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Information Exchange Mainly on HTGR Operation and Maintenance Techniquebetween JAEA and INET in 2006

Yukio TACHIBANA, Ryutaro HINO+ and Suyuan YU*

Department of HTTR
Oarai Research and Development Center
Japan Atomic Energy Agency
Oarai-machi, Higashiibaraki-gun, Ibaraki-ken(Received April 2, 2007)

The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been
growing because the high temperature heat produced by the reactor can be utilized not only for
efficient power generation but also for broad process heat applications, especially forthermo-chemical hydrogen production to fuel a prospective hydrogen economy in future.
Presently only two HTGR reactors are operational in the world, including the HTTR (HighTemperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and theHTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua Universityin China. JAEA and INET have cooperated since 1986 in the field of HTGR development,particularly on the HTTR and HTR-10 projects. This report describes the cooperation withemphasis on HTGR operation and maintenance techniques between JAEA and INET andoutlines cooperation activities in 2006.

Keywords: HTGR, HTTR, HTR-10, International Cooperation+ Nuclear Science and Engineering Directorate* Institute of Nuclear and New Energy Technology of Tsinghua Universityᣣᧄේሶജ⎇ⓥ㐿⊒ᯏ᭴ߣਛ࿖ᷡ⪇ᄢቇᩭ⢻෸ᣂ⢻Ḯᛛⴚ⎇ⓥ㒮ߣߩ㜞᷷ࠟࠬἹㆇォ଻቞ᛛⴚ╬ߩᖱႎ੤឵ߦ㑐ߔࠆႎ๔ᦠ㧔2006 ᐕ㧕ᣣᧄේሶജ⎇ⓥ㐿⊒ᯏ᭴ᄢᵞ⎇ⓥ㐿⊒࠮ࡦ࠲࡯㜞᷷Ꮏቇ⹜㛎⎇ⓥἹㇱᯌ ᐘ↵‫ޔ‬ᣣ㊁ ┥ᄥ㇢+‫ޔ‬Suyuan YU*㧔2007 ᐕ 4 ᦬ 2 ᣣฃℂ㧕㜞᷷ࠟࠬἹ߆ࠄขࠅ಴ߐࠇࠆ㜞᷷ߩᾲߪ‫ޔ‬㜞ല₸⊒㔚ߩߺߥࠄߕ‫ޔ‬ᐢ▸࿐ߥࡊࡠ࠮ࠬᾲ೑↪‫ޔߦ․ޔ‬ᾲൻቇ᳓⚛⵾ㅧߦ↪޿ࠆߎߣ߇ߢ߈ࠆߎߣ߆ࠄ‫ޔ‬㜞᷷ࠟࠬἹ߳ߩ㑐ᔃ߇਎⇇⊛ߦ㜞߹ߞߡ޿ࠆ‫⃻ޕ‬࿷‫ޔ‬਎⇇ߢㆇォߐࠇߡ޿ࠆ㜞᷷ࠟࠬἹߪ㧞ၮߩߺߢ‫ޔ‬㧝ߟ߇⁛┙ⴕ
᡽ᴺੱᣣᧄේሶജ⎇ⓥ㐿⊒ᯏ᭴ߩ HTTR㧔㜞᷷Ꮏቇ⹜㛎⎇ⓥἹ㧕ߢ޽ࠅ‫ ߁߽ޔ‬1 ߟ߇‫ޔ‬ਛ࿖ߩᷡ⪇ᄢቇᩭ⢻෸ᣂ⢻Ḯᛛⴚ⎇ⓥ㒮㧔INET㧕ߩ HTR-10 ߢ޽ࠆ‫ޕ‬ේሶജᯏ᭴ߣ INET ߪ‫ޔ‬1986ᐕߩⷡᦠ✦⚿એ᧪‫ߢ߹ࠇߎޔ‬㜞᷷ࠟࠬἹಽ㊁‫ޔߦ․ޔ‬HTTR ⸘↹෸߮ HTR-10 ⸘↹ߦߟ޿ߡ⎇ⓥදജࠍㅴ߼ߡ߈ߚ‫ᧄޕ‬ႎߪ‫ޔ‬2006 ᐕߩේሶജᯏ᭴ߣ INET ߩ㜞᷷ࠟࠬἹ㐿⊒ߦଥࠆਥⷐߥ⎇ⓥදജᵴേߦߟ޿ߡ‫ޔ‬㜞᷷ࠟࠬἹㆇォ଻቞ᛛⴚߦ㊀ὐࠍ⟎޿ߡ߹ߣ߼ߚ߽ߩߢ޽ࠆ‫ޕ‬ᄢᵞ⎇ⓥ㐿⊒࠮ࡦ࠲࡯㧦‫ޥ‬311-1393 ⨙ၔ⋵᧲⨙ၔ㇭ᄢᵞ↸ᚑ↰↸ 4002+ ේሶജၮ␆Ꮏቇ⎇ⓥㇱ㐷* ਛ࿖ᷡ⪇ᄢቇᩭ⢻෸ᣂ⢻Ḯᛛⴚ⎇ⓥ㒮

