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IAEA-TM-38728 (2010)
1
PRESENT STATUS AND FUTURE POTENTIAL FOR COMMERCIAL
APPLICATION OF JAEA RESEARCH REACTORS
A.M. ISHIHARA, H. KAWAMURA
Japan Atomic Energy Agency, Oarai Research & Development Center,
Oarai-machi, Ibaraki-ken,
Japan
1. INTRODUCTION
In the check and review discussion of the Japan Materials Testing Reactor (JMTR)
reactivation, the Japan Atomic Energy Agency (JAEA) has surveyed utilization fields for
Materials Test Reactors among other research reactors. From the survey, it has been
concluded that the utilization of research reactors can be categorized into four major
application targets:
(i) Lifetime extension of LWRs, e.g., aging management of LWRs, development of next
generation LWRs;
(ii) Progress of science and technologies, e.g., next generation reactors such as the high
temperature gas cooled reactor (HTGR), fusion reactor, basic research on nuclear
energy, neutron beam utilization;
(iii) Expansion of industrial use, e.g., doping of silicon semiconductor, radioisotope (RI)
production, production of 99m
Tc for the medical diagnosis medicine;
(iv) Education and training of nuclear scientists and engineers.
These are thought to be common in the world.
JAEA has developed a fleet of four different types of research reactors, Japan Research
Reactor-3 (JRR-3), JRR-4, Nuclear Safety Research Reactor (NSRR) and JMTR designed
specifically for intended purposes. JRR-3, with a thermal power of 20 MW, is applied to
beam experiments, irradiation tests, RI production, activation analysis and silicon
semiconductor doping. JRR-4, with a thermal power of 3.5 MW, is designed for medical
irradiation such as boron neutron capture therapy (BNCT), RI production, and education and
training. NSRR, with a maximum power of 23 GW at pulse operation, is utilized for nuclear
fuel safety research. Finally, JMTR, with a thermal power of 50 MW, is devoted to irradiation
tests for nuclear fuels and materials, and RI production. The role of research reactors in JAEA
is summarized in Table 1.
JMTR and its reactor facilities are now under refurbishment. The refurbished JMTR is
expected to gain an appreciable income from commercial users. A few successful examples
on JMTR utilization are shown in this paper from a viewpoint of commercial applications.
Since the strengthened regional and international cooperation is a key issue to enhance the
steady commercial applications such as RI production, the importance of regional and
international frameworks is also mentioned.
IAEA-TM-38728 (2010)
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TABLE 1. ROLE RESEARCH REACTORS IN JAEA
2. RESEARCH REACTORS IN JAEA
2.1. Outline of research reactors
JAEA has developed four different research reactors: JRR-3, JRR-4, NSRR and JMTR.
JRR-3 is a light water moderated and cooled pool type reactor with 20 MW of thermal power.
Its first criticality was achieved in 1962, and remodeling was carried out in 1985. In 1990 the
remodeled JRR-3 was re-started for utilization. The thermal flux is at maximum 3×1018
m-2
s-1
,
and the operation mode is 26 days per cycle with 6 to 7 cycles per year. Specifications and a
view of the reactor are shown in FIG. 1.
JRR-4 is a light water moderated and cooled swimming pool type reactor with 3.5 MW of
thermal power. The first criticality was achieved in 1965, and radiation shielding experiments
for the nuclear ship Mutsu were started in 1966, followed by training for reactor engineers
beginning in 1969. The thermal flux is 7×1017
m-2
s-1
at maximum, and daily operation with
6 hours per day is carried out. Specifications and a reactor view are shown in Figure 2.
NSRR is a pulse reactor with the maximum power of 23 GW at pulse operation and 300 kW
at steady state operation. The first criticality was achieved in 1975, and modification of
experimental facilities and the reactor control system was carried out in 1989. Spent fuel
experiments started in 1989, and spent mixed oxide (MOX) fuel experiments started in 1996.
In 2006, high burnup fuel and MOX fuel experiments as well as high pressure water capsule
experiments were started. Specifications and a reactor view are shown in Figure 3.
