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Session I.4.8Session I.4.8

Part I Review of Fundamentals

Module 4 Sources of Radiation

Session 8 Research Reactors

IAEA Post Graduate Educational CourseIAEA Post Graduate Educational CourseRadiation Protection and Safe Use of Radiation SourcesRadiation Protection and Safe Use of Radiation Sources

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OverviewOverview

In this session we will discuss the types of In this session we will discuss the types of Research ReactorsResearch Reactors

We will also discuss where these Research We will also discuss where these Research Reactors are locatedReactors are located

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IntroductionIntroduction

Research ReactorsResearch Reactors

Not used to generate electrical powerNot used to generate electrical power

Produce neutrons for various usesProduce neutrons for various uses

Use higher enriched Use higher enriched 235235U than power U than power reactorsreactors

Approximately 238 worldwideApproximately 238 worldwide

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TypesTypes

Pool type (67 units)Pool type (67 units) Curved aluminum clad fuel platesCurved aluminum clad fuel plates Control rodsControl rods Water for moderation and coolingWater for moderation and cooling Beryllium or graphite neutron reflectors Beryllium or graphite neutron reflectors

commoncommon Empty channels for experimentsEmpty channels for experiments Apertures for neutron beamsApertures for neutron beams

Tank Type (32 units)Tank Type (32 units)

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TypesTypes

TRIGA (40 units)TRIGA (40 units) 60-100 cylindrical fuel elements (36 mm 60-100 cylindrical fuel elements (36 mm

diameter)diameter) Uranium fuel and zirconium hydride Uranium fuel and zirconium hydride

moderatormoderator Water for moderation and coolingWater for moderation and cooling Beryllium or graphite neutron reflectors Beryllium or graphite neutron reflectors

commoncommon Pulsed up to 25,000 MWPulsed up to 25,000 MW

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TypesTypes

Some produce radioisotopesSome produce radioisotopes

TypeType NumberNumber

Critical assemblies (zero power)Critical assemblies (zero power) 6060

Test reactorsTest reactors 2323

Training facilitiesTraining facilities 3737

PrototypesPrototypes 22

Generating electricityGenerating electricity 11

ResearchResearch 160160

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TypesTypes

Some moderated by heavy water (12) or Some moderated by heavy water (12) or graphitegraphite

Some are fast reactors (no moderator and Some are fast reactors (no moderator and mixed U - Pu fuel)mixed U - Pu fuel)

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FuelFuel

Typically a few kilogramsTypically a few kilograms

High enriched uranium (HEU) >20% High enriched uranium (HEU) >20% 235235U U compared to 3-5% for power reactorscompared to 3-5% for power reactors

Typically plates or cylinders Typically plates or cylinders of Uranium-Aluminum alloy of Uranium-Aluminum alloy clad with pure Aluminum clad with pure Aluminum compared to ceramic UOcompared to ceramic UO2 2

pellets in power reactorspellets in power reactors

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FuelFuel

Security concerns over the use of HEU have led to Security concerns over the use of HEU have led to development of high-density, low-enriched uranium development of high-density, low-enriched uranium (LEU) fuel(LEU) fuel

Fuel density for U-Al fuel increased fromFuel density for U-Al fuel increased from1.3 - 1.7 g/cm1.3 - 1.7 g/cm33 to 2.3 - 3.2 g/cm to 2.3 - 3.2 g/cm33 as enrichment as enrichment decreaseddecreased

In 1996, with the Summer Olympics scheduled to be In 1996, with the Summer Olympics scheduled to be held in Atlanta, Georgia in the USA, security held in Atlanta, Georgia in the USA, security concerns caused Georgia Tech University to concerns caused Georgia Tech University to remove the HEU from its research reactorremove the HEU from its research reactor

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UsesUses

Analysis and testing of materialAnalysis and testing of material Production of radioisotopesProduction of radioisotopes Fusion researchFusion research Environmental scienceEnvironmental science Advanced material developmentAdvanced material development Drug designDrug design Nuclear medicineNuclear medicine

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UsesUses

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UsesUses

Neutron scattering experiments to study Neutron scattering experiments to study structure of materials at atomic levelstructure of materials at atomic level

Neutron activation for detecting presence Neutron activation for detecting presence of small amounts of materialof small amounts of material

