- Email: [email protected]
Present status of research and development for HTR in China
0360-5442191 53.00 + 0.00 Pngamon Pras pk
&wgy Vol. 16. No. l/2, pp. 159-167, 1991 Printed inGreat Britain
PRESENT STATUS OF RESEARCH AND DEVELOPMENT FOR HTR IN CHINA
DAZHONG WANG, DAXIN ZHONG,
and YUANKUI XU
Institute of Nuclear Energy Technology, Tsinghau University, Beijing, P. R. China
Abstract - The HTR R&D project is being carried out in the rele_--vant institutions in China. The topics covered include fuel element technology, graphite development, fuel element handling system, helium technology, fuel reprocessing technology, as well as HTR design study. Some results of the HTR research studies are described. In addition, a test facility for the investigation of HTR Module reactor safety and the process heat applications of HTR is under construction in a joint project to build a 10 MW test HTR with Siemens-Interatom, KFA Juelich, and INET. The conceptual design of a 10 MW test HTR has been completed by the joint group. In parallel the application study of HTR Module is being carried out for the oil industry and the petrochemical industry, as well as for power generation. Some preliminary results of the application study include heavy oil recovery in the Shengli oil field and process heat application at the Yan Shan Petroleum Company. 1. THE STATUS OF HTR PROGRAM The research and development program of HTGR in China began in the mid-1970s. In the first phase beginning from 1974 , the target was to design and construct a 100 MW(t) HTGR thorium thermal breeder with two-zone pebble bed core. In parallel with the design work of the reactor, a series of research studies for HTGR development were carried out which included the manufacture of fuel kernels, coated particles and several kinds of spherical fuel elements, the characterization of graphite, the prestressed concrete reactor vessel technology and the HTGR components development such as the graphite core structure , the control rod and its drive, charge and discharge of spherical fuel, helium circulator, and the steam generator. In addition, the reprocessing technology of thorium fuels is under development. But the HTGR breeder project was stopped at the end of 1970 due to various reasons, mainly the financial problem. The second phase of HTGR research and development program was in the period of the 5 year plan (1981 to 1985). The State Science and Technology Connnission gave support to continue some basic technology development and to investigate the possibilities of nuclear process steam and heat for industry application. The work was concentrated in certain areas:
.
To continue the coated particle fuel technology development and to some laboratory facilities.
.
To investigate the HTR module concept design and to develop design tools, e.g., the computer codes for physics, thermohydraulics, and safety analysis.
.
Investigation of the application possibilities of HTGR for heavy oil recovery, chemical industry, refinery, oil-shale retorting, and coal gasification.
improve
The present research and development program on HTGR (third phase) is covered in the high technology research and development program, as part of the development of nuclear energy in the next century in China. It is important to develop the advanced
DAZHONGWANG et al
160
reactors which have inherent safety, economical viability, and high fuel utilization. The high-temperature gas-cooled reactor (HTGR) is one of these advanced reactors to be selected to carry out research and development work for future applications. The main topics of this program include: .
HTR fuel technology development, preparation and manufacture of fuel kernels, coated particles and fuel elements on a laboratory scale, characterization and qualification as well as the irradiation testing of coated particles and fuel elements,
.
Graphite,
.
Helium
.
Charging
and
discharging
.
Research technique.
work
on the
.
Application
metallic, technology
study
and and
of
ceramic
materials
components
development.
technique
for
thorium-uranium
the
Modular
development.
spherical fuel
HTR for
cycle
fuel
elements.
and HTR fuel
different
potential
reprocessing
users.