JMTR is a light water cooled tank type reactor with 50 MW of thermal power. The first
criticality was achieved in 1968, and user operation was carried out from 1970 to 2006. Now
refurbishment works are being carried out until 2010. The thermal and fast fluxes are almost
the same at 4×1018
m-2
s-1
at maximum, and the operation mode is 30 days per cycle with
maximum 6 cycles per year. Specifications and areactor view are shown in Figure 4.
Reactor
Items
JMTR
(50MW)
JRR-3
(20MW)
JRR-4
(3.5MW)
NSRR
(23GW*)
Lifetime extension of
LWRs ○ ○
Progress of science and
technology ○ ○
Expansion of industry use ○ ○ ○
Education and training ○ ○* : Pulse operation
IAEA-TM-38728 (2010)
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Fig. 1. Specifications and reactor view of JRR-3.
Fig. 2. Specifications and reactor view of JRR-4.
Specifications of JRR-3
PurposeBeam experiment, Fuel/material irradiation, RI production, Activation analysis, etc.
TypeLight water moderated and cooled pool type
Fuel LEU/Si/Al dispersion fuel
Thermal power 20 MW (max.)
Thermal flux 3 x 1018 n/m2・s (max.)
CoreCylinder shape(60cm dia. 75cm in height)
Operation mode 26 days/cy, 6-7 cy/year
1962 First criticality
1985 Remodeling works start to achieve high performance
1986 Take out reactor core
1990 Criticality & Utilization start
1993 Cumulative output reached at 10,000MWD
1998 High density fuel loading(LEU/Si/Al dispersion fuel)
2006 Cumulative output reached at 50,000MWD
View of Reactor building
Cooling towerReactor building
Reactor core
Top shield
Reactor pool
Control rod drive
mechanism
Core
Heavy water
tank
CNS low temperature channel tube
Irradiation hole
Beam tube
Primary cooling
pipe
1965First criticality
1966 Thermal power at 2500 kW,
Radiation shielding experiment start for
nuclear ship “MUTU”
1969 Training start for reactor engineers
1974 Outside utilization start
1999 Thermal power at 3500kW
1996 LEU fuel,
Update reactor facilities & utilization facilities
1998 Outside utilization restart
Specification of JRR-4
Purpose
Activation analysis, education & training, RI production, Medical irradiation, radiation shielding experiment
TypeLight water moderated and cooled swimming pool type
Fuel LEU/Si/Al dispersion fuel
Thermal power 3,500 kW s (max.)
Thermal flux 7 x 1017 n/m2・s (max.)
CoreRectangular
(34.4cm×40.5cm, 60cm in height)
Operation mode Daily operation (6h/day)
Medical
irradiation room
Core
Irradiation pipe
Reactor pool
Medical irradiation
Facility (BNCT)
Prompt g analysis equipment
Bird‘s eye view of reactor
Cd shutter
Heavywatertank
Core tank
Core
No.1pool
Collimator
Medical irradiation room
Medical irradiation Facility
(BNCT)
IAEA-TM-38728 (2010)
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Fig. 3. Specifications and reactor view of NSRR.
Fig. 4. Specifications and reactor view of JMTR.
2.2. Utilization of research reactors
JRR-3 is applied to beam experiments, irradiation tests, RI production, activation analysis and
silicon doping. For beam utilization, JAEA users constitute around 39% of users, and others
external users are around 61%. Within external users, around 82% are university users, and
around 15% are private users (industry users). For irradiation utilization, the major user is
1975 First criticality/ Fresh fuel experiments starts1980 Succeed in visible capsule experiments1989 Modification of experimental facilities and
reactor control systemSpent fuel experiments starts
1996 Spent MOX fuel experiments starts2004 3,000 pulse operations achieved2006 High burnup fuel and MOX fuel experiments
startsHigh pressure water capsule experimentsstarts
実験実験
Schematic illustration of NSRR
Experimental
capsule
Reactor pool
Control rod
driving mechanism
Reactor core
Offset loading tube
Cutaway view of NSRR reactor building
Reactor buildingReactor core
Specification of NSRR
TypeType of Uranium-Zirconium-hydride moderatingheterogeneous
Fuel Uranium-Zirconium-hydride
Maximum Reactor power
300kW(Steady state operation)23,000MW(Pulse operation)
Maximum neutron flux
1.9×1016n/m2・s
(Steady state operation)
Core Annular core
Operation mode
Steady state operation
Natural pulse operation
Shaped pulse operation
Combined pulse operation
Reactor
building
Canal (Waterway)
The JMTR was constructed to
perform irradiation tests for LWR
fuels, materials and to produce radio
isotopes in order to establish
domestic technology for developing
nuclear power plants.
