M. M. MarekMarek, J., J.KyselaKysela, J., J.BurianBurianNuclear Research Institute Nuclear Research Institute ŘŘeežž, plc, plc

Reactor Services DivisionReactor Services Division

LVR-15 Reactor Application for Material Testing

Research Reactor LVR-15�� LightLight--water moderated and cooled tank water moderated and cooled tank nuclear reactor with forced cooling.nuclear reactor with forced cooling.

�� Maximum thermal power of 10 MWMaximum thermal power of 10 MW�� The fuel type IRTThe fuel type IRT--2M enriched to 36% 2M enriched to 36% �� Combined waterCombined water--beryllium reflector beryllium reflector �� 5 kg of 235U5 kg of 235U�� 28 to 31 fuel elements28 to 31 fuel elements

LVR-15 cross section

LVR-15 - Core cross section

The LVR-15 reactor horizontal cross section

Reactor Characteristics

99xx10101717 n/mn/m22ssthermal neutron flux in irradiation thermal neutron flux in irradiation channel in reflector channel in reflector

11..22xx10101818 n/mn/m22ssthermal neutron flux in irradiation thermal neutron flux in irradiation channel in fuel channel in fuel

11xx10101313 n/mn/m22ssthermal neutron flux at the end of thermal neutron flux at the end of the horizontal beam tubethe horizontal beam tube

33xx10101818 n/mn/m22ssmaximum fast neutron flux in the maximum fast neutron flux in the corecore

11..55xx10101818 n/mn/m22ssmaximum thermal neutron flux in maximum thermal neutron flux in the corethe core

10 M10 MWWmaximum reactor powermaximum reactor power

Fuel Element

580 mm580 mmactive lengthactive length

3,2 kg3,2 kgmass of the mass of the assemblyassembly

71,5 x 71,5 71,5 x 71,5 mmmmsection squaresection square

882 mm882 mmtotal lengthtotal length

Fuel Element (cont.)

36%36%235235U enrichmentU enrichment230 g230 gmass of mass of 235235UU

UOUO22 –– AlAlfuel materialfuel material

min.0,4 mmmin.0,4 mmcladding cladding thicknessthickness

2 mm2 mmtube wall tube wall thicknessthickness

The Reactor Serves as a Radiation Source for:�� Material testing experiments in water loops and Material testing experiments in water loops and irradiation rigs irradiation rigs

�� Activation analysis with the pneumatic rabbit Activation analysis with the pneumatic rabbit system system

�� Experiments at beam tubes in the field of Experiments at beam tubes in the field of nuclear and applied physics nuclear and applied physics

�� Irradiation of iridium for medical purposes Irradiation of iridium for medical purposes �� Irradiation for radioIrradiation for radio--pharmaceuticals pharmaceuticals production production

�� Irradiation of silicon mono crystals Irradiation of silicon mono crystals �� Neutron capture therapy projectNeutron capture therapy project

Reactor Dosimetry�� According to the type of experiment different According to the type of experiment different demands on reactordemands on reactor dosimetrydosimetry are expected. are expected. Neutron spectra, thermal and fast neutron flux Neutron spectra, thermal and fast neutron flux densities and their changes during the irradiation, densities and their changes during the irradiation, final neutronfinal neutron fluencesfluences, gamma radiation heating , gamma radiation heating and absorbed doses are to be measured. Toand absorbed doses are to be measured. To fulfil fulfil these demands, several measures are taken:these demands, several measures are taken:

�� •• irradiation position assessmentirradiation position assessment�� •• instrumentation designinstrumentation design�� •• mock up experimentmock up experiment�� •• radiation monitoringradiation monitoring�� •• postpost--irradiation evaluationirradiation evaluation

Reactor Dosimetry (cont.)

�� The power and neutron group flux densities The power and neutron group flux densities distribution in the core distribution in the core -- NODER 4 groups diffusion NODER 4 groups diffusion code. code.

�� The macroscopic constants The macroscopic constants -- the use of WIMSD4 and the use of WIMSD4 and WIMSD4WIMSD4--M codes. M codes.

�� Fast neutron and gamma ray spectra calculation Fast neutron and gamma ray spectra calculation ––�� DORT transport with the BUGLEDORT transport with the BUGLE--96 coupled cross 96 coupled cross

section library of 47 neutron and 20 gamma groups. section library of 47 neutron and 20 gamma groups. �� Monte Carlo neutron and particles transport code Monte Carlo neutron and particles transport code

MCNP 4A with the ENDF/BMCNP 4A with the ENDF/B--VI crossVI cross--section section library library

Irradiation position assessmentIrradiation position assessment

Reactor Dosimetry (cont.)

