Development of a counting-type neutron imaging detector for energy- resolved imaging at J-PARC/MLF
Joe Parker CROSS-Tokai BL22 Group
1J-PARC13 October 2016
Development of a counting-type neutron imaging detector for energy- - - PowerPoint PPT Presentation
Development of a counting-type neutron imaging detector for energy- resolved imaging at J-PARC/MLF Joe Parker CROSS-Tokai BL22 Group 1 J-PARC 13 October 2016 RADEN/BL22 and NID development members
Joe Parker CROSS-Tokai BL22 Group
1J-PARC13 October 2016
JAEA/J-PARC Center Takenao Shinohara Tetsuya Kai Kenichi Oikawa (BL10) Masahide Harada (BL10) Takeshi Nakatani Mariko Segawa Kosuke Hiroi Yuhua Su CROSS-Tokai Hirotoshi Hayashida Joe Parker (µNID Lead Developer) Yoshihiro Matsumoto Shuoyuan Zhang Nagoya University Yoshiaki Kiyanagi
instrument for pulsed-neutron imaging
radiography in Japan
user program from April 2015
World’s first instrument dedicated to energy-resolved neutron imaging using pulsed neutrons!
First images from RADEN (7 Nov 2014)
quantitative information on macroscopic distribution of microscopic quantities
energy range, accurate energy determination by time-of-flight
Energy-dependent neutron transmission
Energy
meV 1 keV
Wavelength
10 10-2 Resonance absorption Bragg-edge, Magnetic imaging
Moderator Bulk shield Shutter Optical Devices Experimental Space 1st Detector position 2nd Detector position
13m 5m
Large load sample stage Optical bench Medium sample stage
0m 8m 14m 27m 31m 18m 23m
Conventional radiography/pulsed-neutron imaging Large beam size (up to 30x30 cm2) High flux (2.6x107 n/s/cm2 @ <0.5eV) Variable L/D (up to 7500) Wide bandwidth (~9, / < 0.2%) Large experimental area
Properties of RADEN
line components, sample stages, and detectors using IROHA2 (automated measurements)
capacity (24TB SSD primary, 100TB secondary)
Gb/s) for fast data transfer
GPGPUs) for data analysis
Camera type Counting type
Andor iKon-L
system for CT
Neutron Color I.I.
(200 µm)
30k, 100k fps)
µNID
t=0.6µs, < 1 Mcps
nGEM
LiTA12
0.1 1 10 100 0.01 0.1 1 10
Count rate (Mcps) Spatial resolution (mm) µNID nGEM LiTA12
9.0 cm 32.8 cm
400 µm
X (strips)
10 20 30 40 50 60
Time-above-threshold (clocks)
5 10 15 20 25 30
Energy Deposition
TOT for proton-triton track Proton Triton Neutron
Digital encoder with time-over-threshold (TOT)
Threshold
µPIC
Discriminator
Time-above-threshold (∝ energy dep.)
neutron proton triton
3He
pattern
(TOT)
encoder
→ Good spatial resolution,
strong background rejection, high data rates possible
Neutron detection via 3He
Track length ~8 mm in gas
E µPIC
Encoders DAQ PC
SiTCP
Encoders µPIC
Control box
DAQ controller system monitor DC power External timing signals Vessel pressure Ethernet GbE × 4
±2.5V, +3.3V
Ambient temperature Network DAQ control Monitoring Power
Add 10GbE hub to reduce cables
Sensor power
Image data taken at NOBORU in Feb. 2011
Distance from interaction point (mm)
4 8
Time-over-threshold (ns)
50 100 150 200 250 6 2
Template for fit
Measured TOT distribution
Proton Triton
using TOT information
analysis
100 200 300 400 500
Counts/hr/3.75 clocks
1 2 3 4 5 6 7
137Cs
No source ‘Energy’ cut Neutrons γ’s
Total TOT (clocks)
µNID performance characteristics Area 10 x 10 cm2 Spatial res. 0.3 mm Time res. 0.6 µs TOF/TOF < 0.07% @18m
< 10-12 Efficiency Up to 26% Count rate 0.6 Mcps
pressing
by 100BASE-T Ethernet transfer
not yet tested)
22 cm
FPGA
CMOS ASICS
GbE
DDR3 memory
Originally developed by Kyoto U. and KEK (Open-it)
Previous gas New gas Mixture Ar-C2H6-3He (67:7:30 @ 2atm) CF4-iC4H10-3He (45:5:50 @ 2atm) Drift velocity 23 µm/ns 58 µm/ns Diffusion 275 µm/cm1/2 80 µm/cm1/2 Efficiency @25.3meV 18% 26% Proton-triton track length 8 mm 5 mm
Gas characteristics simulated with MAGBOLTZ, GEANT4
using B4C slits
hardware
detector
Detector B4C slits
N e u t r
b e a m
with GbE
encoder
increased by more than factor of 6
than 3 Mcps
1 2 3 4 5 500 1000 1500 2000 2500
Count rate (Mcps) Slit area (mm2)
Neutron rates vs slit area
GbE 100Mbps
mixture
Mcps
increase over Ar-based gas mixture
2 4 6 8 10 1000 2000 3000 4000
Count rate (Mcps) Slit area (mm2)
Neutron rates vs slit area
Ar-C2H6 CF4-iC4H10
50 60 70
(200µm line width)
Ethane mixture
8 cm
0.2 mm 0.3 mm 0.4 mm 0.5 mm 0.6 mm Bin size: 40 x 40 µm2
0.55 0.6 0.65 0.7 0.75 0.8 0.85 0.9 0.95
Transmission Distance from top (mm)
above 100~300 kcps
company to improve speed and ease-of-use of analysis software
TOF (ms)
5 10 15 20 25 30 35 40
Efficiency
0.2 0.4 0.6 0.8 1
Neutron reconstruction efficiency
5.6 Mcps 2.5 Mcps <0.4 Mcps Efficiency of analysis determined by comparing numbers of raw hits and reconstructed neutron events
to x,y strips
simultaneous events
(structures down to 10µm)
pitches
testing at RADEN 280 µm 215 µm
y1 y2 x2 x1 u2 u1
280µm pitch (192×192 strips) 215µm pitch (64×64 strips)
Time (ms)
5 10 15 20 25 30 35 40
s µ Counts/pulse/25
0.02 0.04 0.06 0.08 0.1 0.12
Neutron TOF (MEMS uPIC test)
MEMS µPIC test board Neutron TOF spectrum measured on 215µm section
section (gain too low)
stability, imaging capability
(t=1µm)
memory
early next year
~5 mm Al drift cathode (t=1mm) 3-axis µPIC readout
Expected performance Efficiency@25.3meV 3~5% Time resolution 10 ns Spatial resolution 200~400 µm Peak count rate 20~30 Mcps
10B coating (t=1µm)
0.1 1 10 100 0.01 0.1 1 10
Count rate (Mcps) Spatial resolution (mm) µNID GEM LiTA12
µNID
(GbE and
Boron µNID µNID (GbE/memory and reduced pitch)
upgrades, optimization of gas mixture
characteristics
spatial resolution has begun
software
resolution thanks to smaller event size