For management and coordination of the HTR research and development program a special unit was established. The institutions which take part in this program are the Institute of Nuclear Energy Technology (INET), Beijing Institute of Nuclear Engineering (BINE), South-West Center of Reactor Research (SWCR), and Shanghai Institute of Nuclear Research (SINR) and others. The aims of this program are to research and develop the key technologies and to investigate the possibility of constructing a demonstration Modular HTR plant. THE 10 MW HTR TEST MODULE CONCEPT 2. In order to introduce and develop the Modular HTR technique in practice, a joint project was started on construction of a 10 MW HTR test module, with collaboration CmbH, and the Nuclear among the INET of Tsinghua University PRC, Siemens-Interatom The 10 MW test module will be constructed at the Research Center Juelich (KFA) FRG. site of INET located in the north-west of Beijing. The main object of the test module is to verify and demonstrate the unique features of Modular HTR at a nuclear test facility. Therefore, the test module have been defined jointly as follows:
relevant the aims
and for
.
The test module will be designed for a wide range of possible applications, e.g., electricity, steam and district heat generation in the first operation phase, and process heat generation and methane reforming in the second phase.
.
The relevant components can be e.g., graphite core structure, handling facility.
.
Verification of the inherent tive temperature coefficient passive decay heat removal, ingress.
.
The test module is capable of withstanding extremely so that fuel element mass-test could be carried out conditions at temperatures up to 1600°C.
tested steam
and proven under helium generator,
nominal blower,
safety features of the HTR-Module such as negatemperature limitation due to of reactivity, and limitation of power excursion due to water
high under
core temperatures, nominal reactor
The conceptual design of the 10 MW test module was carried out jointly The main data of the test module are as follows: and INET in 1988. Maximum thermal power Average thermal power Primary helium pressure Helium temperature Secondary steam pressure Live steam temperature Power density
conditions, and the fuel
20 MW 10 MW 30 bar 250’ and 35 bar 43s”c 2 MU/m3
7OO’C
by
Interatom
Current statusand piansfor the HTGR Core diameter Average core height Height/diameter radio Number of fuel elements Heavy metal content Average burnup Fuel element in-core time Loading scheme
161
190 cm 176 cm 0.93 27,000 5 g/fuel element 80,000 Mu(t) 1078 EFPD OTTO
Figures 1 and 2 show the cross sections of the reactor and the the test module. It has the following important design features.
primary
circuit
of
The reactor core and steam generator are housed in two separate steel vessels and positioned side-by-side in a staggered arrangement. The graphite cylinder core which holds the pebble bed has a diameter of 1900 mm and a height of approximately 2200 sun. This is adequate for the required volume of the active core which amounts to 5 m3. The new fuel elements are charged from the top of the core via five charging tubes. The fuel elements are removed from the core-bottom via a fuel element discharge tube with an inner diameter 500 mm. Decay heat is removable by surface coolers outside the reactor vessel. The surface cooler system is subdivided into two trains. It is sufficient to dissipate decay heat by means of passive heat transfer mechanisms to the simple surface coolers. The primary helium pressure of 30 bar is chosen. The inlet and outlet temperatures of the core are 250’ and 7OO’C. A secondary pressure of 35 bar and a live steam temperature of 435’C are chosen SO that the small standard industrial turbines can be used. The average thermal power of the test module plant is set to be IO MJ. In order to enhance the experimental flexibility the maximum thermal power output is set to be 20 MW. Some variants of the secondary heat sink have been evaluated. Figure 3 shows the heat flow diagram for district heating and electricity generation with the maximum thermal power of 20 MW. The respective figures for the normal operation case (10 MU) are given in brackets. The basic
data
of
the
steam
generator
Helium flow (shell side) Helium pressure Helium temperature Water/steam flow (tube side) Water/steam pressure Water/steam temperature Steam generation rate
are: 8.6 (4.3) kg/s 30 bar 250’ and 7OO’C 7.5 (3.75) kgls 40 to 35 bar 150° to 435oc 27 (13.5) t/h
Figure 4 shows the time schedule of the whole cooperation program. The 10 Mu test module will take 5 years for design, construction, installation, and connrissioning. The basic design will be performed jointly after this project is approved by both the Chinese and German governments. Major .
topics
during
the
basic
design
phase
are:
Design of the test module with the aim of preparing adequate documents for the preliminary safety analysis report.
.
Start
.
Cost review for the test module program with special emphasis on the definition of the local/import sharing.
.
