PRESENT STATUS AND FUTURE POTENTIAL FOR … · PRESENT STATUS AND FUTURE POTENTIAL FOR COMMERCIAL APPLICATION OF JAEA RESEARCH REACTORS ... Type Type of Uranium-Zirconium-hydride

IAEA-TM-38728 (2010)

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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

[email protected]

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.

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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

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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)

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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

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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)

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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

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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