Contents
1. Introduction ···························································································································· 1
2. Cooperation on HTGR Development between JAEA and INET ··········································· 62.1 History of Cooperation ·································································································· 62.2 Area of Cooperation ·······································································································62.3 Status of HTTR in 2006 ································································································· 72.4

Status of HTR-10 in 2006······························································································ 83. Major Cooperation Activities in 2006 ·················································································· 113.1 Information Exchange Meeting ··················································································· 113.2 Mutual Visits between JAEA and INET ······································································ 11
4. Concluding Remarks ·············································································································12Appendix A ·································································································································· 13
Appendix B ·································································································································· 23⋡    ᰴ㧝㧚ߪߓ߼ߦ ································································································································1
㧞㧚JAEA ߣ INET 㑆ߩ㜞᷷ࠟࠬἹ㐿⊒ߦ㑐ߔࠆදജ ··························································6㧞㧚㧝 දജߩ⚻✲ ················································································································6㧞㧚㧞 දജߩ▸࿐ ················································································································6 㧞㧚㧟 2006 ᐕߩ HTTR ߩ⁁ᴫ ·························································································· 7 㧞㧚㧠 2006 ᐕߩ HTR-10 ߩ⁁ᴫ ······················································································· 8
㧟㧚2006 ᐕߩਥⷐߥදജౝኈ ·································································································11㧟㧚㧝 ᖱႎ੤឵ળ⼏ ··········································································································11㧟㧚㧞 JAEA ߣ INET 㑆ߩ⋧੕ߩ⸰໧ ············································································ 11㧠㧚⚿ ⸒ ··································································································································12ઃ ㍳㧭 ······································································································································13
ઃ ㍳㧮 ······································································································································23

1. Introduction
The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been
growing because the high temperature heat produced by the reactor can be utilized not only for
efficient power generation but also for broad process heat applications, especially forthermo-chemical hydrogen production to fuel a prospective hydrogen economy in future.
National projects on HTGRs are ongoing in Japan, China, France, USA, South Africa, Korea,etc., and the VHTR (Very High-Temperature Reactor) is chosen as the most promising
Generation IV nuclear reactor system in GIF (Generation IV International Forum). There arepresently only two HTGRs operating in the world, HTTR, High Temperature Engineering Test
Reactor, in JAEA (see Table 1.1 and Fig. 1.1) and HTR-10 in Institute of Nuclear and New
Energy Technology of Tsinghua University (INET) (see Table 1.2 and Fig. 1.2).
Construction of the HTTR was started in 1991 and its first criticality was achieved onNovember 10, 1998. Then, power-up tests were carried out, and rated thermal power of 30MW
at the reactor outlet coolant temperature of 850°C was attained in December 2001. Rated power
operation and safety demonstration tests using the HTTR have been conducted since FY2002.
After several operational cycles, high temperature test operation of the HTTR to achieve thecoolant temperature of 950°C was conducted, and coolant temperature of 950°C at reactor outlet
was reached on April 14, 2004.
First criticality of the HTR-10 was achieved at air condition on December 1, 2000, andre-criticality at helium condition was attained in July 2002. Then, power-up tests wereconducted, and the first synchronization at 3MWt was achieved in January 2003, followed byfull power operation at 10MWt with core outlet temperature of 700°C in February 2003. Safety
demonstration tests including helium circulator trip without scram and reactivity insertion
without scram were carried out in 2003 and 2005.
INET is also promoting development of Modular High-Temperature Gas-cooled Reactor(MHTGR) named as High Temperature Gas-Cooled Reactor – Pebble bed Module (HTR-PM)(see Table 1.2 and Fig. 1.2), based on the technology and experiences of the HTR-10. The
HTR-PM project is under the standard design phase, and the HTR-PM demonstration plant isplanned to finish construction by 2013.
JAEA and INET have cooperated in the area of HTGR development, especially on HTTR andHTR-10 projects, since 1986 when a Memorandum of Understanding was exchanged between thetwo institutes. This report describes cooperation on HTGR development between JAEA and INETand major cooperation activities in 2006.