�� Activation monitors Activation monitors –– thermal, resonance, threshold, thermal, resonance, threshold, fissionfission�� Neutron spectrum measurementNeutron spectrum measurement�� Neutron flux distribution Neutron flux distribution �� Foils, wires.Foils, wires.

�� Adjustment procedure Adjustment procedure -- calculated spectra combined with calculated spectra combined with activation monitors activation monitors –– determination of neutron flux determination of neutron flux densities,densities, fluencesfluences, and integral values, and integral values

�� SelfSelf--powered neutron detectors (powered neutron detectors (SPNDsSPNDs) ) �� Neutron flux prediction in irradiation positionNeutron flux prediction in irradiation position�� Neutron flux densities distribution along the reactor Neutron flux densities distribution along the reactor

core height. core height.

Neutron Neutron dosimetrydosimetry

Reactor Dosimetry (cont.)

� Reactor calorimeter or string of calorimeters can be used for the gamma radiation heating measurement and monitoring.

� Type 1 - inside the reactor core (ŠKODA Nuclear Machinery Ltd.)

� Type 2 - at the reactor core periphery.

Gamma heatingGamma heating

Experimental Facilities�� HighHigh--pressure water loops pressure water loops �� Vertical channels for Vertical channels for

material testing (rigs) material testing (rigs) �� Vertical irradiation Vertical irradiation

channels channels �� Pneumatic rabbit system Pneumatic rabbit system

for shortfor short--time irradiation time irradiation �� Nine horizontal channels Nine horizontal channels

(beam tubes) (beam tubes) �� BNCT facility BNCT facility �� Hot cells Hot cells

RVS–3 LoopThe loop is designed for material and radioactivity The loop is designed for material and radioactivity

transport investigation under PWR/VVER transport investigation under PWR/VVER conditions. The RVSconditions. The RVS--3 loop facility enables to 3 loop facility enables to perform irradiation experiments in wide range of perform irradiation experiments in wide range of operational parameters limited by following operational parameters limited by following maximum parameters :maximum parameters :

�� Pressure 16.5Pressure 16.5 MPaMPa�� Temperature 345Temperature 345°°C C �� Water flow rate 10 000 kg/hr Water flow rate 10 000 kg/hr �� Neutron flux ~1x10Neutron flux ~1x101818 n/mn/m22s s �� Electrical heating capacity 100 kW Electrical heating capacity 100 kW

RVS–3Loop Diagram

RVS–3 LoopIrradiation Channel

RVS–3 Loop�� Investigation of structural materials Investigation of structural materials

mechanical properties degradation and mechanical properties degradation and corrosion behaviour under irradiation and corrosion behaviour under irradiation and PWR/VVER water chemistry and thermalPWR/VVER water chemistry and thermal--hydraulic conditionshydraulic conditions

�� Investigation of behaviour (corrosion, Investigation of behaviour (corrosion, hydridinghydriding) of fuel cladding materials under ) of fuel cladding materials under influence of irradiation, thermal flux and influence of irradiation, thermal flux and water chemistry conditions water chemistry conditions

RVS–3 Loop�� Investigation of radioactivity transport and Investigation of radioactivity transport and

behaviour under PWR/VVER conditions behaviour under PWR/VVER conditions (e.G. Influence of water chemistry, (e.G. Influence of water chemistry, pHTpHTregime, zinc injection ammonia, etc.) regime, zinc injection ammonia, etc.)

�� Testing of highTesting of high--temperature, high pressure temperature, high pressure sensors for water chemistry monitoring. sensors for water chemistry monitoring.

BWR–1 Loop�� The loop is designed for investigation of structural The loop is designed for investigation of structural materials behaviour and radioactivity transport materials behaviour and radioactivity transport under BWR conditions. The BWRunder BWR conditions. The BWR--1 loop facility 1 loop facility enables to perform irradiation experiments in wide enables to perform irradiation experiments in wide range of operational parameters limited by the range of operational parameters limited by the following maximum parameters:following maximum parameters:

�� Pressure 10Pressure 10 MPaMPa�� Temperature 300Temperature 300°°C C �� Water flow rate 2 000 kg/hr Water flow rate 2 000 kg/hr �� Neutron flux ~1x10Neutron flux ~1x101818 n/mn/m22s s

BWR–1Loop Diagram

BWR–1 Loop�� Investigation of materials mechanical Investigation of materials mechanical

properties degradation and corrosion properties degradation and corrosion behaviour under irradiation and BWR water behaviour under irradiation and BWR water chemistry conditions.chemistry conditions.

