L SI

* -, -

X~r~tb*4 ~4

~ ;tA 'L

slo' -

* *: A:: :: 4

Governmetal. S r f- -u fGovernmental Support- -or am- -,

4Z -iliJ ,ztzb zmVice Premier Li Lanqmg inspecting the installation of reactor core

State Councillor Wu Yi and Minister of Ministry of Science and Technology Zhu Lilan

inspecting the instaUation of steam generator

a or* a a * -

of~

. I I I

jI I -*.

Ir- -

. .

0I.

Usft-~Ua I ' '

! Ifi,

Ir1..1-,;a ¾I, 6-

. 3

A IV Ik5

t Is Z15-ItH R--mc rs oii )a*. y _ .

r,,lqfiN*s b1*U'tZ#PJJHTR-IO0I:FUi:f3&Zgtartar State Councillor Song Jian taking part in the ceremlony of pouring the first concrete

M l

-mq

•,tSVS1

.s

>7U., ii ?r s 1h:' TR 1 0- t.-or>gj DCooperation for HTR-1O0

I1

IC=Sza .I;?~

CER 6 0 NY FO R PROF. SCH ULTE NBEING AWARDED AS GUEST PROFESS OR

OF 1SINGULIMINIVERSITV..:

t

IT . V -.1111¼ - h -. ^-q 4

C

r-

L.

C-4C

.. C

at

AI

I%

.& £51 Il R I'Mfl±.- ,;t 4t J j- flj 9 : )f: 4:.IffjuFTR- I Oflj

Prof. Schiuten. Geriany nuclear exlxprt. was awarded as a guestproicssofi Tlshimgha Ulniversity, visiting HlTR- 10 and givinghintrst ton 111

* : - 6 4wJ''

jlll:Jli fflult;iLijQ.C i 1j: (;+ eI'jjIJ I I'l'R- i:f'¶"tJ& *

t Ir. 1I juts MIx, Dirct-lor General Elmerilt Lt It L.A, visiti1 - itt1s and giv ilng insI ru'l tioI

! f i

_ ---

~ 965Pt,

EtDrgo)OC6~ E~j 1966.4q

rsi ~WNPR43-4%, t, W9:M i

-V (ThTR-(Dago) 164I-81966~~j

(Pac Bttm PFrmatmeIl ±J½ JtB"nJT- (AR I971,K

- Ar-

- L3

4.Kd~a- t --I Io

FS F-S

~~Al # AV.~k~

!J18Ocm, e;Ak-)-&1 97cm.-

a3

HTR-1 O0 a 9MI E- 4 ]aJ . L

~±~~* X4~ 3f J=±i&1~L~FA ~1O;±jE

IV' t -%

* ~ i~M

The 1 0 MW High TernperE.u.Gas-cooled Reactor Test M

(termed HTR-10)

The 10 MW High Temperature Gas-cooled Reactor Test Module(termed HTR-10) is a majorproject in the energy sector of the Chinese National High Technology Programme, serving as the

first major step of the development of modular HTGR in China. Its main objectives are: 1. to explorethe technology in the design, construction and operation of HTGRs, 2. to establish an irradiation and

experimental facility, 3. to demonstrate the inherent safety features of modular HTGR, 4. to testelectricity and heat co-generation and closed cycle gas turbine technology and 5. to perform research and

development work on nuclear process heat applicationInstitute of Nuclear Energy Technology (INET) of Tsinghua University is the leading institution to organize

and inplement the key technology development, the conceptual design and the feasibility study of HTGRduring 1986-1990, the so called Seventh Five-Year Plan Period, and then it continues to be responsible for

the design, license application, construction and operation of the HTR-10 test reactor. Now the construction ofHTR-10 was completed at the site of INET, which is located in the northwest suburb of Beijing city.

The HTR-10 project is to be carried out in two phases In the first phase, the reactor with an coolant outlettemperature of 7000C will be coupled with a steam generator providing steam for a steam turbine cycle which

works on an electricity and heat co-generation basis. In the second phase, the reactor coolant outlet temperatureis planned to reach to 9000C. A gas turbine cycle and later on a steam reformer will be coupled to the reactor inaddition to the steam turbine cycle.

The HTR-10 design represents the features of modular HTGR design The reactor core and the steam

generator are housed in two steel pressure vessels, which are arranged in a side-by-side way These two vesselsare connected to each other by a connecting throeugh the hot gas duct . All these steel pressure vessels are in

touch with the cold helium of about 2500C coming out from the circulator which sits over the steam generator tubesin the same vessel.

Fuel elements are the spherical fuel elements (6 cm in diameter) with coated particles The reactor core containsabout 27,000 fuel elements forming a pebble bed which is 180 cm in diameter and 197 cm in average heightSpherical fuel elements go through the reactor core in a"multi-pass" pattem. Pulse pneumatic fuel handling systemis designed for continuously charging and discharging fuel elements.It has the advantage of reliability andsimplicity.

