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Hybrid Capsule Assembly for Irradiation Testing. Donna P. Guillen and Brian Durtschi Idaho National Laboratory Adam Zabriskie and Heng Ban Utah State University. 2011 RELAP5 IRUG Meeting Salt Lake City, Utah June 26, 2011. Outline. Genesis of Experiment Background

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Hybrid capsule assembly for irradiation testing

Hybrid Capsule Assembly for Irradiation Testing

Donna P. Guillen and Brian Durtschi

Idaho National Laboratory

Adam Zabriskie and Heng Ban

Utah State University

2011 RELAP5 IRUG Meeting

Salt Lake City, Utah

June 26, 2011


Outline
Outline

  • Genesis of Experiment

    • Background

    • Design Requirements

  • Absorber Block Design

    • New Material Developed

    • Specimen Fabrication

  • Objectives of Irradiation Experiment

  • Requirements for in-Pile Corrosion Test

    • Specimen Holder Hardware

    • Autoclave Tests and Analysis

  • Recommendations


Genesis of experiment
Genesis of experiment

Establish a domestic high intensity fast-flux irradiation test capability for nuclear fuels and materials for advanced concept nuclear reactors

Provide an interim fast-flux test capability to test nuclear fuels and materials

  • Could be brought on-line in 5-6 yrs.

  • Much sooner than building a new fast-flux test reactor

    Use existing irradiation facility with irradiation volume large enough to irradiate meaningful numbers of test specimens

    Potential users include Generation IV Reactor Program, Advanced Fuel Cycle Initiative, and Space Nuclear Programs


Background
Background

Gas Test Loop project

  • Mission need established 2004

  • CD1-A in 2005 authorized resolution of key feasibility issues

    Original Gas Test Loop Conceptual Design estimated cost was $80M to $100M depending on contingency

    Challenge - Find a way to make the Gas Test Loop less expensive by using a different cooling approach than pressurized helium

    Boosted Fast Flux loop concept explored


Bffl design requirements
BFFL Design Requirements

Fast flux (E > 0.1 MeV) ≥ 1015 n/cm2·s

Fast-to-thermal neutron ratio≈ 40

Fuel specimens

Up to 3 simultaneous experiments

Diameter ~ 1 cm

Axial heating rates ≤ 2.3 kW/cm

Total heat load ≤ 200kW

Maintain test article surface temp. ≤ 500 °C nominal, 1000 °C max.

Locate in ATR large flux trap with IPT outer diameter = 9.128 cm (3.593 inches)


Absorber block design
Absorber Block Design

Concept developed to filter out a large portion of the thermal flux component by using a thermally conductive neutron absorber block

Use Hf-Al alloy (Al3Hf-Al) to conduct heat away from the experiments

Serves a dual role

High thermal conductivity of Al

Thermal neutron absorption of Hf

Limit amt. of pressurized water for cooling

Pressurized water systems already exist in ATR

If water is not close to experiments, thermalization may be manageable

Use booster fuel to augment neutron flux


Specimen fabrication
Specimen Fabrication

  • Cast Al3Hf intermetallic

  • Al3Hf-Al composite specimens

    • Al3Hf is brittle, can be easily ground into powder

    • Grind

      • Mortar and pestle

      • Spex mill

    • Sieve by particle size

      • <35 μm, 75-105 μm, and 105-149 μm

    • Mix Al3Hf powder with Al powder

      • Al3Hf vol%: 20.0, 28.4, 36.5, 100

    • Press into pucks

  • Machine to size


Specimen geometries
Specimen Geometries

  • Due to brittleness of material, could not machine intermetallic into thin disks

  • Irradiation specimen geometries designed to accommodate thermophysical property measurements


Irradiation experiment in inl s atr
Irradiation Experiment in INL’s ATR

Objectives:

Thermophysical and mechanical properties of Al3Hf intermetallic and Al3Hf-Al metal matrix composite (MMC) at different temperatures

Physical/morphological, metallurgical, and microstructural changes of the Al3Hf-Al composite after different cycles of irradiation

Effect of irradiation on the thermophysical and material properties of the Al3Hf intermetallic and Al3Hf-Al composite.

Decay products of hafnium (presence of metastable isotopes)

Corrosion behavior of the Al3Hf-Al composite

B2

position

Focus of this presentation


Safety requirements for in pile test with corrosion specimens
Safety Requirements for In-Pile Test with Corrosion Specimens

  • To assess corrosion behavior of the new material under reactor operating conditions, it must be exposed to the reactor primary coolant

  • ATR Safety requirements with respect to corrosion specimens:

    • The irradiation experiment hardware must allow adequate coolant circulation past corrosion specimens

      • No regions of stagnant water!

    • The corrosion specimens must maintain integrity during irradiation

      • No release of particles into coolant!