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UsesUses

Radioisotope productionRadioisotope production

9090Y from Y from 8989Y for treatment of liver cancerY for treatment of liver cancer

9999Mo from fission of Mo from fission of 235235U foil to produce U foil to produce 99m99mTc for nuclear medicineTc for nuclear medicine

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UsesUses

Industrial processingIndustrial processing

Neutron transmutation doping of Neutron transmutation doping of silicon crystalssilicon crystals

Study changes resulting from intense Study changes resulting from intense neutron bombardment (e.g., neutron bombardment (e.g., embrittlement of steel)embrittlement of steel)

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Spent FuelSpent Fuel

U-Al fuels can be reprocessed in FranceU-Al fuels can be reprocessed in France

United States has offered to take back United States has offered to take back spent fuel resulting from fuel originally spent fuel resulting from fuel originally supplied by the USsupplied by the US

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Chicago Pile ReactorsChicago Pile Reactors

CP-2CP-2

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Chicago Pile ReactorsChicago Pile Reactors

CP-3CP-3

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Chicago Pile ReactorsChicago Pile Reactors

CP-5CP-5

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zero‑power full‑scale reactor core mockup assemblies zero‑power full‑scale reactor core mockup assemblies used to:used to:

gain understanding of a variety of reactor conceptsgain understanding of a variety of reactor concepts assist in the engineering design of these reactor assist in the engineering design of these reactor

systemssystems

Zero Power ReactorZero Power Reactor

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Zero Power ReactorZero Power Reactor

ZPR‑2, a heavy‑water ZPR‑2, a heavy‑water reactor, began operation in reactor, began operation in 1952 and was used in the 1952 and was used in the development of the development of the Savannah power reactors Savannah power reactors used for plutonium used for plutonium productionproduction

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Zero Power ReactorZero Power Reactor

ZPR‑6, designed to ZPR‑6, designed to advance fast reactor advance fast reactor technology for civilian technology for civilian power use, went into power use, went into operation in July 1963operation in July 1963

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Test ReactorsTest Reactors

The Materials Test The Materials Test Reactor (MTR) completed Reactor (MTR) completed in 1952 in Idaho was the in 1952 in Idaho was the workhorse of the U.S. workhorse of the U.S. Atomic Energy Atomic Energy Commission's test Commission's test reactor program for reactor program for many years. It was the many years. It was the first reactor to be builtfirst reactor to be built

solely for testing materials to be used in other reactors.solely for testing materials to be used in other reactors.

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Test ReactorsTest Reactors

The Transient Reactor The Transient Reactor Test Facility (TREAT), Test Facility (TREAT), a pulsed, graphite - a pulsed, graphite - moderated reactor, moderated reactor, was designed to safely was designed to safely generate very large generate very large integrated bursts of integrated bursts of thermal neutrons for thermal neutrons for use in destructiveuse in destructive

testing of fast reactor fuel elements. This reactor began testing of fast reactor fuel elements. This reactor began operation in February 1959 at ANL‑Idaho.operation in February 1959 at ANL‑Idaho.

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SLOWPOKESLOWPOKE

Large sample irradiation tube Large sample irradiation tube

Small sample irradiation tube Small sample irradiation tube

Central control rod Central control rod

Beryllium annulus Beryllium annulus

Lower beryllium reflector Lower beryllium reflector

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SLOWPOKESLOWPOKE

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SLOWPOKESLOWPOKE

prime functions are to perform nondestructive prime functions are to perform nondestructive elemental analysis and produce quantities of selected elemental analysis and produce quantities of selected radioactive material for use in industry and medicineradioactive material for use in industry and medicine

SLOWPOKE laboratories have been utilized in a SLOWPOKE laboratories have been utilized in a number of different fields such as:number of different fields such as:

Trace element identification Trace element identification Radiotracer supply Radiotracer supply Forensic science Forensic science Environmental analysis Environmental analysis Radioactivity counting Radioactivity counting

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Trace Element IdentificationTrace Element Identification

The The SLOWPOKESLOWPOKE Facility can analyze samples for a Facility can analyze samples for a number of elements number of elements simultaneouslysimultaneously, with a , with a sensitivity at the sensitivity at the ppmppm level level