Purpose
• One of the high neutron flux Materials Testing Reactor in the world
• Large irradiation area in the core region for various irradiation tests• Flexible reactor core configuration allows various irradiation facilities installation to the reactor core
• The reactor building is connected to the hot laboratory by a canal for PIE tests for fuels and materials.
Major feature
Reactor and Irradiation Facilities
Ancillary
facilities room
Hot Laboratory
Construction began : 1965 Apr.
First Criticality : 1968 Mar.
For user operation : 1970 Sep.
to 2006 Aug.
• Thermal power : 50 MW
• Fast neutron flux : 4 x 1018 (n/m2/s)
(Maximum)
• Thermal neutron : 4 x 1018 (n/m2/s)
flux (Maximum)
Conclete Cell : 8Microscope Lead Cell : 4Lead Cell : 7Steel Cell : 5X-ray Microanalyzer : 1
IAEA-TM-38728 (2010)
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universities; university users are around 50%, private users are around 34%, and JAEA users
are around 14%. Utilization of JRR-3 is summarized in FIG.5.
JRR-4 is designed for medical irradiation such as BNCT, RI production and education and
training. For BNCT, utilization was carried out 25 times in 2007. For irradiation utilization,
the major user is also universities; university users are around 50%, private users are around
36%, and JAEA users are around 10%. Comparatively, for experimental utilization such as
radiation shielding experiments, the major users are JAEA personnel; JAEA users are around
74%, university users are around 17%, private users are around 9%. Utilization of JRR-4 is
summarized in Figure 6.
JMTR is devoted to irradiation tests for nuclear fuels and materials, and RI production. The
major irradiation field is the progress of science and technologies (e.g., fundamental research,
fusion reactors and high temperature gas cooled reactors) which covers 58%, followed by the
light water reactor (LWR) related field with about 21% and RI production with about 15%.
From the viewpoint of users, JAEA users comprise about 50%, university users about 30%,
RI production users about 15%. Utilization of JMTR is summarized in Figure 7.
Fig. 5. Utilization of JRR-3.
Irradiation Utilization
Irradiations
JAEA79
(14%)17 rooms
282(50%)
32 universities
8 (2%)
193(34%)
13
companies 562
3 facilities
Beam utilization
Users
( man-day)
JAEA
University7,533(39%)
9,490(49%)
475(3%)
23 rooms
86 universities
19,199
Private uses
43 facilities
1,701(9%) <Perform an ce in 2 0 0 8 >
Private
uses
Public uses
Public uses
298
256
193
0 150
metal, inorganic compound
soil
rock
600300
animal, plant, fish 608
2631air dust, filter
450 2750
The number of NAA samples in FY 2008
Change in number of users for Beam utilization
19274
15233
1828618151
15188
1631715765
11310
17073
8038
3286
4752
6646
10427
3670
7640
5817
9948
6215
10102
6675
8513
8054
10097
7909
7324
8887
10387
6781
11505
7533
11666
0
5000
10000
15000
20000
1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008
8038
17073
11310
1576516317
15188
18151
15233
1927418286
19199
Use
rs (m
an
-day
)
JAEA Others
253 231 246290
341
80
173
50
181
63
183
55
235
73
268
79
483
0
100
200
300
400
500
600
2003 2004 2005 2006 2007 2008
253 231 246
290
341
562
Change in number of irradiation utilization
uti
liza
tions
IAEA-TM-38728 (2010)
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Fig. 6. Utilization of JRR-4.
Fig. 7. Utilization of JMTR.
3. COMMERCIAL APPLICATION OF JMTR
Irradiation utilization
Irradiations
JAEA
University
Private uses 33(10%)
8 rooms
171(50%)
26 universities12 (4%)
122(36%)
11
companies 338
Public uses
2 facilities
12
25
34
5
9 10
96
42
393336
6
44
2003 2004 2005 2006 2007 FY
0.8
1.2
0.80.7
0.3
40
10
20
30
0
Change in number of utilization in each topic
Attentions: Y2007 had 25 cycles.