Requirement 1
Requirement #1 Specimens

Irradiation experiment hardware must allow adequate coolant circulation past corrosion specimens


New capsule design
New Capsule Design Specimens

A new type of capsule assembly has been designed for irradiation testing of fuels or materials

  • Capsules are used to house fuel or material specimens for irradiation testing in a nuclear reactor, such as ATR

    Traditionally, experiments are designated either as drop-in (static, hermetically sealed from exposure to coolant) or flow-through (all specimens exposed to coolant)

  • Hybrid capsule design separates flow-through specimens from static specimens to enable testing in a single irradiation position


Hybrid capsule design
Hybrid Capsule Design Specimens

This new hybrid design holds fuel or material specimens in two different types of sections, integrated into a single capsule assembly:

  • static section – specimens remain isolated from the coolant

  • flow-through section – flow enters/exits through “windows” in the capsule, exposing selected specimens to the reactor primary coolant


Advantages of hybrid capsule design
Advantages of Hybrid Capsule Design Specimens

  • The benefits of this design are the ability to expose a limited number of specimens to the reactor coolant, while simultaneously isolating other specimens from coolant exposure

  • Enables two types of irradiation tests to be performed with a single irradiation test assembly

  • Allows enhanced cooling and/or corrosion testing of selected specimens

  • Modular design facilitates reconfigurability and permits flexibility to add or remove flow-through sections as required by the experiment objectives

  • Experiments can be performed in one irradiation campaign, rather than over several campaigns, with a substantial saving in costs, time and resources


Corrosion specimen holder
Corrosion Specimen Holder Specimens

  • Vertical orientation of specimens to preclude buildup of debris from reactor coolant

  • Notched design to securely hold specimens in place

  • Ramps to entrain flow into flow-through section

  • Holder maximizes specimen surface area exposed to coolant

  • Paired “windows” allow coolant to flow in/out, permits circulation and convective cooling of specimens

  • Constant outer diameter of capsule for ease of reactor insertion/removal




Flow test experiment
Flow Test Experiment Specimens

  • Idaho State University Skyline Lab test loop

  • Flow test performed to determine pressure drop

    • System A – solid rod (0.625” dia.) in basket

    • System B – solid rod with flow through specimen holder (test cap)

  • Pressure tap holes located ½” above and below test cap


Flow through capsule result
Flow-Through Capsule Result Specimens

  • Unexplained pressure drop discrepancy from experiment

  • Preliminary CFD analysis did not explain result

  • Further experimentation and simulation needed:

    • Reproducible result from experiment

    • CFD analysis spanning full flow range and both geometries


Pressure drop comparison
Pressure Drop Comparison Specimens

  • Calculate velocity through triform, knowing total flow rate

    • Suction orifice in a thin wall in the presence of passing flow

    • Flow exit approx. as single top-hinged flap

    • Abrupt area change across specimen holder

    • Thick-edged orifice installed in a transition

  • Flow splits into parallel branches, then merges again after exiting endcap

    • ζtot := ζent + ζtriin + ζtriout + ζexit

    • 23% of flow goes through end cap

Pmax=2.32 psi for Impress transducer


Possible explanations
Possible Explanations Specimens

  • Expected Result – Addition of a parallel flow path should decrease pressure drop

    • Branch with lower resistance should get more flow

    • Branch with higher resistance should get less flow

  • Actual Result – Pressure drop increased with test cap

  • Plausible explanation for increased pressure drop

    • Disturbance of flow in annulus near inlets

∆P1=∆P2

Q=Q1 + Q2

∆P1 ,Q1

test cap

Q

Q

flow inside basket

∆P2 ,Q2


Requirement 2
Requirement #2 Specimens

Corrosion specimens must maintain integrity during irradiation


Pre irradiation corrosion testing of specimens
Pre-Irradiation Corrosion Testing of Specimens Specimens

  • Pre-irradiation autoclave testing necessary to assess severity of corrosion

    • Data essential to incorporate flow-through capsules in experiment

    • Does hydroxide grow underneath particles?

    • Are particles likely to loosen under hydraulic pressure?

  • Tested four Al3Hf-Al specimens with different particle size ranges:

    • 1) <35 μm, 2) 53-75 μm, 3) 75-105 μm, and 4)105-149 μm

  • Three sets of autoclave tests

    • Cold pressed material

    • Hot pressed (damaged) material

    • Hot pressed material

  • Examination:

    • Surfaces by SEM

    • Cross-sections by metallography

No boehmite at aluminide boundary

Boehmite presence indicates surface connection


Autoclave procedure
Autoclave Procedure Specimens

  • Used to apply an adherent boehmite surface film onto ATR fuel plates before irradiation

  • Very good test of the stability of the materials and a good indicator of the worst possible behavior in the ATR core

    • If autoclaving of the material does not result in significant degradation of the material, it is highly probable that it can withstand the less invasive chemical environment during irradiation

  • Specimens treated in deionized water:

    • ~12 mm diameter and 1-2 mm thick

    • 185 ± 15ºC

    • pH 8.1 (initially), pH 7.15 (following exposure)

    • 17.5 hrs

    • 150 psi


Corrosion tests

Fabrication Technique Specimens

Corrosion Tests

Conclusions

Cold pressed MMC

Use smallest particle size & round particles

Hot pressed MMC (damaged)

Particles pulled from matrix due to use of acrylic mount (shrinkage)

May need to clad or functionally grade material

Hot pressed MMC


Recommendations
Recommendations Specimens

To satisfy ATR Safety requirements:

  • Requirement: The irradiation experiment hardware must allow adequate coolant circulation past specimens

    • Recommended Action:

      • Eliminate possibility of regions of stagnant water by redesigning corrosion specimen holder

  • Requirement: The material must maintain integrity during irradiation

    • Recommended Actions:

      • Functionally grade or clad material to avoid potential for release of particles into coolant

      • Fabricate material using round particles


The end questions answers
The End SpecimensQuestions? Answers?


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