ML22336A105
| ML22336A105 | |
| Person / Time | |
|---|---|
| Issue date: | 12/08/2022 |
| From: | NRC/OCM |
| To: | |
| Shared Package | |
| ML22293A445 | List: |
| References | |
| M221208 | |
| Download: ML22336A105 (21) | |
Text
Nuclear fuel testing capabilities at NRG, Petten (NL)
NRC-meeting Sander van Til, MSc.
8-12-2022 K6255/22.247985 EU DuC= N
2 Aerial view of the NRG site Petten
Amsterdam Arnhem
3 The High Flux Reactor (HFR)
Tank in pool MTR
45 MW thermal power
Stable and constant flux profile in each irradiation position
Main applications Isotope production Nuclear energy services R&D
30 operation days per irradiation cycle, 9 cycles/year (~290 FPD/y)
Operational positions
In-core (17)
Poolside facility (12)
Horizontal beam tubes (12)
4 HFR overview; core plan
5 Fuel and Material irradiations Fuels UO2 / MOX (LWR)
- Irradiation induced creep HTR
- Qualification of HTR fuel pebbles SFR/LFR
- High Pu-content MOX
- Pu-nitride
- Am-transmutation candidates
- Matrix fuels MSR
- Fluoride and chloride salts
- Interaction with graphite and steels
- Radiolysis of fluoride salts Materials Nuclear graphite
- Life time extension of AGRs in the UK
- Qualification of nuclear graphite for MSR application
- Qualification of nuclear graphite for HTR application Steels
- RPV materials and Long Term Operation (LTO)
- Scientific research on irradiation effects in RPV materials
- He-embrittlement in Ni-based steels
6 Example HTR fuel qualification 5 pebbles are in graphite samples holder Double containment A total of 48 thermocouples for accurate temperature registration Online gas monitoring (online R/B of fission gases)
Including neutron fluence registration Self Powered Neutron Detectors Activation monitor sets Kept central temperatures at 1050 +/- 50 °C
7 Example Fuel irradiations (rodlet)
Main specs/options
- Sodium filled or dry sample holder
- Up to 700 mm
- Cd or Hf shroud for spectrum tailoring
- Instrumented sample holder
- Thermocouples
- Pressure transducers
- SPND
- Neutron fluence monitor sets Temperature control through gas gap of double containment Stable Ttarget within 20°C
8 Hot Cell Facility - Fuel studies Fuel dismantling in inert atmosphere Non-Destructive Testing Fuel dissolution studies Flexible Inner boxes SEM - EDS JEOL 6490 LV SEM, in alpha hot cell
9 Overview of available PIE Non exhaustive list of Post Irradiation Examination capabilities.
- Dimensions and weight
- Pycnometry
- Laser Flash diffusivity
- Thermal expansion
- Dynamic Youngs Modulus
- Electrical resistivity
- Hardness testing (Vickers)
- Tensile properties
- Fatigue Crack Propagation
- Fracture toughness
- Bending test
- Digital Image Correlation
- Compressive strength
- Creep testing
- TEM
- Profilometry
- Gamma-spectroscopy
- Oxide Layer determination (eddy current)
- Puncturing, mass spectroscopy gas-analysis
- Optical microscopy
- Scanning Electron Microscope in cell
(+WDS+EDS+EBSD)
- X-ray Diffraction
- X-ray Computer Tomography
- Neutron Transmission Radiography
- Tritium inventory
- In-cell specimen manufacture
- In-cell capsule assembly
- Clad burst tests (under development; 2023)
On (non-)irradiated structural materials On (non-)irradiated fuels
10 Capabilities at NRG in summary*Fabricationof (oxide) fuels*Radiologicallabs forstudies on non-irradiatedfuels*Design of experimentsbydedicatedengineers: Nuclear, thermal-mechanical, thermohydraulic*Fabricationof experimentsin in-house mechanicalworkshop*Versatilein designingfordifferent fuel/ reactor concepts*Extensiveoptions forin-coreinstrumentationin HFR*Extensiveoptions forpost-irradiationexaminationson irradiatedfuelsandmaterials*Logisticsunits fororganizinginternationaltransports*Waste handling / disposalat national r epository
11 2030s : PALLAS reactor to replace HFR
12 Thank you for your attention
Disclaimer:
Goods labeled with an EU DuC (European Dual-use Codification) not equal to N are subject to European and national export authorization when exported from the EU and may be subject to national export authorization when exported to another EU country as well. Even without an EU DuC, or with EU DuC N, authorization may be required due to the final destination and purpose for which the goods are to be used. No rights may be derived from the specified EU DuC or absence of an EU DuC.
14 Design Process
- Design process has a number of steps
- Duration of process depends on the number of iterations and complexity of the irradiation, typically 12-18 months
- The number of iterations depend on clarity of scope Scope Neutronic Calculations Concept Design T&M Calculations Final Design Manufacturing
- Test matrix
- Selection of core position
- Targets
- Material heating
- DPA estimates
- Material selection
- Instrumentation
- Drawings
- Stress
- Temperatures
- Fixed for approval by Safety Comm
- In NRG Central Workshop
15 HFR in-core irradiation facilities For in-core experiments a TRIO, QUATTRO or REFA facility is placed 1, 3 or 4 experiments (sample holders) can be placed in one position Cooled (HFR primary coolant) or dry Effective height 600 mm Standard HFR Irradiation capsules
16 Fabrication & Assembly
17 Separate effect irradiation experiments 6 Samples UO2, (U,Pu)O2 Fuel Creep
- Measure height change in-situ through capacitor plates
- Stable, flat temperature
- Well-known power/fission density
- Axial load through actively pressurized bellow
(~88 bars ; 100MPa on Ø4mm discs)
- Load on samples is simultaneous, but displacements are individually Bellow/LVDT Proof-of-principal (no fuel) loaded with (Zr,Y)O2 and TZM(Mo)
Measuring thermal expansion Temperature range 500-1200°C
18 Online gas monitoring: sweep loop facility The Sweep loop Facility To measure the release of fission gases online by gamma spectrometry For accurate temperature control Grab sample for external verification measurement (gammaspec, gas mass spec)
CORE Experimental rig Helium Neon NaI detector Filtering station Gas volume (15 cm3)
Grab sample Aerosol filter Polyethylene Tungsten alloy Lead Germanium detector Energy Counts Counts Energy [MeV]
Glove Box CORE Experimental rig Helium Neon NaI detector Filtering station Gas volume (15 cm3)
Grab sample Aerosol filter Polyethylene Tungsten alloy Lead Germanium detector Energy Counts Counts Energy [MeV]
Glove Box
19 Molten Salt Irradiations SALIENT series Simulation of MSR environment:
Temperature gradient Salt flow Fuel burn-up (typically 1-4 %FIHMA)
Fluoride and/or chloride salts In-pile corrosion of structural materials Graphite Steel / Nickel-based alloys Fission product migration and deposition Image: Pavel Soucek, JRC Karlsruhe
-4
-2 0
2 4
Horizontal position (mm)
Zr-95 (salt-seeker)
Ru-103 Noble metal particles salt graphite
20 The SAGA facility for measurement of radiolytic gas production EU DuC = E001
21 NRG in support of AGR long term operation Accelerated aging of AGR graphite to provide data in support of LTO Graphite combined oxidation and neutron irradiation Graphite irradiation creep testing Extensive post-irradiation characterization program in NRG Hot Cell Laboratories
+40 years of operational years added to EDF Energy AGR reactor fleet AGR graphite sampling Analysis of results for safety case Irradiation and characterisation