Status of OECD/NEA activities related to Nuclear Fuel · PDF fileStatus of OECD/NEA activities related to Nuclear Fuel Research Simone MASSARA ... –The provision of experimental

© 2015 Organisation for Economic Co-operation and Development 1

Status of OECD/NEA activities

related to Nuclear Fuel Research

Simone MASSARA

TWGFPT Meeting

22-23 April 2015, IAEA, Vienna


As of 18 September 2012

NEA Committees

Nuclear

Science

Committee

Nuclear

Science

Committee

NSC



NEA Committees

Nuclear

Science

Committee

Nuclear

Science

Committee

NSC

Working Group on Fuel Safety (WGFS)

See next presentation by

W. Wiesenack (HRP)

http://www.oecd-nea.org/nsd/csni/wgfs.html



NEA Committees

Nuclear

Science

Committee

Nuclear

Science

Committee

NSC


Expert Group on MP Experimental Data,

Benchmarking and Validation

Thermodynamics of

Adv. Fuels Intern.

Database (TAF-ID)

Expert Group on Accident

Tolerant Fuels

NSC activities

NEA/IAEA Intern. Fuel

Performance Experiments

database (IFPE) IAEA/FUMEX

HRP

http://www.oecd-nea.org/science/wprs/fuel/ifpelst.html






NSC activities related to fuels and structural materials

Expert Group on Accident

Tolerant Fuels Expert Group on MP Experimental Data,

Benchmarking and Validation

Thermodynamics of

Adv. Fuels Intern.

Database (TAF-ID)

NEA/IAEA Intern. Fuel

Performance Experiments

database (IFPE) IAEA/FUMEX

HRP







NEA fuel-related activities

• Fuel Performance

NEA/IAEA Intern. Fuel Performance Experiments Database (IFPE)

Expert Group on Reactor Fuel Performance

• Advanced Fuels Research

Expert Group on Innovative Fuels

Expert Group on Accident Tolerant Fuels for LWRs

Joint Project on Thermodynamics of Advanced Fuels International

Database

• Advanced Modelling and Multi-physics validation

Expert Group on Multiscale Modelling of Fuels

Expert Group on Multi-Physics, Experimental Data, Benchmarks

and Validation










Database




and Validation


IFPE History and Overview • IFPE: International Fuel Performance Experiment database

• OECD/NEA Taskforce setup 1993

• OECD/NEA Report, prepared by J. A. Turnbull (1995)

• Including data from IAEA/FUMEX Programmes (1993-2012)

• Creation of IFPE with data from Halden + Studsvik and Risø

(1995)

– The public domain database

– Thermal reactor fuel performance, principally for Zry + UO2

– Addition of advanced products with fuel and clad variants

is not ruled out

– Today, about 1452 rods/samples from various sources

encompassing BWR, CAGR, PHWR, PWR, and VVER

IFPE webpage http://www.oecd-nea.org/science/wprs/fuel/ifpelst.html





Expert Group on Reactor Fuel Performance, EGRFP

• Created in 2011 under the guidance of the Working Party on

Scientific Issues of Reactor Systems (WPRS)

• Chair: G. Rossiter (NNL, UK)

• NEA Secretariat: S. Massara

Objectives

• To provide expert advice on the development needs (data

and methods, validation experiments, scenario studies) for

existing and future fuel designs

• To provide specific technical information regarding:

– National / international programmes, experimental capabilities

– The provision of experimental data for model development and

validation from the IFPE Database

– Methods for code verification

http://www.oecd-nea.org/science/wpfc/index.html





EGRFP: Key Activities & Deliverables Identification and preservation of appropriate experimental data

(currently focusing on LWR fuels)

– State of the art report “Experimental Data Requirements for Fuel

Performance Modelling” (Update to “Turnbull report”, Review of

Nuclear Fuel Experimental Data, 1995)

– Collaborations with IAEA/FUMAC programme (through IFPE)

– 2015-2017: PCMI benchmark of fuel performance codes:

Cases 1 and 2 (2015-2016): modelling of hypothetical BOL ramp of PWR

rodlet (# 1) and commercial PWR rod (# 2)

Cases 3 and 4 (2016-2017): modelling + comparison with experimental

data provided by Halden Reactor Project (HRP)

Case 3: BOL ramps of experimental rods with different pellet designs: IFA-118 rig irradiated in the Halden Boiling Water Reactor (HBWR) from 1969 to 1970

Case 4: EOL ramping of PWR rodlet : IFA-629.4 rod 7

Participation of non-NEA member countries organisations very welcome










Database




and Validation


Expert Group on Innovative Fuels (EGIF)