First evaluation of application concepts in the field of electricity generation, cogeneration of electricity, and process steam and tertiary oil recovery.
of
research and development as well as training programs.
A period of about 1 year is assumed for completion of this phase.
162
DAZHOUG WANG et al
4 aJ
163
Current status and plans for the HTGR
Fig.
2.
Cross
section
of
the
primary
of
circuit
1 _@
the
teat
module.
.,,o,v
l-z?-
Fig.
3.
Heat
flow
diagram
-
district
heating
and
power
generation.
DALHONGWANG et al
164
COOPERATICN
PHASES I
111
rCn* -
.N,
,,,,,m .,/,#_
*InmoN . RYISt . OUY 1RIvM
1:
I:
wm
STEAMCEwEnAlon
WlTNSTEW IKFQIVtR
I
1
I
Fig. 4. Overall time schedule test module China.
m
El Q 0
Fig. 5. Production schedule at Shanjasi.
steam Sook Steam
DriveCmv Steam Drive WTR Wotef llooding
165
Currentstatus and plansfor the HTGR
APPLICATION STUDY OF HTR IN HEAVY OIL RECOVERY AND CHEMICAL INDUSTRY 3. Since the beginning of the 8Os, The heavy oil reserve is relatively rich in China. heavy oil recovery by injection steam had been developed in several oil fields in But conventional thermal recovery of order to increase the crude oil production. heavy oil needs a great quantity of high temperature steam at high pressure. About 30% to 40% of the produced crude oil would be consumed to supply these amounts of the injecting steam with a In some pilot areas of thermal recovery, injecting steam. temperature of 355'C and pressure of 170 bar is produced from the small oil-fired of oil-fired boilers can save a great amount boilers. Therefore, using HTR instead of crude oil. For the investigations on the use of the HTR in heavy oil recovery, the Shanjasi section of Shengli oil field has been selected to serve as a reference case for this The initial OIP in Shanjasi section is 66 x lo6 tons. The exploration for study. oil is not finished and 100 x lo6 tons of OIP is expected. The crude oil is very heavy and does not flow at reservoir conditions. Therefore, the heavy oil has been extracted by the steam-soak process since October 1984. The production planning aims at an output of one million tons heavy oil per year with subsequent upgrading in a special refinery. The main
aims
of
the
application
.
The physical properties steam injection, i.e.,
.
The nuclear steam fired boilers.
is
of oil
study
are
the Shanjasi recovery by
economic
compared
to
find
out
reservoir steam drive to
whether: are suited process.
conventional
steam
for
a continuous
generated
by oil-
The evaluation of the physical properties of Shenjasi reservoir with respect to the steam drive process was a major effort of the study. For calculation of the reservoir properties a numerical simulation computer code (NUMSIP model) has been developed by INET. Based on the results of calculation and evaluation, an option of using two HTRs with total thermal output of 400 MW for steam and electricity generation was proposed.
As shown in Fig. 5 the oil production capacity of one million tons per year (about 20,000 bblld) may last up to 13 years with steam soak and partly steam drive. Then steam soak will decrease and the production by steam drive will be maintained for another 20 years. This means in total a duration of about 33 years with a nearly continuous oil production of 0.5 million tons per year. According to preliminary investigations a ratio of four tons steam to one ton oil can be expected. With this boundary condition a steam production of about two million tons per year (about 6000 t/d - 250 t/h) is needed. This steam amount can be generated by one HTR-module with a capacity of 200 MU thermal. Another HTR-module is necessary for electricity generation to meet the electricity demand in the oil-field area. Therefore, 2 x HTR-module plant is proposed as an energy source for the Shanjasi heavy oil-field. Figure 6 represents the flow scheme for such 2 x HTR-module plant. It is proposed to interconnect the feedwaterlsteam circuits of both HTR-modules to get a cogeneration plant generating injection steam for heavy oil recovery and elecgenerates about 77 kg/s live tricity for the Shengli grid. Each steam generator From there the steam steam with a pressure of 190 bar and temperature of 53O’C. The electrical output is about to injection wells and the turbine. steam leaving the turbine at different extractions is partly used for the (with preheaters to form a part of the feedwater. The other part of the feedwater 70 kg/s) is fed from outside via a water treatment station. is distributed 75 MW. The
The economic assessment is performed on the basis of the dynamic cost calculation. The most important results of this application study are as follows: .