Table 1.1 Major specifications of HTTRThermal power

30MW

Outlet coolant temperature

850°C/950°C

Inlet coolant temperature

395°C

FuelLow enriched UO2Fuel element type

Prismatic block

Direction of coolant flow

Downward

Pressure vessel

Steel

Number of cooling loop

1

Heat removal

IHX and PPWC (parallel loaded)

Primary coolant pressure

4MPa

Containment type

Steel containment

Plant lifetime

20 years

MWMW
MPa°C°C
kg/s
MPa°C-Net output powerPrimary helium pressure

Helium inlet temperature

Helium outlet temperature

Helium mass flow rate

Main steam pressure

Main steam temperature

Number of spherical fuel elements

27000

435

3.5

4.3

380000

543

13.5

96750

250

2507007.0100250

HTR-PM

3.0

2.5

10HTR-10

Specifications of HTR-10 and HTR-PM

Reactor thermal powerParameters

Table 1.2

HTR-10Fig. 1.2

Figures of HTR-10 and HTR-PMHTR-PM

2. Cooperation on HTGR Development between JAEA and INET
2.1 History of Cooperation
Vice chairman of Atomic Energy Commission of Japan, was requested for collaboration
between China and Japan in the area of HTGR research and development during his visit toChina in June 1985.
In September 1985, Director of Institute of Nuclear Energy Technology of Tsinghua
University (INET) visited HTGR research and development facilities in Japan Atomic Energy
Research Institute (JAERI), and discussed exchange of a Memorandum of Understanding(MOU) about cooperation on HTGR research and development.
In December 1985, A JAERI delegation visited INET and discussed exchange of a MOU.
In June 1986, JAERI and INET exchanged the initial MOU.
In June 1988, valid duration of the MOU was extended until June 1990.
In June 1990, the MOU was further extended until June 1995. In addition, PersonnelAssignment Agreement was added to the memorandum of understanding.
In June 1995, valid duration of the MOU was extended until June 2000.
In June 2000, the MOU was further extended until June 2005.
In September 2003, Institute of Nuclear Energy Technology of Tsinghua University (INET)
changed its full official name to Institute of Nuclear and New Energy Technology of Tsinghua
University (INET) to further broaden academic disciplines of the institute.
In June 2005, valid duration of the MOU was once again extended until June 2010.
In October 2005, JAERI and Japan Nuclear Cycle Development Institute (JNC) merged toform Japan Atomic Energy Agency (JAEA).
Since June 1986 until today, information exchange meetings have been held almost everyyear as shown in Table 2.1, and general information exchange on research and development
plan on HTTR and HTR-10 as well as on technologies in the area of HTGRs has been made.
Since the HTR-10 is the only pebble bed type HTGR and the HTTR the only prismatic block
type HTGR being operated in the world at present, the information exchange has been
beneficial for both JAEA and INET.
Since 1990 when the Personnel Assignment Agreement was added, JAEA has accepted
researchers from INET in the field of HTGR safety, nuclear heat utilization, etc.

2.2 Area of Cooperation
The original MOU exchanged in 1986 stipulated the area of cooperation as follows. INET

and JAEA will provide to each other program status and technical outline information such as is
generally available at each of their respective facilities relating to their respective programs forresearch and development of Gas-cooled Reactors. Each party will review the information
provided by the other’s programs as a basis for discussions on a future agreement. The subject
matter of the information to be exchanged shall include, but not be limited to, the followings:A)

The High-Temperature Gas-cooled Reactor (HTGR), for process heat andcogeneration, including both fuel technology and plant technology.

B)

The Very-High Temperature Gas-cooled Reactor (VHTR), for process heat, including
both fuel technology and plant technology.
(Note: The Very-High Temperature Gas-cooled Reactor (VHTR) here is similar to but
not the same as the VHTR selected as a Generation IV nuclear system.)

In 1990, the MOU was amended by inserting that each party may assign its personnel into
the facility of the other in accordance with the Personnel Assignment Agreement, and that forthe purpose of carrying out the cooperative activities under the MOU, both parties may
exchange samples when agreed by both of them. The MOU in 1990 also added a newparagraph: Each party shall make available, at least once a year to the other party reports written
in English which have been published by each party.