The analytical techniques used require minimal The analytical techniques used require minimal sample preparation and are sample preparation and are nondestructivenondestructive permitting retention of valuable samples or reuse of permitting retention of valuable samples or reuse of the same sample for further measurementsthe same sample for further measurements

The technique can be both rapid and inexpensive The technique can be both rapid and inexpensive and over 30 elements can be readily identifiedand over 30 elements can be readily identified

SLOWPOKESLOWPOKE

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Radiotracer SupplyRadiotracer Supply

The The SLOWPOKESLOWPOKE Reactor can produce highly useful Reactor can produce highly useful short-lived radioactive tracersshort-lived radioactive tracers

Some of the applications for which radioactive Some of the applications for which radioactive tracers have been produced by tracers have been produced by SLOWPOKESLOWPOKE include: include:

Industry (example - leak detection)Industry (example - leak detection) Medicine (example - labeling of pharmaceuticals )Medicine (example - labeling of pharmaceuticals )

SLOWPOKESLOWPOKE

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Forensic ScienceForensic Science

Neutron Activation Analysis (NAA) can be used to Neutron Activation Analysis (NAA) can be used to identify elements in samples that provide clues to identify elements in samples that provide clues to solving cases:solving cases:

Arsenic in suspected poisoning cases can be Arsenic in suspected poisoning cases can be determined in hair samplesdetermined in hair samples

SLOWPOKESLOWPOKE

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Environmental AnalysisEnvironmental Analysis

The techniques of neutron activation analysis (NAA) The techniques of neutron activation analysis (NAA) can also be applied to measure the elemental can also be applied to measure the elemental composition of environmental samples:composition of environmental samples:

Toxic organo-chlorine compounds such as PCBs, Toxic organo-chlorine compounds such as PCBs, dioxins and furans can be selectively extracted dioxins and furans can be selectively extracted from river water, effluent, settling ponds and from river water, effluent, settling ponds and assayed for their chlorine content by NAAassayed for their chlorine content by NAA

Mercury in compounds produced by industrial Mercury in compounds produced by industrial processes can be assayed in the same wayprocesses can be assayed in the same way

SLOWPOKESLOWPOKE

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Radioactivity CountingRadioactivity Counting

Low levels of man-made or naturally occurring Low levels of man-made or naturally occurring radioactivity in the environment can be measured radioactivity in the environment can be measured using the sophisticated analytical instrumentation at using the sophisticated analytical instrumentation at SLOWPOKESLOWPOKE..

The fallout isotope The fallout isotope 137137Cs provides a fixed activity-Cs provides a fixed activity-against-depth profile in undisturbed soil for soil-against-depth profile in undisturbed soil for soil-erosion studieserosion studies

The radionuclidic purity of The radionuclidic purity of 125125I labelled cancer I labelled cancer diagnostic kits can be determineddiagnostic kits can be determined

SLOWPOKESLOWPOKE

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SLOWPOKESLOWPOKE

Reactor SpecificationsReactor SpecificationsTypeType Pool and TankPool and TankLicensed limitLicensed limit 20 kW20 kWFuelFuel Extruded Uranium/aluminum alloyExtruded Uranium/aluminum alloyModeratorModerator Light waterLight waterCoolingCooling Convection/conductionConvection/conductionCore diameter/heightCore diameter/height 22cm/22.1cm22cm/22.1cmCritical mass Critical mass 235235UU 816.664g816.664gFuel lifeFuel life 6.4 x 106.4 x 101919 nvt (at small inner sites) nvt (at small inner sites) Irradiation ParametersIrradiation Parameters

ParameterParameter Inner SitesInner Sites Outer SitesOuter Sites

Thermal fluxThermal flux 1 x 101 x 101212 0.5 x 100.5 x 101212

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TRIGATRIGA

most widely used non‑power nuclear reactor in the most widely used non‑power nuclear reactor in the worldworld

In 24 countries, 66 in use or under construction at:In 24 countries, 66 in use or under construction at: universitiesuniversities government and industrial laboratoriesgovernment and industrial laboratories medical centersmedical centers

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TRIGATRIGA

used in many diverse applicationsused in many diverse applications production of radioisotopes for medicine and production of radioisotopes for medicine and

industryindustry treatment of tumorstreatment of tumors nondestructive testingnondestructive testing basic research on the properties of matterbasic research on the properties of matter education and trainingeducation and training

operate at thermal power levels from less than 0.1 operate at thermal power levels from less than 0.1 to 16 megawatts and pulsed to 22,000 megawattsto 16 megawatts and pulsed to 22,000 megawatts