• Under the guidance of the NSC Working Party

on Scientific Issues of Fuel Cycle (WPFC)

• Chair: N. Chauvin (CEA, France)

• Secretary: S. Cornet (NEA)

Objectives & Scope

- Technical issues associated with the development of innovative

fuels for transmutation purposes: homogeneous and heterogeneous

minor actinide (MA) bearing fuels in different form (oxide, nitride,

metal, carbide, etc)

- Covers technical issues related to: fabrication techniques, irradiation

performance, post irradiation examinations, predictive models/codes

for fabrication and performance

- State-of-the-art report on Innovative Fuels, published Dec-2014

(https://www.oecd-nea.org/science/docs/2015/nsc-wpfc-doc2015-9.pdf)



https://www.oecd-nea.org/science/docs/2015/nsc-wpfc-doc2015-9.pdf















• Focus on experiments on MA bearing fuels with different chemical

forms (oxide, metal, IMF, spherepac, etc.)

• Benchmark exercise with fuel performance codes

Phase 1: oxide and metal fuels with low content

Phase 2: Inert Matrix fuels, sphere pack, fuels for ADS with MAs

• Participating countries:

EC, France, Germany, Japan, Rep. Korea, US

• Irradiations data from Phénix, JOYO, HANARO, ATR and EBR2

• Codes: SIMMER, GERMINAL, TRANSURANUS, MBM

• First results to be shared in September 2015

• Discussion will be undertaken to include results in IFPE database

EGIF current activity: Benchmark Study on Fuel

Performance Codes and Experiments


Expert Group on Accident Tolerant Fuels for

LWRs (EGATFL) • June 2012 Nuclear Science Meeting

– Proposal for ATF Workshop received from the NEA Working Party on

Scientific Issues of the Fuel Cycle (WPFC)

• 10-12 December 2012: 1st OECD/NEA Workshop on

Increased Accident Tolerance of Fuels for LWRs

• 28-29 October 2013: 2nd OECD/NEA Workshop on

Increased Accident Tolerance of Fuels for LWRs

• 28-29 April 2014: EGATFL Start-up meeting

• 2nd meeting: 23-25 September 2014

• 3rd meeting: 3-5 March 2015

• 4th meeting scheduled 17-18 Sept. 2015,

PSI, in conjunction with TOPFUEL 2015

Download at:

https://www.oecd-nea.org/science/egatfl/





High temperature

during loss of

active cooling

Slower Hydrogen Generation Rate

- Hydrogen bubble

- Hydrogen explosion

- Hydrogen embrittlement of the clad

Improved Cladding Properties

- Clad fracture

- Geometric stability

- Thermal shock resistance

- Melting of the cladding

Improved Fuel Properties

- Lower operating temperatures

- Clad internal oxidation

- Fuel relocation / dispersion

- Fuel melting

Enhanced Retention of Fission Products

-Gaseous FPs, Solid/liquid FPs

Improved Reaction Kinetics with

Steam

- Heat of oxidation

- Oxidation rate

Fuels with enhanced accident tolerance are those that, in comparison with the

standard UO2 – Zircaloy system, can tolerate loss of active cooling in the core for

a considerably longer time period (depending on the LWR system and accident

scenario) while maintaining or improving the fuel performance during normal

operations.

From K. Pasamehmetoglu (INL), Summary of the US National Workshop, OECD-NEA Workshop on ATF, Dec. 2012

Definition of Accident Tolerant Fuels


• Under the guidance of the Nuclear Science Committee, the

Expert Group will primarily act as a forum for scientific and

technical information exchange on advanced Light Water

Reactor (LWR) fuels with enhanced accident tolerance.

• The Expert Group will focus on the fundamental properties

and behaviour under normal operations and accident

conditions for advanced core materials and components

(fuels, cladding, control rods, etc.).

• The materials considered will be applicable to Gen II and

Gen III Light Water Reactors, as well as Gen III+ reactors

under construction.

