On the possibility to investigate irradiated fuel pins non-destructively by digital neutron radiography with a neutron-sensitive microchannel plate detector with Timepix readout

Tremsin, Anton S.; Craft, Aaron E.; Papaioannou, Glen C.; Smolinski, Andrew T.; Boulton, Nicholas; Ruddell, M.A.; Littell, B.J.; Riley, K.

doi:10.1016/j.nima.2019.02.012

Cited by 12 publications

(7 citation statements)

References 33 publications

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“…The elevator shaft lowers material directly in front of the beam line Quantum Beam Sci. 2021, 5, 8 2 of 14 to enable neutron radiography using an indirect method (e.g., transfer method) to produce neutron radiographs [2][3][4], though some direct digital methods are possible as well [5,6].…”

Section: Introductionmentioning

confidence: 99%

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Giegel

Craft

Papaioannou

et al. 2021

QuBS

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The Neutron Radiography Reactor at Idaho National Laboratory (INL) has two beamlines extending radially outward from the east and north faces of the reactor core. The control rod withdrawal procedure has recently been altered, potentially changing power distribution of the reactor and thus the properties of the neutron beams, calling for characterization of the neutron beams. The characterization of the East Radiography Station involved experiments used to measure the following characteristics: Neutron flux, neutron beam uniformity, cadmium ratio, image quality, and the neutron energy spectrum. The ERS is a Category-I neutron radiography facility signifying it has the highest possible rank a radiography station can achieve. The thermal equivalent neutron flux was measured using gold foil activation and determined to be 9.61 × 106 ± 2.47 × 105 n/cm2-s with a relatively uniform profile across the image plane. The cadmium ratio measurement was performed using bare and cadmium-covered gold foils and measured to be 2.05 ± 2.9%, indicating large epithermal and fast neutron content in the beam. The neutron energy spectrum was measured using foil activation coupled with unfolding algorithms provided by the software package Unfolding with MAXED and GRAVEL (UMG). The Monte-Carlo N-Particle (MCNP6) transport code was used to assist with the unfolding process. UMG, MCNP6, and measured foil activities were used to determine a neutron energy spectrum which was implemented into the MCNP6 model of the east neutron beam to contribute to future studies.

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Section: Introductionmentioning

confidence: 99%

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Giegel

Craft

Papaioannou

et al. 2021

QuBS

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“…Hasil pengukuran menunjukkan bahwa tidak terjadi perubahan dimensi, sehingga integritas PEB U3Si2/Al densitas 4,8 gU/cm 3 tetap terjaga setelah mengalami proses iradiasi di teras RSG-GAS. Indikasi lain yang menunjukkan solidnya integritas PEB U3Si2/Al adalah diperolehnya nilai jarak aman meat pada tiap-tiap sisi PEB masih berada pada interval nilai jarak yang ditetapkan [12]. Berdasarkan data dimensi PEB yang telah dianalisa, selanjutnya dilakukan pemetaan untuk menentukan titiktitik pencuplikan sampel.…”

