Ezeiza

RA-3 Reactor

Radioisotopes

production

NPP Fuel

Elements

production

PIE facilities

IGORR 2014


RA-10 Siting: Centro Atómico Ezeiza

IGORR 2014


RA-10 Reactor Building

IGORR 2014


To arrange a set of presentation to the Regulatory Body

according to the development of the engineering

To agree about the scope and contents of the Preliminary

Safety Report

To promote an ordered and efficient process for the

Preliminary Safety Report reviewing

Construction License obtained on last October

Licensing Plan: I-Construction License

IGORR 2014


Funds provided by the government

Project team (40) + CNEA personnel (150)

Agreement with INVAP for the development of basic and

detailed engineering

Siting studies and Licensing conducted by CNEA

Civil work contracted in the frame of a bidding process

Contract with INVAP for “Supply, assembly and

preoperational test”

Operators training provided CNEA (simulator)

Commisioning executed by CNEA

To promote future users developed by CNEA

Project execution

IGORR 2014


Project schedule

2010 2019

2011 2012 2013 2014 2015 2016 2017 2018 2019

2010 2019

2011 2012 2013 2014 2015 2016 2017 2018 2019

Licensing

Milestones

Engineering

And

Construction

Milestones

Página 1

RA-10 PROJECT TIMELINE

jun-10

Conceptual

Engineering

mar-15

Radiological

Baseline

Start

oct-19

Delivery

For

Operation

sep-13

PSAR

jul-19

Operating

License

dic-14

Bidding porcess

For

Civil Work

oct-14

Construction

License

sep-14

U235

Bidding process

Start

dic-11

Basic

Engineering

(BE)

oct-12

BE. Critical

Design

Review

jul-13

Detail

Engineering

nov-14

Obtainment of

Certificate of

Environmental

Suitability

mar-12

BE Preliminar

Design

Review

feb-19

Commissioning

jul-13

End Basic Eng.

mar-12

Environmental

Management

Plan

feb-16

Installation

Start

Now

jun-15

Civil Work

Start

Now

mar-16

Operators

Training

dic-18

Commissioning

License

oct-14

End EIA

(Presentation

to OPDS)

IGORR 2014


New Fission Products Plant (moli production)

New Research Reactors Fue Elements Production Plant

RA-10 Neutron Beam Project

Related projects

IGORR 2014


RA-10 Reactor Installations

IGORR 2014


Basic Design has been completed, mostly under a contract

with INVAP S. E.

Detailed Design is being developed in the frame of a new

contract with INVAP S. E.

The Preliminary Safety Report has been accepted by the

Regulatory Body and the Construction License has been

obtained on last October.

The Environmental Assessment Study has been finished

Technical specification for civil work has been completed

Bidding process has just been opened.

The construction is expected to be initiated by June 2014.

Conclusion

IGORR 2014


Thank you for your attention !!!

IGORR 2014


Reactor Pool

IGORR 2014


Reactor and Service Pool

IGORR 2014


Reflector Tank

IGORR 2014


Reflector Tank

IGORR 2014


Irradiation

Position

Thermal

Flux

Epithermal

Flux

Fast

Flux

Central 1.4x1014 4.4x1014 5.1x1014

Adjacent 3.0x1014 1.7x1014 1.3x1014

In-core facilities performance

IGORR 2014


RI facility Target

geometry

Irradiation

period

Final

Activity

Mo99 LEU

miniplates 5 days 4000 Ci*

Ir 192

(med) Wires 1 cycle 34400 Ci

Lu 177 Cans 1 cycle 1700 Ci/g

Ir 192

(ind) Foils 1 cycle 12600 Ci

(*) 6 days Curies

Radioisotopes performance

IGORR 2014


BEAM

TYPE POSITION

NEUTRON

FLUX

(n/cm2/sec)

Thermal

neutron beams hall (50 m from

reactor core) 2.5 x109

(Required: 1x109 )

reactor face 2.9 x1010

(Required:1x1010)

Cold

neutron beams hall (50 m from

cold source) 5.4 x109

(Required:1x109)

reactor face 1.4 x1010 (Required:4x109)

Neutron Beams Performance

IGORR 2014


Neutron Beams Performance

BEAM TYPE POSITION

NEUTRON

FLUX

(n/cm2/sec)

Thermal

TG1, TG2 neutron beams hall (50 mts from reactor core)

3 x109

(1x109 )

TG3 reactor face

3 x1010

(1 x1010)

Cold

CG1, CG2 neutron beams hall (50 mts from cold source)

6 x109

(1 x109)

CG3 reactor face

6 x109

(4x109)

IGORR 2014


3 rods

(base mode)

1 rod

(ramp mode)

Total power (kW) 51.2 21.4

Average lineal

power (W/cm) 426.7 535

Fuel Irradiation LOOP performance

Documents

ADVANCE IN THE RA-10 REACTOR PROJECT · ADVANCE IN THE RA-10 REACTOR PROJECT H ... RA-6 MTR, pool type, 1 MW Bariloche/CNEA Teaching/BNCT/NAA RA-3 MTR ... Detailed Design is …