�� Investigation of radioactivity transport and Investigation of radioactivity transport and behaviour under BWR conditions (e.g. behaviour under BWR conditions (e.g. Hydrogen water chemistry, zinc injection, Hydrogen water chemistry, zinc injection, etc.).etc.).

�� Testing of highTesting of high--temperature, high pressure temperature, high pressure sensors for water chemistry monitoring.sensors for water chemistry monitoring.

BWR–2 Loop�� The experimental water loop shall be used The experimental water loop shall be used

for the material research of BWR reactors for the material research of BWR reactors under conditions simulating the operation of under conditions simulating the operation of BWR reactors (pressure, temperature, BWR reactors (pressure, temperature, radiation, fluid analysis).radiation, fluid analysis).

�� Pressure 12Pressure 12 MPaMPa..�� Temperature 300Temperature 300°°C.C.�� Water flow rate 8 000 kg/hr.Water flow rate 8 000 kg/hr.�� Force applied to the specimen 150 Force applied to the specimen 150 kNkN..

BWR–2Loop Diagram

BWR–2 LoopIrradiation ChannelIASCC of RPV and core internals

2CT & 1CT specimens, hydraulic loading –cycling/constant load 20-75MPa√m, ferritic & austenitic steels, BM, HAZ

HTR Materials Irradiation- He Loop conceptual design

�� Material performance in Material performance in He at high temperature He at high temperature and under the influence of and under the influence of impurities such as Himpurities such as H22O, O, COCO22

�� Temperature 500 Temperature 500 –– 1000 1000 ººCC�� Flow rate 20g/sFlow rate 20g/s�� He pressure of 7 He pressure of 7 MpaMpa�� Purification systemPurification system

Objectives:Objectives:�� Materials performance under Materials performance under the combined influence of the combined influence of supercritical water and supercritical water and irradiationirradiation�� Temperature 600Temperature 600°°CC�� Pressure of 25 Pressure of 25 MpaMpa

SCWR Materials IrradiationLoop conceptual design

Irradiation Rigs�� Cylindrical, flatCylindrical, flat�� Full temperature controlFull temperature control�� Four types of specimens:Four types of specimens:��Tensile specimenTensile specimen��CT specimenCT specimen��Round CT specimenRound CT specimen��CharpyCharpy--v specimenv specimen

CHOUCAIrradiation Rig

�� Independent and Independent and controlled heating in controlled heating in sectionssections

�� ThermocouplesThermocouples�� Neutron monitoringNeutron monitoring

FlatIrradiation Rig

�� Independent and Independent and controlled heating in controlled heating in sectionssections

�� ThermocouplesThermocouples�� Neutron monitoringNeutron monitoring

FlatIrradiation RigRig crossRig cross--sectionsection�� 70 x 70 mm70 x 70 mm22

�� 140 x 70 mm140 x 70 mm22

Sample crossSample cross--sectionsection�� 60 x 60 mm60 x 60 mm22

�� 120 x 60 mm120 x 60 mm22

Experimental Base for GIV Reactor Systems�� Experience based on long term research in material, Experience based on long term research in material,

water chemistry and water chemistry and radiolysisradiolysis tests for PWR, VVER tests for PWR, VVER and BWRand BWR

�� The experience for SCWR is based on water The experience for SCWR is based on water chemistry and materials studies going from PWR chemistry and materials studies going from PWR (VVER) to BWR reactor irradiation condition(VVER) to BWR reactor irradiation condition

�� The experience for HTR/VHTR is based on material The experience for HTR/VHTR is based on material irradiation for ADTT and big samples (CCT) irradiation for ADTT and big samples (CCT) irradiation of RPVirradiation of RPV

Experimental ProjectsMaterial degradation studies (SCC):

� IASCC of RPV and core internals (for VGB) � 2CT & 1CT specimens, hydraulic loading –

cycling/constant load 20-75 MPa√m, ferritic & austenitic steels, BM, HAZ, BWR environment, ECP monitoring; pre-irradiation in inert gas at flat rig

� In-pile and out-of-pile SSRT studies (for EPRI)� pre-irradiated tensile specimens (∅ 2 mm), 10 dpa,

hydraulic loading, deformation rate 10-6/10-7 s-1, PWR environment

� Irradiation of RPV steels (for JAPEIC) � dry irradiation, weldments

� SSRT of pre-irradiated austenitic specimens, up to 20 dpa (for CEZ)