Section: Pendahuluanunclassified

UJI TAK MERUSAK PELAT ELEMEN BAKAR U3SI2/Al DENSITAS URANIUM 4,8 gU/cm3 MENGGUNAKAN RADIOGRAFI SINAR-X DIGITAL

Artika

Sigit

Rahmatullah

et al. 2020

urania

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Telah dilakukan uji tak merusak PEB U3Si2/Al densitas uranium 4,8 gU/cm3 pasca iradiasi dengan burn up 20, 40,dan 60 %. Pengujian meliputi pengamatan secara visual, analisis citra radiograf dan pengukuran dimensi menggunakan radiografi sinar-X digital. Uji tak merusak bertujuan untuk mengetahui unjuk kerja, integritas dan kehandalan PEB selama diiradiasi di RSG-GAS. Kehandalan dan kesalamatan bahan bakar selama di reaktor diindikasikan dengan tidak adanya anomali pada hasil pengujian pasca iradiasi. Elemen bakar uji (EBU) terdiridari tiga PEB U3Si2/Al densitas 4,8 gU/cm3pasca iradiasi ditransfer dari RSG-GAS ke hotcell 101 IRM melalui kanal hubung Instalasi Penyimpanan Sementara Bahan Bakar Bekas (IPSB3). Selanjutnya EBU ditransfer ke hot cell 103 untuk dilakukan pengujian tak merusak menggunakan radiografi sinar-X digital dengan tujuh kali penembakan sehingga diperoleh hasil citra radiografi dengan resolusi yang baik. Citra radiografi yang dihasilkan dievaluasi lebih lanjut untuk mendapatkan data cacat dan dimensi PEB U3Si2/Al densitas 4,8 gU/cm3pasca iradiasi antara lain lebar meat, lebar PEB, jarak meat-cladding, jarak batas meat-cladding sisi kanan kiri pada sisi jauh (SJ) dan sisi dekat (SD). Hasil analisis menggunakan radiografi sinar-X menunjukkan adanya bercak putih pada cladding bagian tengah PEB U3Si2/Al densitas 4,8 gU/cm3dengan burn up 20%. Penyebab keberadaan bercak putih tersebut harus dibuktikan dengan menggunakan metode uji merusak salah satunya yaitu analisis metalografi. Sementara itu, PEB U3Si2/Al densitas 4,8 gU/cm3 dengan burn up 40 dan 60 % tidak ditemukan adanya indikasi cacat permukaan dan cacat lainnya. Data hasil pengukuran dimensi menunjukkan tidak terdapat kerusakan dan perubahan dimensi signifikan yang menunjukkan bahwa integritas bahan bakar tetap terjaga setelah PEB U3Si2/Al densitas 4,8 gU/cm3 diiradiasi di teras RSG-GAS.Kata kunci: PEB, U3Si2/Al, 4,8 gU/cm3, uji tak merusak, radiografi sinar-X.

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“…The radiation emitted from irradiated nuclear fuels typically precludes the use of direct imaging techniques, though some direct digital techniques have successfully been used to examine irradiated nuclear fuels directly. 8,9 While indirect neutron radiography has traditionally been used for examining irradiated nuclear fuels, digital neutron imaging systems employed by the worldwide neutron imaging community have significantly expanded the application space of neutron imaging and the scientific pedigree of the entire neutron imaging field. The most common digital neutron imaging systems use a digital camera optically coupled to a neutron-sensitive, promptly decaying scintillator screen to record an image.…”

Section: Introductionmentioning

confidence: 99%

Performance Testing of Dysprosium-Based Scintillation Screens and Demonstration of Digital Transfer Method Neutron Radiography of Highly Radioactive Samples

et al. 2021

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Scintillator screens consisting of a dysprosium neutron converter and various scintillator materials were tested in the Heinz Maier-Leibnitz Zentrum Forschungsreaktor München II (FRM II) ANTARES cold neutron beam with the goal of finding a suitable screen for digital transfer method neutron radiography. This work explores the cold neutron response of 16 scintillator screens, 7 of which were previously tested with thermal neutrons. Light yield, signal-to-noise ratio (SNR), and spatial resolution were measured to compare the scintillator screens and determine which were best suited for digital transfer method neutron radiography. Screens with a zinc sulfide (ZnS:Cu) scintillator were most suitable for digital transfer method radiography based on light output, spatial resolution, SNR, and gamma-ray insensitivity. Spatial resolutions between 65 and 220 μm were measured. The top-performing screens were then used to demonstrate the feasibility of a new digital transfer method neutron radiography to image highly radioactive (8.84 Sv/h at ≈1 cm) nuclear fuel at Idaho National Laboratory's Neutron Radiography reactor (NRAD). These results suggest that digital transfer method neutron radiography can be used to indirectly image highly radioactive objects and/or use neutron beams with a large gamma-ray content on a timescale of ~10 min/image (~144 images/day), much faster than the >10 h required using the current transfer method with film (limited to ~14 radiographs/day at NRAD).

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On the possibility to investigate irradiated fuel pins non-destructively by digital neutron radiography with a neutron-sensitive microchannel plate detector with Timepix readout

Cited by 12 publications

References 33 publications

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

UJI TAK MERUSAK PELAT ELEMEN BAKAR U3SI2/Al DENSITAS URANIUM 4,8 gU/cm3 MENGGUNAKAN RADIOGRAFI SINAR-X DIGITAL

Performance Testing of Dysprosium-Based Scintillation Screens and Demonstration of Digital Transfer Method Neutron Radiography of Highly Radioactive Samples

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