NEA Expert Group on Accident Tolerant

Fuels for LWRs (EGATFL) Scope


Chair: S. Bragg-Sitton (INL) Chair: M. Kurata (JAEA) Chair: M. Moatti (EDF)

Task Force 1 Systems Assessment

• Evaluation Metrics

– Economics

– Fuel cycle (SNF)

– Normal operation

– DBAs

– BDBAs

– …

• Technology Readiness Level (TRL) definition

• Definition of Illustrative Scenarios for ATF evaluation (input for TF2 and TF3)

• Fuel performance and System codes

• Parametric studies

Task Force 3 Fuel Concepts

• Properties of material

candidates

— Improved UO2

— High density fuel

— Coated particle fuel

• Evaluation under normal operations

• Evaluation under illustrative scenario

• PCI

• Testing needs – data gaps

• Modeling needs – modeling gaps

• Experimental infrastructure

Expert Group on Accident Tolerant Fuels for LWRs (EGATFL) Information Exchange and Technical Discussions on general issues of ATF

Task Force 2 Cladding/Core Materials


candidates

– Coated and improved Zr-based alloys

– SiC and SiC/SiC composites

– Advanced steels

– Refractory metals

– Non-fuel components • Evaluation under normal

operations • Evaluation under illustrative

scenario • PCI • Testing needs – data gaps • Modeling needs – modeling

gaps • Experimental infrastructure

Chair: K. Pasamehmetoglu (INL)


Task Force 1 Systems Assessment

• Evaluation Metrics

– Economics

– Fuel cycle (SNF)

– Normal operation

– DBAs

– BDBAs

– …

• Technology Readiness Level (TRL) definition

• Definition of Illustrative Scenarios for ATF evaluation (input for TF2 and TF3)

• Fuel performance and System codes

• Parametric studies

Task Force 3 Fuel Concepts


candidates

— Improved UO2

— High density fuel

— Coated particle fuel

• Evaluation under normal operations

• Evaluation under illustrative scenario

• PCI

• Testing needs – data gaps

• Modeling needs – modeling gaps

• Experimental infrastructure

Task Force 2 Cladding/Core Materials


candidates

– Coated and improved Zr-based alloys

– SiC and SiC/SiC composites

– Advanced steels

– Refractory metals

– Non-fuel components • Evaluation under normal

operations • Evaluation under illustrative

scenario • PCI • Testing needs – data gaps • Modeling needs – modeling

gaps • Experimental infrastructure

EGATFL deliverables (end-2016)

Del 1

Del 2

Del 4 Del 3


EGATFL: 30 organisations from 13 member countries + PRC

International org. IAEAP.R. of China CGN

Country Organisation Country Organisation

Belgium SCK-CEN

P.R. of China CGN

Czech Rep. ALVEL

CEA

IRSN

CRIEPI

JAEA

Kyoto University

Muroran Inst. Techn.

NFD

Toshiba

Japan

EDF

Germany KIT

France

AREVA

Rep. of Korea KAERI

Norway OECD-Halden

Kurchatov Institute

NITI

Switzerland PSI

Sweden Westinghouse

AREVA

GE

INL

Univ. Illinois

Univ. Florida

MIT

ORNL

UK NNL

USA

EPRI

Russian Federation


• Objective: to make available a comprehensive, internationally

recognised thermodynamic database (Gibbs energy, phase diagrams)

on nuclear fuel materials for:

– Fuel fabrication

– Fuel behaviour under

normal and off-normal

operative conditions

• Participants: 9 Signatories from 6 member countries: Canada (CNL,

RMCC, UOIT), France (CEA), Japan (JAEA, CRIEPI), Rep. of Korea

(KAERI), The Netherlands (NRG), US DoE (ORNL, LLNL, INL), and

NNL (UK) in the process of signing the Agreement

• OECD-NEA acting as Project Coordinator

• Budget: 280 000 EUR for 3 years (2013-2015)

https://www.oecd-nea.org/science/taf-id/

Joint Project on ‘Thermodynamics of Advanced

Fuels – International Database (TAF-ID)’








Objectives of the TAF-ID Project (1 / 2) Objectives

– To develop a thermodynamic database as a computational tool for advanced fuel materials using the Calphad method

Phase diagrams + Thermodynamic properties of the phases

– To exchange on the models, review of experimental data, softwares, assessments ….

Systems of interest: Fuel materials for Generation II, III, IV

– Fuels

» UO2, (U,Pu,Am,Np)O2 , (U,Th)O2, (U,Pu,Zr,Am,Np), UN, (U,Pu)C

– Fission products

» Ba, Sr, Mo, Zr, Lanthanides (Ce, La, Nd, Gd), metallic FPs (Pd, Ru, Rh, Te),

Volatile (Cs, I, Te)

– Structural materials

» Fe-Cr-Ni, Zr alloys, Fe-Cr-Al-Y, Concrete (SiO2-CaO-FexOy-Al2O3-MgO),

SiC, B4C


Objectives of the TAF-ID Project (2 / 2) Applications

– Fuel behaviour at high temperature under normal and off-normal conditions

» Influence of the Minor Actinides on the fuel thermodynamic properties

» Fission product « chemistry »