Experimental ProjectsZrZr--alloys cladding corrosion alloys cladding corrosion (electrically heated fuel rod(electrically heated fuel rod iimitators):mitators):

�� ZrZr--alloys behaviour at alloys behaviour at PWRsPWRs conditions (for conditions (for FRAMATOME)FRAMATOME)�� new alloysnew alloys (incl. M4, M5)(incl. M4, M5), PWR chemistry, high Li, , PWR chemistry, high Li, subcooledsubcooled boiling, corrosion, boiling, corrosion, hydridinghydriding

�� ZrZr--4 and 4 and ZrZr--1%1%NbNb behaviour at behaviour at VVERsVVERs conditions conditions (for SONS, IAEA support) (for SONS, IAEA support) �� compatibility study, corrosion, compatibility study, corrosion, hydridinghydriding, K/NH, K/NH33chemistrychemistry

�� Russian Russian ZrZr--alloys (E110, E635) corrosion behaviour alloys (E110, E635) corrosion behaviour in PWR conditionsin PWR conditions�� subcooledsubcooled boiling, corrosion, boiling, corrosion, hydridinghydriding

Experimental ProjectsWater chemistry influence on radioactivity transport Water chemistry influence on radioactivity transport and buildand build--up:up:�� Effect of Effect of Zinc injection Zinc injection inin PWRPWR conditions on corrosion and conditions on corrosion and

radioactivity radioactivity buildbuild--upup (for NUPEC/MHI)(for NUPEC/MHI)

�� Ammonia/Hydrogen/Ammonia/Hydrogen/Zinc additionZinc addition chemistry chemistry effect on effect on radioactivity buildradioactivity build--up up in VVER conditions in VVER conditions (for (for CCEZ, SE); comparison studies, EZ, SE); comparison studies, radioactivity transport, radiochemistry modellingradioactivity transport, radiochemistry modelling

�� Optimisation of VVER primary water chemistry; standard pH, Optimisation of VVER primary water chemistry; standard pH, high pH (7.4)high pH (7.4)and hydrazine chemistry, corrosion & corrosion products and hydrazine chemistry, corrosion & corrosion products release, radioactivity buildrelease, radioactivity build--upup

�� Development Development and testing and testing of a primary surface preof a primary surface pre--conditioning conditioning technology technology –– HTCT (HydroHTCT (Hydro--thermal Chromium Treatment)thermal Chromium Treatment)

�� Investigation of highInvestigation of high--temperature electromagnetic filtrationtemperature electromagnetic filtration

Experimental ProjectsHighHigh--temperature sensors temperature sensors testingtesting

�� Irradiation of a potential structure materials for ECP sensors (Irradiation of a potential structure materials for ECP sensors (for for ANERI/Hitachi/Toshiba); BWR environmentANERI/Hitachi/Toshiba); BWR environment

�� ECP sensors testing under irradiation (for ANERI/Hitachi); BWR ECP sensors testing under irradiation (for ANERI/Hitachi); BWR environment, different types of ECP sensors, water chemistry chaenvironment, different types of ECP sensors, water chemistry changes nges (NWC/HWC), (NWC/HWC), lifelife--timetime

Fusion programme (EFDA)Fusion programme (EFDA)�� Corrosion behaviour and mechanical properties of fusion reactor Corrosion behaviour and mechanical properties of fusion reactor

structure materials (e.g. EUROFER) under fusion blanket or primastructure materials (e.g. EUROFER) under fusion blanket or primary ry first wall relevant conditions (e.g. liquid metal first wall relevant conditions (e.g. liquid metal PbPb--17Li, neutron 17Li, neutron irradiation, thermal cycling, hydrogen embittermentirradiation, thermal cycling, hydrogen embitterment))

ADTT programmeADTT programmePotential structure materials corrosion behaviour and compatibilPotential structure materials corrosion behaviour and compatibility with ity with

molten salts (fluoridemolten salts (fluoride--based molten salts)based molten salts)�� Verification of neutronVerification of neutron--physics calculationsphysics calculations

Fusion Reactor Structural MaterialsInIn--pile Rig for Corrosion Tests in pile Rig for Corrosion Tests in PbPb--Li Eutectic AlloyLi Eutectic Alloy

�� Fusion Reactor (ITER); structural material (EUROFER)Fusion Reactor (ITER); structural material (EUROFER)�� EUROFER material specimens in the irradiation capsule EUROFER material specimens in the irradiation capsule

filled with filled with PbPb--15.8Li15.8Li�� Test temperature (approx. 500Test temperature (approx. 500°°C)C) and temperature gradient and temperature gradient

