Utilization of Thai Research Reactor (TRR-1/M1)
S. Chue-inta, N. Klaysuban, C. Tippayakul and A. Konduangkaeo
Descriptions of TRR-1/M1
TRIGA Mark III First Critical July 1977 Max. Power: 2 MW Nominal Operation: 1.2 MW Flux 3x1013 cm-2.sec-1
Coolant water
Descriptions of TRR-1/M1
Fuel Elements 20% TRIGA rod
Control Rods
4 FFCR 1 AFCR B4C
Descriptions of TRR-1/M1
Current Core Configuration: No. 18
107 Fuel elements (4 Fuel Follower Control Rods)
9 In-core irradiation positions (CT, C8, C12, F3, F12, F22, F29, G5 and G33)
CT
A1
9866
C10
10096
E19
8624
G28
TR
C4
8621
F26
8563
G3
9224
B5
10019
D14
8575
F23
9223
B3
10043
D6
8572
F9
9860
B610027
E6
8615
F24
8610
F21
10018
D5
8570
F8
9228TC
B4
10048
D15
10044
E188574
G27
9862
C5
10095
E8
8583
G11
9868
C11
10025
E20
8638
G29
9226
C3
8568
F6
8573
G9IIT
C12
SH2
10247
D16
8559
F25
9221
C2
9227
TC
E7
9219
B1
IIT
C8
SH1
10246
D13
IIT
F22
9863
C6
9861
D7
8566
F10
9220
C1
9865
C9
9615
E21
ND
G30
10020
D3
9614
E5
ND
G8
9864
C7
10049
D12
9613
E17
8637
G26
10023
D8
9612
E9
8605
G12
10046
D4
10026
E22
8564
G6
9859
D2
10022
E4
9222
B2
10041
D11
10093
E1610024
D9
10050
E108604
F11
REG
10245
D10
10092
E158609
F20
10088
E11IIT
F12
SAFE
10097
D1
10045
E238599
F27
10021
E38612
F5
10091
E148639
F19
8594
G24
10089
E128569
F13
8590
G14
10094
E248636
F28IIT
F29
9225
E2
8565
F4IIT
F3
10042
E1IIT
G33
8618
G10
IIT
G5
10090
E138578
F18
8634
G23
8596
F14
8623
G15
8600
F17
8602
F15
8597
G16
8606
F30
8643
G34
8620
F2
8649
G48595
F1
8645
G35
8630
F16
8561
G21
8562
G17
8585
G36
8627
G2
ND
G20
8617
G18
S
G22
S-3
S-1
S-2
8558
F7
8619
G32
9867
D18
10047
D17
Operating Organization
Thailand Institute of Nuclear Technology (TINT)
Nuclear Technology and Reactor Operation Div.
Reactor Management Section(11 operators)
TINT Policy : Equivalent Social and
Beneficial Utilization of TRR-1/M1
Irradiation Services
Educa
tion a
nd
Tra
inin
g
Experim
ents a
nd
Rese
arch
es
Public Tours
Operation Schedule
Operating power: 1200 kW
Weekly operation schedule: 46 hours / week
Monday : Experiments
Tuesday-Friday: Operation
Annual operation schedule: 10.5 months
Annual maintenance: 1.5 months (Feb-Mar)
Ten In-core facilities
CT 3x1013ncm-2sec-1
C-ring 2x1013ncm-2sec-1
F-ring 1x1013ncm-2sec-1
G-ring 9x1012ncm-2sec-1
Irradiation Service
Isotope Production
Mainly 131I, 5Ci per week ~ half of country’s demand
153Sm, 32P and 177Lu on occasional basis
Aluminium container
TeO2
Irradiated by Reactor
Processed in a hot cell
80gmTeO2(131I)
CT 6wks 2days, 5mg Sm2O3 (153Sm)
C8 6wks
C12 7wks
F3 8wks 2days, 1mg Lu2O3 (177Lu)
F29 9wks
G5 7wks 1wk, 5gm NH4HPO4 (32P)
G33 7wks
Isotope Production
Products and Patients
131I Solution 18Ci 1,150 cases
131I Diagnostic capsule, 90mCi, 93 cases
131I Therapeutic capsule, 126Ci, 3,338 cases
131I MIBG diagnostic dose, 133mCi, 138 cases
131I MIBG therapeutic dose, 560mCi, 4 cases
131I Hippuran, 144mCi, 144 cases
153SmEDTMP, 2.2Ci, 34 cases
32 P 18mCi
Products 147Ci Values 708,982 $ 4,901 patients
99mTc Products
Total import 26Ci (generator 500mCi/week)
Products from Labs: MAA, MAG3, MDP, DISIDA, DMSA, DTPA, Phytate, Stannous, EC, MIBI, Hynic-TOC
Products 147 units Values 69,333 $
For 20,252 Patients
Incomes from isotope products
TRR-1/M1 originated = 354,491 US$
Generator originated = 423,824 US$
Isotope production income (US$)
354491, 46%
423824, 54%
reactor imported
Ten Out-core Irradiation Facilities
Column 1x109ncm-2sec-1
Beams 1x106ncm-2sec-1
Tubes 1x1011ncm-2sec-1
LS 2x1011ncm-2sec-1