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TRIGATRIGA

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High Flux Isotope ReactorHigh Flux Isotope Reactor

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High Flux Isotope ReactorHigh Flux Isotope Reactor

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High Flux Isotope ReactorHigh Flux Isotope Reactor

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High Flux Isotope ReactorHigh Flux Isotope Reactor

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EgyptEgypt

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EgyptEgypt

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EgyptEgypt

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EgyptEgypt

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GermanyGermany

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IndiaIndia

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IndiaIndia

KAMINI - REACTORItem DescriptionNature of Reactor system Tank typeReactor vault size 2.8m X 6.2m X 6.7 m highReactor tank size 2 m dia., 4.18 m high, 12 mm thk.Nominal power 30 KWFuel U-233 (20 Wt %) - Al alloyNumber of fuel subassemblies 9Fuel plates per subassembly 8Gap between fuel plates 6 mmFuel plate size 2 mm X 62 mm X 260 mmFuel assembly size 66 mm X 66 mm X 275 mmTotal fuel inventory 600 gCore size 204 mm X 204 mm X 275 mm

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IndiaIndia

KAMINI - REACTORItem DescriptionReflector material BeO encased in ZircaloyThickness 200 mmNumber of reflector modules 20Moderator/Coolant/Shield material Demineralized waterQuantity 12.5 MTCore cooling mode By natural convectionType of control By absorber platesAbsorber material CadmiumBeam tubes 3Flux at outer end of beam tube 10E+6 to 10E+7 n/ cm2/secFlux at irradiation sites 10E+11 to 10E+12 n/cm2/secCore flux 10E+12 n/cm2/secCapsule size for transfer system 12 mm dia. X 30 mm longMax. sample size (thimble irradiation) 30 mm dia. X 50 mm long

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KoreaKorea

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PakistanPakistan

PARR-1PARR-1

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ThailandThailand

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LocationLocation

RussiaRussia 6262

United StatesUnited States 5454

JapanJapan 1818

FranceFrance 1515

GermanyGermany 1414

ChinaChina 1313

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

ArgentinaArgentina poolpool 500500 9090 USAUSAAustriaAustria TrigaTriga 250250 20‑70 20‑70 USAUSA

ArgonautArgonaut 1010 20‑9020‑90 USAUSAAustraliaAustralia heavy waterheavy water 10,00010,000 6060 UK, USAUK, USABelgiumBelgium tanktank 100,000100,000 74‑9374‑93 USAUSACanadaCanada poolpool 5,0005,000 9393 USAUSA

SlowpokeSlowpoke 20 (x 3)20 (x 3) 9393 USAUSAChileChile poolpool 2,0002,000 9090 FranceFrance

poolpool 5,0005,000 20‑4520‑45 USAUSA

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

ChinaChina Crit fastCrit fast 0.050.05 9090 ChinaChinatanktank 125,000125,000 9090 ChinaChinaMNSRMNSR 2727 9090 ChinaChinapoolpool 50005000 9090 ChinaChinaMNSRMNSR 30‑33 (x 3)30‑33 (x 3) 9090 ChinaChina

Czech RepCzech Rep tanktank 10,00010,000 3636 RussiaRussiapoolpool 55 3636 RussiaRussia

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

FranceFrance poolpool 0.10.1 90‑9390‑93 USAUSATank in poolTank in pool 0.10.1 3‑933‑93 USA, FranceUSA, FranceCrit fastCrit fast 33 12‑2512‑25 USAUSAheavy waterheavy water 58,30058,300 9393 USAUSApoolpool 14,00014,000 9393 USAUSAFBRFBR 563,000563,000 22‑2822‑28 FranceFranceArgonautArgonaut 100100 9393 USAUSAhomogeneoushomogeneous 11 9393 USAUSA

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

GermanyGermany poolpool 4,0004,000 45‑9345‑93 USAUSAheavy waterheavy water 23,00023,000 80‑9380‑93 USAUSApoolpool 10,00010,000 20‑9320‑93 USAUSAtanktank 0.010.01 3636 RussiaRussia