Graphite serves as the main material of core structures which mainly consist of the top, bottom and sidereflectors The ceramic core structures are housed in a metallic core vessel which is supported on the steelpressure vessel. The thickness of side reflector is 100 cm, including a 25 cm thick layer of carbon bricks at theouter periphery. In the side reflector, cold helium channels are designed in which helium flows upward afterentering the reactor pressure vessel from between the connecting vessel and the hot gas duct.

Helium flow reverses at the top of reactor core into the pebble bed, so that a downward flow pattern takesplace in it. After being heated in the pebble bed, heliurri enters into a hot gas chamber in the bottom reflector,and from there it flows with reactor outlet temperature through hot gas duct to the heat exchangingcomponents.

The steam generator is composed of a number of modular helical tubes, which are arranged in a circlebetween two insulation barrels inside the steam generator pressure vessel The place inside the inner barrelis foreseen for an intermediate heat exchanger (IHX) which will be installed in the second phase of theproject The IHX is a helical tube type Nitrogen flows inside the tube while helium flows outside the tube.

Decay heat removal of the HTR-10 is designed on a completely passive basis. At a loss of pressureaccident, against which no core cooling is foreseen at all, decay power will dissipate through the core

structures by means of heat conduction and radiation to the outside of the reactor pressure vessel,where, on the wall of the concrete housing, a surface cooling system is designed. This system works

on the principle of natural circulation of water and it takes the decay heat via air coolers to theatmosphere.

There are two reactor shutdown systems, one control rod system and one small absorber ballsystem. They are all installed in the side reflector. Both systems are able to bring the reactor to

cold shutdown conditions. Since the reactor has strong negative temperature coefficients anddecay heat removal does not require any circulation of the helium coolant, so the tum-off of

the helium circulator can also shut down the reactor from power operating conditions.

- -{ . ,, i .

-¼L I ,- - , X -D

t a-

HTR-10 O345t -:HTR-1O Fuel Elements .PI

p . ,

4.+

4

Spherical fuel elements .

E

Wfi

.: ~shell region: :

* ' ,APR, ' .-_ / fuel region

Fn I ; matrix graphite '

< : 2coated particles

- :tOm . -:,*A

4

50mmo I jI6mm --p # ;v-

one wit cote parics Fue elemen@t:

4.

dtiamter s0 0mm. Abot 8300oatedIpatRicles are homogen, l dsprsed inE a0Je mar region .

4i

The HTR-10 fuel elements are sphericalones with coated partic;s. Fuel elementdiameter is 60mm. About 8300 coatedparticles are homogeneeusly dispersed in agraphite matrix region irnevery fuel element.The matrix region has aqiiameter of 50mm.The coated particles are.TRISO type, i.e.,

there is one SiC coating layer between tw opyrocarbon layers which is very effective inretaining fission products within theparticles.

111F.

.U

.Iik.Z

0

I.v-

r C

I _Iftti, 7L. M 11,% & ififftjCross section of coated particle

- - . 6 O.L.

Coating layers -

1 0n L JL' I-E IA+t t t -Specification of HTR-

1 Reactor core

A lb : 1OMWThermal power

.JAveraged -powerdenslty ''t 4lL~w - Ls>

t :ti~a:1800mmCore diameter

<-Eqtvlet orheight;<- S~,-_ I-527000

Number of fuel elements

t >sg~t:250°CCore inlet temperature of helium

-'Core ou tperaeou nkrtaf>e '

g~q~g~qt~~tijtit:20Number of helium coolingchannel in the reflector

,JvLwmbL-& cL em2fsLe2A L

Number of absorb ball channels 7In the reflector

Reactor pressure vessel

- -4200mmInner diameter

Total height 11344mm

, I, - , .,

_ . i -, - ,Y

*UUNWUNEU- &armaE . II.* .,,, . ;

Steam generator -i:W_ ,b- . 4--

,, . I _. I

| .. .. ... Ia._ . .j

1, 7

SeRageneIL-atr pss- Steam generator pressure vessel

IF . . I

-, ,-

,= 0i~s :00 0 d

Pressure v'qssel of steam generator :;. -

Inner diameter - % 2500 mm

, M4AJM.: p

Thickness : . 50 mm. O

Total height * 12000mm

'.,

U

I AN TX;:, 1

:~ Helium ii-rc-Antoru

C

g-lTICITRVIM- U M )3Installing helium circulator in pressure vessel

-Pressure vessel of hot gas diU.

it

Total lengths

Outer diameter

l'iThkikess

Ii' . ami

Af, .

. t rk ; ... . it

H

Hot gas i1uct- :.