» Solid/liquid phase transition

» Vaporization

– Fuel / cladding chemical interaction at high temperature

– Fuel fabrication

vessel(steel)

fuel sheath(zircaloy)

fuel pellet(UO2)

Radiative heat transfer

Metallic layer

Oxidic pool

Q

Oxidic crust Lower head

Maximum heat flux

Radiative heat transfer

Metallic layer

Oxidic pool

Q

Metallic layer

Oxidic pool

Q

Oxidic crust Lower head










Database




and Validation


Working Party on Multiscale Modelling of Fuels

and Structural Materials (WPMM)

Focused on materials

science aspects of nuclear

fuels and structural materials

Aims at promoting and

developing multiscale

models and simulations

as validated predictive tools

for nuclear fuel design,

fabrication and performance

Set up in 2009, renewed mandate 2014-2017


Structure of the WPMM Expert Groups

(2015 – 2017)

Task Force on

‘Unit Mechanisms of

gaseous FP release’

Task Force related to

Structural Materials

Modelling

(will be established in 2015)


Structure of the WPMM Expert Groups

(2015 – 2017)

Task Force on

‘Unit Mechanisms of

gaseous FP release’

Task Force related to

Structural Materials

Modelling

(will be established in 2015)


EG on Multiscale Modelling of Fuels (M2F) Chair: T. Besmann (ORNL, USA)

Vice-Ch.: C. Valot (CEA, France)

Assess multi-scale modeling

approaches devoted to nuclear

fuels from the atomic to the

macroscopic scale

Address all types of fuels: both

current (mainly oxide fuels) and

advanced fuels

Address key engineering issues

associated with each type of fuels

Assess the quality of existing links

between the various scales

State-of-the-art report will be

published in June 2015


Computational Approaches: 2015

Continuum

Merhods Thermochemistry &

Mean Field

(Rate theory)

Molecular

Dynamics

Density

Functional

Theory

nm m mm cm

ps

s

ms

da

ys

LENGTHSCALE

TIM

ES

CA

LE

Phase Field

se

c

ATOMS PELLET MICROSTRUCTURE

ns

Fuel Performance

Codes

From S. Phillpot (Univ. Florida), OECD-NEA NSC Meeting, 13/06/14 (figure adapted from Marius Stan, DOE)


Task Force on “Unit mechanisms of gaseous

FP release” Objectives: Building on historical experience and exploiting recent

advances in experimental capabilities and modelling/simulations, the

effort will focus on advancing the understanding of unit mechanisms of

fission gas release:

Scope

Identify fission gas behaviour mechanisms

Determine critical modelling parameters

Relate model parameters to physics-based phenomena

Critically assess existing data

Recommend new, key experiments/simulations

Core group of 6-8 participants from US, France, UK, Belgium and the

Russian Federation

M. Tonks (INL) elected as Chair

First draft scheduled for May 2015, final deliverable published as

OECD/NEA Technical Report & Paper on a Scientific Journal


Expert Group on Multi-physics, Experimental

Data, Benchmarks & Validation (EGMPEBV)

• Created in 2015, directly reporting to the NSC

• Chair: P. Finck (INL, US)

• Secretariat: J. Dyrda (NEA)

Objectives

• Response to a request by member countries to receive guidance

and recommendations for the validation of multi-physics computer

codes

• Validation of multi-physics tools (coupling neutronics,

thermalhydraulics, fuel performance, and potentially chemical

phenomena, structural mechanics, etc.) will require the access to

experimental data which may not be fully accessible though

experimental programmes carried out in the past, and with stricter

requirements, in particular for the definition of uncertainties.


EGMPEBV structure

• Work of the group will include

the certification of experimental

data and benchmark models

along with establishing the

processes and procedures for

using that information for the

validation of simulation tools

• Two Task Forces:

– TF1: Experimental Data

Qualification and Benchmark

Evaluation

– TF2: Consensus Validation

Procedure


Summary of NEA fuel-related activities within

the NEA NSC (with links to NEA webpages) • Fuel Performance







Database




and Validation

https://www.oecd-nea.org/science/wprs/fuel/ifpelst.html

https://www.oecd-nea.org/science/wprs/egrfp/

https://www.oecd-nea.org/science/wpfc/index_if.html




https://www.oecd-nea.org/science/wpmm/expert_groups/m2f.html






https://www.oecd-nea.org/science/egmpebv/









Thank you for your attention!

https://www.oecd-nea.org/science/

Documents

Status of OECD/NEA activities related to Nuclear Fuel · PDF fileStatus of OECD/NEA activities related to Nuclear Fuel Research Simone MASSARA ... –The provision of experimental