GhanaGhana MNSRMNSR 3030 9090 ChinaChinaGreeceGreece poolpool 55 20‑9320‑93 USAUSAHungaryHungary tanktank 10,00010,000 3636 RussiaRussiaIsraelIsrael poolpool 5,0005,000 9393 USAUSA

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

IndiaIndia poolpool 10001000 9393 UK & FranceUK & FranceFBRFBR 40,00040,000 55‑7055‑70 IndiaIndia

IranIran MNSRMNSR 3030 9090 ChinaChinaItalyItaly Fast sourceFast source 55 9393 USAUSAJamaicaJamaica SlowpokeSlowpoke 2020 9393 USAUSAJapanJapan ArgonautArgonaut 0.010.01 9090 USAUSA

tanktank 50005000 9393 USAUSACrit fastCrit fast 22 20‑9320‑93 USA, UKUSA, UKTankTank 50,00050,000 20‑4620‑46 USAUSACrit assemblyCrit assembly 0.10.1 45‑9345‑93 USAUSA

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

Korea Ð NorthKorea Ð North poolpool 8,0008,000 3636 RussiaRussiaKazakhstanKazakhstan poolpool 6,0006,000 3636 RussiaRussia

tanktank 10,00010,000 3636 RussiaRussiatanktank 60,00060,000 9090 RussiaRussia

LibyaLibya poolpool 10,00010,000 8080 RussiaRussiaMexicoMexico TrigaTriga 10001000 20‑7020‑70 USAUSANetherlandsNetherlands ArgonautArgonaut 3030 9090 USAUSA

poolpool 20002000 20‑9320‑93 USAUSATank in poolTank in pool 45,00045,000 9393 USAUSA

PakistanPakistan MNSRMNSR 3030 9090 ChinaChina

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

PolandPoland poolpool 30,00030,000 36‑8036‑80 RussiaRussiaPortugalPortugal poolpool 10001000 9393 USAUSARomaniaRomania TrigaTriga 14,00014,000 20‑9320‑93 USAUSARussiaRussia variousvarious (39 units,(39 units, VariousVarious RussiaRussia

12 over 1 MW)12 over 1 MW)South AfricaSouth Africa Tank in poolTank in pool 20,00020,000 87‑9387‑93 S.AfricaS.AfricaSwedenSweden poolpool 10001000 9393 USAUSASwitzerlandSwitzerland homogenoushomogenous 22 9090 USAUSASyriaSyria MNSRMNSR 3030 9090 ChinaChina

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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CountryCountry TypeType PowerPower EnrichmentEnrichment Source of fuelSource of fuelKWKW %%

UKUK Fast burstFast burst 0.50.5 37.537.5 UKUKPoolPool 100100 8080 UKUK

UkraineUkraine tanktank 10,00010,000 3636 RussiaRussiaUSAUSA variousvarious (22 units(22 units VariousVarious USAUSA

13 - 1 MW or more)13 - 1 MW or more)UzbekistanUzbekistan tanktank 10,00010,000 3636 RussiaRussiaVietnamVietnam poolpool 500500 3636 RussiaRussiaYugoslaviaYugoslavia heavy waterheavy water 0.0010.001 Up to 80Up to 80 RussiaRussia

Total of 38 countries with about 130 units (data published in 2000)Total of 38 countries with about 130 units (data published in 2000)

TaiwanTaiwan poolpool 3030 9393 USAUSA

HEU Research Reactors HEU Research Reactors WorldwideWorldwide

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Where to Get More InformationWhere to Get More Information

Cember, H., Introduction to Health Physics, 3Cember, H., Introduction to Health Physics, 3rdrd Edition, McGraw-Hill, New York (2000)Edition, McGraw-Hill, New York (2000)

Firestone, R.B., Baglin, C.M., Frank-Chu, S.Y., Eds., Firestone, R.B., Baglin, C.M., Frank-Chu, S.Y., Eds., Table of Isotopes (8Table of Isotopes (8thth Edition, 1999 update), Wiley, Edition, 1999 update), Wiley, New York (1999)New York (1999)

International Atomic Energy Agency, The Safe Use International Atomic Energy Agency, The Safe Use of Radiation Sources, Training Course Series No. 6, of Radiation Sources, Training Course Series No. 6, IAEA, Vienna (1995)IAEA, Vienna (1995)