"V L_-,F

f

'- l A Ek i I P'1 t,('- l . ) LIlInserting ml. gas d .ct into Its pressurt vessel

S ux';.t i':: 570iuMmiei i011inscer of 1t11r L ILt ic JInnr cianivil er or inner 1300m1

I 1 5111 111Thickness ol inner dLUCI

MiPffI UL : 1I niThlsicknsess or inSwltion ....... i

4

4

a#**

4.*-

Features of pu

1go of Fuefeem elements e

tRJ%.ER~gW *XgJ ANK

HTR-10 Fuel handling system works on _pneumatic principle. Fuel elements are removed P

from the reactor core in a singularized way by t _

means of pneumatic pulses.

PI 0 1KE i 8lm * Fuel element elevator

TF r-R$MP* MASTt X AO li1.75ttR-f=

9FLJSW .

..- - s , !aa,,, . .

1. 06 0", ..-q ,- -I

. I �� - ; , I I.

, i. : m . -i- X

v I . � -

1 OJL4ag

t* To

It A

2 -:-9AMIrf jt ;NAM

U

Cavity cooling system

Cr

LL-

The HTR-10 reactor internal erial isprimarily graphite and carb ricks.Residual heat removal fthe reactorcore can take place te gh mechanismsof heat conducti iation and natureconvection cooling system takesther eat away to air coolers.

avity cooling and air coolers workon natural circulation principle. Thesepassive/inherent features of the residualheat removal enhance reactor safety.

1S W k H E--I 'Ia I, IteR~~n4 PI I= -'

t o t<Ft .T

Helium punification system

Even though radioactivitylEreleased into primary coolant is i 8minimized, helium purification Esystem which continuously_ _ l _removes radioactivity and other I-

impurities from primaryDl

radioativt level of primnary

- Steam turbine generator

.. _K

U EU EUDUE ma ama. I � 1 1 , Ir, , , , -,;: - � I ...I I ..

Z''Z"ZO /--- %4 & MP= -rr.3M- )�&3"FFE3 Ila II J;jEA...., " F;U13E �- -1 1

Mil 06 *constructing HTR-10'. r -'+ tJrS a

'

ItV

1 AZ. 3.1 4 raI?1 0 jr n {t*j

."863' &Mitil] 3i... 1994.14- t4 n 0§ E'n t

1995.6.140 HT<R--;1003TTEMg-M& $

-- 1997.10.28 aEo rg I t"J

1998.11.27 Z Rs ,+ it

- - a2000.12

2000.4.29 , JThiAtmiilojr- 2000.9 irof HTRk 10

2000,11.17 n~ WPWm T ii-2000.11.20 ItM4P

g 2000.12 10

1992.3.14 HTR-103roject was approved by government .-

as one of the national "863" project

1994.12 Constnuttion Permit of HTR-10 was issued:.4 by Natisial Nuclear Safety Administration

;~~ .a.*

1995.6.14 - First concrete was poured -:

1997.10.28 Main ruilding of HTR-10 was completed

1998.11.27 The feactor Presure Vessel and SteamGernerator Pressure Vessel was installed

rmit : int the cavity

i

11ITConrfirucl ion cere

-- a.n

~Jib'dL l:-1Construction Pi'o

a1999.12 installation of ceramic intemals was completed

22000.4.29 *The head of pressure vessels were covered .

a

! 2000.9 ... ..

~*2,MO.11 .20

. 2000.12-a

Components and systems installation werecompleted

Fuel loading Commissioning license was issuedby National Nuclear Safety Administration .

Starting fuel loading

First criticality of the HTR-1 0

I lITl IO fr- 0) lkitBasmeinct CoiiMtruic~$mn or i rnm-io

a

el7 .- ~i

Construction of HTR-10 main building

Former Director of National Nuclear Safety AdministrationHuang Qitao checking up on work

Academician Zhao Renkal and Ruan Keqtang, members of energyexpert committee, checking up on work.

Installing Reactor Pressure Vessel

. i -,

|.-|w" A-.&8,0 a.,Z

t : *

�I

� - ',� -...

; \ W~'.-

z v .

FI

' .t,+w

i, . '

I-V.i

?;-''I

Fastening the flanges of reactor presu.Ire vessel by stretchingM180 bolts using stretch machines'devcldted by INET

r rs~s: e~esi ' ', 'i .* wt U

-#,,yS,-i~s,.,e;.S,,Et-L-.- i ;

Il l �-

h44�.IL2

-. t~

- 't

ArBME,

X L E

C

Installing core Internals

- . ,,

Officers and s~tffs of National Nuclear Safety Administration monitoring physical startup

_

4

4 4*0

4 *

iwry-

I _- I

r-fIII

LL E

=4

DQ hf.. -Z~to 0

0-a--

I ~o I

. 0-. s..52- o.7-

00 0 0

i lOMW A. As A * * J