WT 8x1011ncm-2sec-1
8. Activity < 2nCi/g 7. Satisfied
6. Radiation monitoring
9. Return to customer
1. Topaz
2.Aluminum container
3. wet tube
4. Irradiation 10-20 wks
5. Decay 3-36 wks
Gems Irradiation capacity: 150
kg/year
Cd covered, 1011 ncm-2sec-1
Beryl
[gamma > 200 Mrad]
Diamonds [neutron & heat]
London Blue
[neutron & heat]
Quartz
[gamma]
Sky Blue
[EB & heat]
Super Blue
[neutron, EB & heat] Swiss Blue
[neutron, EB & heat]
บุษราคัม [neutron]
Tourmaline
[gamma]
White Topaz Rough White Topaz Faceted Topaz
[neutron]
Topaz Faceted
[EB no heat]
Topaz
[gamma]
Topaz
[neutron & EB]
Topaz Performs-Sky Blue
[EB & heat]
Topaz Performs
[EB no heat]
Topaz
[neutron & no heat]
Gems In-core Irradiation
In-core irradiation facilities (F12, F22, G5 and G33)
Calculation core reactivity insertion (MVP Code)
Irradiation tests with 300gm gems for 12-72 hrs
Gems Irradiation Products
Gems irradiation(kgs)
neutron, 27.157, 44%
gamma, 34.707, 56%
Reactor 28,826 US$
Gamma 6,653 US$
Total 35,479 US$
Irradiation Service
3. Neutron Activation Analysis
Alloys, minerals, geological, (teeth)
Foods, biological, air pollution
Incomes 3,713$
INAA
Type Elements irradiation decay
short Al, K, Cl, Cu, Mg, Ti, V Min 5m
short Mn, Na 3hr
Med As, Br, K, La, Na, Sb, Sm Min-day 3days
Long Ce, Co, Cr, Fe, Sb, Sc, Se, Th, Zn 2wks
Number of NAA samples
560
112 133
20 411
77 55
0
100
200
300
400
500
600
700
G22 A1 CA2 CA3 A4 TA LS WTFacility
INAA income 3,713$
Rough Estimations
Incomes (IP+GEMS+NAA)=452,650$
Operation (Fuel + budget)=2,121,212$
Incomes/Operation costs = 21.33 %
Scattering
PGNAA
Radiography
Research
Large sample INAA
DEVELOPMENT OF A PROFILE DATA ACQUISITION SYSTEM FOR NEUTRON
COMPUTED TOMOGRAPHY FOR THE THAI RESEARCH REACTOR TRR-1/M1
1, S.Chueinta2Pattarasumunt , A. 2, S.Srisatit*1K.Sukrod 1Department of Nuclear Technology, Faculty of Engineering, Chulalongkorn University, Bangkok 10330, Thailand
2Thailand Institute of Nuclear Technology, Bangkok 10900, Thailand
ABSTRACT The neutron computed tomography using Thai research reactor TRR-1/M1 was developed in this research. The system was divided into two parts. The first one is the rotate-translate
system and the second is the data acquisition program. The collected profiles data was 1 mm/step of translation and 7.2 degree/step angle of rotation .The neutron beam from Thai research
reactor TRR-1/M1 which is operated at 1200 kilowatts. The neutron CT images were found to be satisfactory.
EXPERIMENTAL & RESULTS Neutron Computed Tomography System.
INTRODUCTION The objective of this research is to develop the neutron computed tomography system for TRR-1/M1. The neutron computed tomography is one of the widely used Non-Destructive
Testing (NDT) methods. The principle of this technique is to measure the intensity of neutrons attenuated by different materials in the object. Two dimensional images of the object are
derived from the measurement. By rotating the object in small increment, several 2D images of the object are taken at different angles and they are finally combined to construct a cross
sectional view by computed tomography methodology.
Average PSL readout from NIP VS exposure time at different disrances form the neutron beam exit
Equipment installation
Neutron image processing
CONCLUSIONS Through this study of neutron computed tomography using thermal neutron beam from TRR-1/1M, the obtained image could be identified the difference kind of materials such as PE,
Steel and Brass by the CT-number.