Uti
liza
tio
ns
Education
Medical
irradiation
Silicon irradiation
Manufacture of radio isotope
0.5
0
1
1.5
Irrad
iated
silicon
weig
ht (to
n)
601
9
825
163
1026
247
732
164
620
172
524
353
374
237
395
187
566
197
523
148
0
500
1000
1500
1998 1999 2000 2001 2002 2003 2004 2005 2006 2007
671582611
763877
792896
1273
988
610
FY
Use
rs (
ma
n-d
ay
)
Change in number of users of experiments
JAEA Others
Attentions: Y2007 had 25 cycles.
Private uses
Experiment utilization
<Results in FY2006>
Uses
( man-day)
JAEAUniversity
566(74%)
129(17%)
68(9%)
8 rooms
11
universities
763
5 facilities
The reactor restarted in 2/22 FY2010. The utilization
has been available since 3/24 FY2010.
Irradiations
9,165*
JAEA4,632(50%)University
2,722(30%)
1,340(15%)
RI production
471(5%)
Private uses
Irradiations
9,165*
Light water Reactor
21%
Fusionreactor
7%
High Temperaturereactor
7%
Fundamental
Research
44%
RI production
15%
7%Others
Irradiation fields(1-165Cy) Users(1-165Cy)
0
50
100
150
200
250
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006
Utiliz
ations
Change in number of irradiation utilization
Private uses
RI production
University
JAEA
140
241218 213
164
85
163 174
10697
*: unit (cycle・capsule)
IAEA-TM-38728 (2010)
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3.1. Refurbishment of JMTR
The check and review on restarting JMTR operation was first carried out in November 2005,
and after about one year of discussion, the JMTR reactivation was set for December 2006
upon strong user requests. Then, refurbishment works have been ongoing since 2007, and
reoperation will be achieved in the 2011 fiscal year. For the reactivation of JMTR, JAEA
announced that external utilization will be promoted corresponding to users’ opinion, and that
the usability of the JMTR will be improved to provide attractive circumstances to users.
From a user’s standpoint, the following measures will be taken:
— Achievement of a reactor availability factor of 50% to 70%;
— Establishment of a simple irradiation procedure and satisfied technical support system;
— Shortening of turnaround time (time from application to obtain data) to get irradiation
results earlier;
— Realization of attractive irradiation costs in comparison with other testing reactors in the
world;
— Security of business confidence by information control and other measures.
For the first item, the achievement of a higher reactor availability factor, the possibility of
reactor scram by an accident will be decreased by the replacement of reactor components. In
addition, even if the failure of components occurs, repairing the failed components will also
become easier due to the replacements. Consequently, these measures will shorten the time of
unavailability. Actually, the JMTR has already achieved a high number of operation days per
year, twice boasting more than 180 days in a year. Then, the replacement of old and
unreliable components leads to a higher reactor availability factor. Furthermore, optimization
of the overhaul time of the reactor, defined once per year by the Nuclear Safety Commission
of Japan, will also create a longer operation period during a given year. The operation of the
new JMTR will achieve at least 210 days per year as shown in Figure 8.
For the second item of the technical support system, specialists of irradiation technology and
irradiation research, such as specialists of reactor fuel and reactor materials, are necessary to
discuss sufficiently with users on the details of irradiation methods and conditions at the
planning stage.
Fig. 8. Operation plan of new JMTR.
Apr. JuneMay Mar.Feb.Jun.Dec.Nov.0ct.Sep.Aug.July
Periodical inspection
171
cycle
174
cycle
175
cycle
176
cycle
177
cycle
Maintenance
2011
2012
F.Y.
24-4
cycle
23-1
cycle
23-2
cycle
23-3
cycle
23-4
cycle
23-5
cycle
23-6
cycle
24-1
cycle
24-2
cycle
24-5
cycle
24-6
cycle
24-1
cycle
166
cycle
167
cycle
169
cycle170
cycle
168
cycle
172
cycle173
cycle
24-3
cycle
JMTR
JRR-3
JMTR
JRR-325-1
cycle
Periodical inspection
Periodical inspection
Corresponding to the increase of irradiation utilization, reactor-operation rate should be increased. - In 2011 F.Y. 5 cycles are planning, In 2012 F.Y. 7 cycles (about 60 %) are planning.- Alternative operation with JMTR and JRR-3 for steady RIs supply.