((~100~100--150150°°C) in the capsule C) in the capsule �� Flow of the molten Flow of the molten PbPb--Li eutectic is driven by natural Li eutectic is driven by natural

convection (in the range of few mm/s).convection (in the range of few mm/s).�� Computer code Computer code COSMOSFloWorksCOSMOSFloWorks has been used to has been used to

define and verify design of the experimental capsule (e.g. define and verify design of the experimental capsule (e.g. capsule dimensions, cooler design, number of specimens capsule dimensions, cooler design, number of specimens etc.). etc.).

�� Calculation results indicate good agreement between Calculation results indicate good agreement between measured and required temperatures.measured and required temperatures.

Fusion Reactor Structural Materials

Principle Design of the Pb-Li In-pile Rig

Fusion Reactor Structural Materials Pb-Li In-pile Rig

Comparison of Calculated and Measured Temperatures

COSMOSFloWork calc.

Tcal=390 0 CTmeas=420 0 C

Tcal=530 0 CTmeas=526,9 0 C

Primary ITER First Wall Mock-up

Beryllium

CuCrZr

Neutron Transmutation Doped Silicon�� Maximum crystal dimensions: Maximum crystal dimensions: �� Diameter 3Diameter 3”” (4(4””))�� Length 20 cm (30 cm)Length 20 cm (30 cm)

�� Typical parameters of irradiation channel Typical parameters of irradiation channel (10 MW):(10 MW):�� Thermal neutron flux:Thermal neutron flux: 2 x 102 x 101717 n/mn/m22ss�� Fast neutron flux: Fast neutron flux: 2 x 102 x 101616 n/mn/m22ss

Radionuclides Production�� Unsealed sources for nuclear medicine Unsealed sources for nuclear medicine

diagnostic and therapydiagnostic and therapy�� Sealed sources for the radiation oncologySealed sources for the radiation oncology�� Sealed sources for commercial irradiationSealed sources for commercial irradiation

Activation In Reactor�� Radio nuclides for radio pharmacy Radio nuclides for radio pharmacy 153153Sm, Sm,

161161Tb, Tb, 165165Dy, Dy, 166166Hop, Hop, 169169ErEr�� Radio nuclides for generator systemsRadio nuclides for generator systems

9999MoMo--99m99mTc, Tc, 113113SnSn--113m113mIn, In, 188188WW--188188ReRe�� Radio nuclides for sealed technical and Radio nuclides for sealed technical and

medicinal sources:medicinal sources:e.g. e.g. 6060Co, Co, 192192Ir, Ir, 182182Ta, Ta, 198198AuAu

Irradiation Possibilities�� Rotary irradiation channels DONARotary irradiation channels DONA

φφ 63,5 and 63,5 and φφ 80 mm80 mm��Max. neutron flux density: Max. neutron flux density: 2 x 102 x 101717 n/mn/m22ss

�� Narrow channel in Be reflector Narrow channel in Be reflector -- φφ 40 mm40 mm��Max. neutron flux density: Max. neutron flux density: 9 x 109 x 101717 n/mn/m22ss

�� Wide channel in HWide channel in H22O reflector O reflector -- φφ 62 mm62 mm��Max. neutron flux density: Max. neutron flux density: 9 x 109 x 101717 n/mn/m22ss

�� Wide channel surrounded with fuel Wide channel surrounded with fuel -- φφ 62 mm62 mm��Max. neutron flux density: Max. neutron flux density: 1.4 x 101.4 x 101818 n/mn/m22ss

Irradiation Capsule for 192Ir Wire Sources

Boron Neutron Capture Therapy�� Treatment of human brain Treatment of human brain gliomasgliomas�� Clinical tests of the therapyClinical tests of the therapy�� Phase I study Phase I study –– toxicity of the BNCTtoxicity of the BNCT�� 9 patients in the project9 patients in the project�� 5 patients treated5 patients treated

BNCT Beam Design

BNCT Beam Parameters� Φth = (1.12 ± 0.05)x108 cm-2s-1

� Φepi = (6.98 ± 0.27)x108 cm-2s-1

� Φfast = (6.94 ± 0.40)x107 cm-2s-1

� (dKfn/dt)/Φepi=1.45x10-12Gy cm2(estimated 20%)

� (dKg/dt)/Φepi=7.88x10-13Gy cm2(estimated 20%)estimated 20%)