2.3 Status of HTTR in 2006
The third periodic inspection of the HTTR was continued, and all the three wide range
monitoring detectors were replaced with new ones.
The HTTR was started up on October 27, 2006 for periodic inspection (full poweroperation) and safety demonstration tests, but on October 31 it was found that pressure ofatmosphere inside the reactor containment vessel had been gradually increasing, and it wasdecided to shutdown the reactor on November 1. After investigation of the causes wascompleted and countermeasures were taken, the HTTR was restarted on November 14, and on
December 8 the third periodic inspection was completed with the final on-the-spot inspection bythe MEXT.
After that, reactor power of the HTTR was decreased from the full power of 30 MW to 24
MW (80%), and reactivity insertion tests and coolant flow reduction tests were performed assafety demonstration tests from December 12 to 15..
Regarding the additional safety demonstration tests, loss of forced cooling tests and vessel
cooling system stop tests, on September 27 JAEA received construction permit from the MEXT
for remodeling of the safety protection system of the HTTR, which is necessary for theadditional tests.

2.4 Status of HTR-10 in 2006
In the year of 2006, INET continued conducting inherent safety test and longtime
operation test on HTR-10. HTR-10’s running days amounted to 97 days, the power operation
last for 2288.83 hours, and the accumulated power reached 458.2MWD. Systems and facilities
logged with good operating records during the long-term and continuous run. In the process ofthe operating tests, the performances of some key systems and facilities of HTR-10, such as
control rod system, absorption ball system, helium circulator, and steam generator were tested
and then inspected following tests in actual operating conditions of high temperature, highpressure, irradiation, etc. All the performances proved consistent with the design specifications.
For example, Table 2.2 shows helium quality in different power.

Table 2.1

Number of people visiting INET from JAEA and JAEA from INET
for the purpose of exchanging information on HTGR

Year

Number of people
visiting INET from JAEA

Number of people
visiting JAEA from INET

1986

201987

201988121989011990131991

30199222199314199431

1995

221996141997221998

42

1999

03

2000

32

2001

022002122003132004252005532006

13Table 2.2

Helium quality in different power(vol ppm)TimePower

H2O2

N2CH4COCO2H 2O

06-1-1

6.9MW

3.50

0.23

0.50

0.35

2.34

0.76

0.05

06-1-9

4.8MW

2.39

0.10

1.33

0.34

3.58

2.14

0.21

06-2-23

3.5MW

1.46

1.82

0.65

0.16

4.45

2.5

0.26

02-2-29

6.7MW

3.29

0.15

0.4

0.3

2.71

0.65

0.14

06-3-12

6.7MW

2.88

0.4

0.64

0.34

1.77

0.67

0.15

06-3-29

6.2MW

2.84

0.41

1.14

0.28

2.30

0.70

0.18

06-11-25

3.3MW

0.72

0.28

1.15

0.07

1.19

0.39

1.6406-12-2

3.4MW

1.21

0.17

0.58

0.19

0.82

0.2

0.73

06-12-20

3.7MW

1.72

0.24

0.78

0.17

1.03

0.38

0.03

3. Major Cooperation Activities in 2006
3.1 Information Exchange Meeting
An information exchange meeting between JAEA and INET under the MOU was held in
INET on September 19, 20 and 21, 2006. An engineer of Department of HTTR, JAEA, and 12
professors and researchers of INET in total attended the meeting.
In the meeting, JAEA presented problems for long high temperature (50days, 950°C)
operation such as performance improvement of gas circulators in helium purification system,
replacement of the filters for the primary helium gas circulators, and performance maintenanceof auxiliary component water cooling system. INET presented status and prospect for the R&D
on HTGR in China including HTR-10, HTR-10GT and HTR-PM projects. In addition, JAEA
and INET exchanged information on operation and maintenance experiences such as impurities
in coolant, helium leak rate of primary cooling system, and filters in cooling system. JAEA also
provided INET information on design, operation experiences, in-service inspection (ISI)
technique, etc. of intermediate heat exchanger of the HTTR.
Presentation material of JAEA and INET in the meeting is attached in Appendix A andAppendix B, respectively.
The JAEA engineer received two reports written in English from the INET researchers.

3.2 Mutual Visits between JAEA and INET
Three researchers of INET have visited JAEA being engaged in the studies as follows .
1.

Liu Tao (January-July, 2006)

Reactor safety2.

Zhang Haiquan (September 2006 – December 2006)

Study on research for system engineering in a nuclear power plant
3.

Yang Xiaoyong (September 2006 – June 2007)

Study on research for system engineering in a nuclear power plant, effective reaction
technology for thermochemical hydrogen production IS process

4. Concluding Remarks
This report summarized cooperation on HTGR development between JAEA and INET andmajor cooperation activities in 2006. An information exchange meeting was held in INET inSeptember. Enhancing future collaboration between JAEA and INET is important, andcontinuous information exchange on HTGR-related technologies is beneficial for the bothinstitutes.

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