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IAEA Sources of Radiation Research Reactors Day 4 – Lecture 4 1.

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IAEA Sources of Radiation Research Reactors Day 4 – Lecture 4 1
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Page 1: IAEA Sources of Radiation Research Reactors Day 4 – Lecture 4 1.

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Sources of Radiation

Research Reactors

Day 4 – Lecture 4

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Objective

To discuss the types and uses of Research Reactors

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Contents

Types of Research Reactors• Pool Type Reactor• TRIGA Reactors• Other Reactors/ Critical Assemblies

Uses of Research Reactors

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Introduction

Research Reactors

Not used to generate electrical power

Produce neutrons for various uses

Use higher enriched 235U than power reactors

Approximately 266 in operation worldwide (January 2014)

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Types

Pool type (61 units)* Curved aluminum clad fuel plates Control rods Water for moderation and cooling Beryllium or graphite neutron reflectors

common Empty channels for experiments Apertures for neutron beams

Tank Type (27 units)*

* Research Reactors data is from Jan. 2014

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Pool Type Reactor

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Test Reactors

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

solely for testing materials to be used in other reactors.

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Types

TRIGA (37 units)* 60-100 cylindrical fuel elements (36 mm

diameter) Uranium fuel and zirconium hydride

moderator Water for moderation and cooling Beryllium or graphite neutron reflectors

common Operate at thermal power levels from less

than 0.1 to 16 megawatts and pulsed to 25,000 MW

* Data from Jan. 2014

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TRIGA

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Types

Some produce radioisotopes

Type Number*

Critical assemblies (zero power)

79

Test reactors 15

Training facilities 21

Prototypes 2

Generating electricity 1

Research 138

* Data from Jan. 2014

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Types

Some moderated by heavy water (10) or graphite

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

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Uses

Analysis and testing of material Production of radioisotopes Fusion research Environmental science Advanced material development Drug design Nuclear medicine

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Uses

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Uses

Neutron scattering experiments to study structure of materials at atomic level

Neutron activation for detecting presence of small amounts of material

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Uses

Radioisotope production

90Y from 89Y for treatment of liver cancer

99Mo from fission of 235U foil to produce 99mTc for nuclear medicine

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Uses

Industrial processing

Neutron transmutation doping of silicon crystals

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

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Chicago Pile Reactors

CP-2

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

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

systems

Zero Power Reactor

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Zero Power Reactor

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

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Zero Power Reactor

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

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SLOWPOKE

Large sample irradiation tube

Small sample irradiation tube

Central control rod

Beryllium annulus

Lower beryllium reflector

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SLOWPOKE

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

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

Trace element identification Radiotracer supply Forensic science Environmental analysis Radioactivity counting

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SLOWPOKE

Reactor SpecificationsType Pool and TankLicensed limit 20 kWFuel Extruded Uranium/aluminum alloyModerator Light waterCooling Convection/conductionCore diameter/height 22cm/22.1cmCritical mass 235U 816.664gFuel life 6.4 x 1019 nvt (at small inner sites) Irradiation Parameters

Parameter Inner Sites Outer Sites

Thermal flux 1 x 1012 0.5 x 1012

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High Flux Isotope Reactor

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Where to Get More Information

Cember, H., Johnson, T. E, Introduction to Health Physics, 4th Edition, McGraw-Hill, New York (2009)

International Atomic Energy Agency, Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources (PGEC), Training Course Series 18, IAEA, Vienna (2002)

IAEA Research Reactor Database http://nucleus.iaea.org/RRDB/RR/ReactorSearch.aspx?rf=1


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