IAEA-TM-38728 (2010)
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This is an example of the improvement of the reactor’s usability that will improve the
experience of many users due to the fulfillment of the technical support system.
3.2. Promotion of utilization
To increase the reactor’s utilization, it should be necessary to contact several user groups with
potential for JMTR usage, as shown in Figure 9. Some kinds of irradiation programmes need
advanced irradiation facilities that are not installed in JMTR. In this case, a user’s fund is
necessary to install the new facilities. As an example of this case, new facilities of safety
research for light water reactor (LWR) materials and fuels are under preparation stage based
on the user’s fund. The key point to promote utilization is to provide highly valuable data to
users with advanced irradiation technologies.
Fig. 9. Increase of irradiation utilization.
3.3 Proposal of international network
The new JMTR will contribute research and development utilization as well as industrial
utilization by offering excellent irradiation technologies. In irradiation, an attractive
irradiation test will be proposed by developments of advanced technologies such as new
irradiation technology, new measurement technology and new Post Irradiation Examination
(PIE) technology. Furthermore, cooperation with various nearby PIE facilities surrounding the
JMTR will be established to extend the capability of PIEs after ongoing discussion with the
nearby facilities.
Construction of a world network is one proposal to achieve efficient facility utilization and
providing high quality irradiation data by role sharing of irradiation tests with Materials Test
Reactors in the world, as shown in FIG.10. As the first step, mutual understanding among
Materials Test Reactors is thought to be necessary. Following this point, an international
symposium on Materials Test Reactors, ISMTR, was held at JAEA in 2008 for the purpose of
Provide high valuable irradiation data to users, and promote the use of irradiation as a result
Reactor Building
Hot Laboratory
Reactor
JMTR
LWR fuels/materials development
Si semiconductor production
User group
- - - - - - - - -
Fundamental research( Univ. etc.)
User group
- - - - - - - - -
RI production
User group
User group
User group
User group
User group
Mo-99 production Education & training
Discussion with each user group and accept users requests
IAEA-TM-38728 (2010)
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world network construction. The 2nd
ISMTR was held in the US in 2009 and the 3rd
was held
in the Czech Republic. The 4th
ISMTR will be held in Argentina during next year.
In the Asian area, some excellent testing reactors are operated currently such as HANARO in
Korea and OPAL in Australia. Each of these reactors has individual and original
characteristics and takes a supplementary role with respect to each other. The JMTR has a
plan to contribute greatly to users by construction of an internationally utilized facility as an
Asian center of testing reactors.
Fig. 10. Increase of irradiation utilization.
4. CONCLUSIONS
From user surveys of Materials Test Reactors among other research reactors, utilization of
research reactors can be categorized into four major application targets: LWR related R&D,
progress in science and technologies, industrial use, and education and training of nuclear
scientists and engineers.
JAEA has developed four different research reactors: JRR-3, JRR-4, NSRR and JMTR,
designed specifically for intended purpose. The utilization status for these reactors was
introduced in this paper.
JMTR and its reactor facilities are now under refurbishment. The refurbished JMTR is
expected to gain an appreciable income from commercial users. A few successful examples of
JMTR utilization were presented in this paper from a viewpoint of commercial application.
Since strengthened regional and international cooperation is a key issue to enhance the steady
commercial applications such as RI production, the importance of regional and international
framework was also mentioned.
Efficient facility utilization and providing high
quality irradiation data by role sharing of
irradiation tests with characteristics of
each testing reactor
- Study of fuel / material for LWRs
- Education, training etc.
- Stable supply of RI, 99Mo etc.
・Information exchange・Interchange of staffs, etc.
European center
BR2
HFIR
HANAROUS center
JMTR
ATR
World Network
Asian center
Regional Network
(Asian Network)
Mutual understanding
WWR-K
TRIGA PUSPATI
OPAL
NRU
SM-3
BRRMARIALVR-15
OSIRIS HFRHBWR
World Network
Construction of international cooperation system
by world wide testing reactor network