CT image was reconstructed from the projection data, because of the neutron scattering reduces the contrast of CT image. So, the scattering neutron correction should be considered.
Detail of objects
1.PVC cover diameter 12 cm.
thickness 0.8 cm
2.Steel diameter 2 cm
3.PE diameter 2 cm
4.Brass diameter 2 cm Detail of scan
1.Profiles : 26
2.Ray sums : 140
3.Time : 3 Sec.
Data Acquisition and
Data Processing
Table control Projection Data CT Image
PE Brass
Steel
Neutron
y = 45.528x - 8.4972R
2 = 0.9931
0
500
1000
1500
2000
2500
3000
3500
0 10 20 30 40 50 60 70Expos ure time in s econds
Aver
age
PSL/
mm
2SENSITIVITY OF NEUTRON IMAGING PLATE
TO NEUTRONS AND GAMMA-RAYS R. Fungklin1, N. Chankow1 , S. ChongKum2
1Department of Nuclear Technology, Faculty of Engineering, Chulalongkorn University, Bangkok 10330, Thailand
2Thailand Institute of Nuclear Technology, Bangkok 10900, Thailand
ABSTRACT The objective of this research is to investigate the sensitivity of a Fuji BAS-ND 2040 neutron imaging plate to neutrons and gamma-rays for non-destructive testing of
some ancient specimens. For sensitivity to neutrons, the imaging plate was exposed to neutrons from a neutron beam of the Thai Research Reactor TRR1/M1 operating at
1.2 MW having a neutron flux of 1.26 x 106 n/cm2-s and a cadmium ratio of approximately 250. It was found that the photostimulated luminescence (PSL) output increased
linearly with increasing of the exposure time and the sensitivity to neutrons was approximately 1 PSL per 280 neutrons. For sensitivity to gamma-rays, it was exposed to
661.6 keV gamma-rays from 10 mCi Cs-137 source. The sensitivity was found to be approximately 1 PSL per 4.8 x 103 gamma-ray photons. The sensitivity of the imaging
plate to neutrons was, therefore, about 17 times faster than to the gamma-rays which was very high comparing to the conventional film technique. Finally, the imaging plate
was employed to record neutron and x-ray radiographic images of some ancient specimens. The image quality was comparable to those obtained from the conventional film
technique with significantly reduction of the exposure time.
INTRODUCTION Neutron Radiography is one of non-destructive testing (NDT) methods. Currently imaging plates have been used in place of or along with traditional X-ray or photographic
films. X-ray film imaging usually takes a long time to process before the image is obtained. The imaging plates, on the other hand, are more sensitive to radiation and
therefore will take much shorter time to process. In this study we used an imaging plate reader which uses laser beams to interact with imaging plates. The output came out
as computer-readable data, which is convenient to be analyzed. In this study we investigated the sensitivity of the imaging plates to neutron and gamma radiation in order to
use the plates in studying some ancient specimens in the future.
1. Linearity and Sensitivity test
CONCLUSIONS (left : Ancient specimen; middle : NR using NIP; right : x-ray radiography using x-ray IP)
Neutron Imaging Plate is more sensitive to neutron radiation than to gamma rays or x-rays.
Neutron Imaging Plate ’s speed is about 40 times faster than the conventional film technique.
This can be applied to neutron radiography using Neutron Imaging Plate for inspection ancient objects.
EXPERIMENTAL & RESULTS
Average PSL readout from NIP VS exposure time
2. Neutron and x-ray images of some specimens
For slow neutrons with Cd ratio of ~ 250 :
NIP requires ~ 280 n/cm2 to obtain 1 PSL/mm2 read out i.e. having a
sensitivity of ~ 3.6 x 10-3 PSL/mm2 per neutron
For gamma-rays from Cs-137 (661.6 keV) :
NIP requires ~4.8 x 103 /cm2 to obtain 1 PSL/mm2 read out i.e.
having a sensitivity of ~ 2.08 x 10-4 PSL/mm2 per gamma-ray photon
Gamma ray (661.6 keV)
y = 2.4413x - 6.3057
R2 = 0.9733
0
20
40
60
80
100
120
140
160
180
0 10 20 30 40 50 60 70
Exposure time in minutes
Ave
rage
PSL
/mm
2
Education and Training
Cooperation Criticality Thermal Hydraulics Neutronics Operation
Maintenance
Safety culture
Radiation protection
Inspection
Quality Assurant
Utilization
Number of visitors in 2009
579 586
177
51
0
100
200
300
400
500
600
700
students public trainee other
Public Tours
Conclusions
TINT has equivalent policy towards social and beneficial utilization of TRR-1/M1
Estimated incomes/operation cost 21.33% Will try to improve….KM, training, Cooperation, etc.
Thank you for kind attention