Recoverable oil by steam drive using HTR nuclear steam supply system: imately 15 million tons in the total period of about 30 years.
.
Average oil year.
production
by
steam
drive:
approximately
0.5
million
tons
approx-
per
DAZHONG WANG et al
77 kg/s vm Guwafu
185 bar, 530 Oc iS4 kg/s
-w-c 70 kg/s 13-i kg/s
HTR-2 module
site
plan
and flow
scheme of
power
and steam
cogeneration.
Currentstatus and plansfortheHTGR
.
Additionally recoverable oil due approximately 4 million tons (25
to x
167
oil substitution by nuclear energy: lo6 bbl).
.
75 MW(e) of electricity could be supplied to the Shengli-oil field grid. The electricity production amounts to 600 million kWh per year which is equivalent to an oil consumption of about 140,000 t/a.
.
Electricity generated by the HTR-module plant will have nearly the same price (levelized cost) as generated by an oil-fired power plant.
The application study of the use HTR in heavy oil recovery has been carried out jointly by INET, Beijing and KFA, Juelich, and supported by Shengli oil field company on the Chinese side and by Siemens KWU/Interatom on the German side. It is well understood that the Shanjasi HTR application study is a preliminary evaluation of the technical and economical possibilities. But it can be regarded as an example, and other heavy oil fields with similar properties may also be potential candidates for the HTR application project. A similar investigation has also been carried out for use of the HTR in the chemical industry. The Yangshan Petrochemical Corporation located in the South-West of Beijing is selected as a reference user for this study. The total requirement of steam at different pressure and temperature ranges is approximately 730 t/h in summer and 1650 t/h in winter. The total annual consumption of electricity is about one billion KWh, which should be partly supplied from cogeneration power plants. A four-module HTR cogeneration plant with thermal power output 800 MW and a two-module HTGR-100 cogeneration plant with a thermal power output of 500 MW have been proposed by the joint application study between Chinese and German institutes and reactor companies. More detailed economic and safety studies for the applications of HTR in the chemical industry will be continued.
&wgy Vol. 16. No. l/2, pp. 159-167, 1991 Printed inGreat Britain
PRESENT STATUS OF RESEARCH AND DEVELOPMENT FOR HTR IN CHINA
DAZHONG WANG, DAXIN ZHONG,
and YUANKUI XU
Institute of Nuclear Energy Technology, Tsinghau University, Beijing, P. R. China
Abstract - The HTR R&D project is being carried out in the rele_--vant institutions in China. The topics covered include fuel element technology, graphite development, fuel element handling system, helium technology, fuel reprocessing technology, as well as HTR design study. Some results of the HTR research studies are described. In addition, a test facility for the investigation of HTR Module reactor safety and the process heat applications of HTR is under construction in a joint project to build a 10 MW test HTR with Siemens-Interatom, KFA Juelich, and INET. The conceptual design of a 10 MW test HTR has been completed by the joint group. In parallel the application study of HTR Module is being carried out for the oil industry and the petrochemical industry, as well as for power generation. Some preliminary results of the application study include heavy oil recovery in the Shengli oil field and process heat application at the Yan Shan Petroleum Company. 1. THE STATUS OF HTR PROGRAM The research and development program of HTGR in China began in the mid-1970s. In the first phase beginning from 1974 , the target was to design and construct a 100 MW(t) HTGR thorium thermal breeder with two-zone pebble bed core. In parallel with the design work of the reactor, a series of research studies for HTGR development were carried out which included the manufacture of fuel kernels, coated particles and several kinds of spherical fuel elements, the characterization of graphite, the prestressed concrete reactor vessel technology and the HTGR components development such as the graphite core structure , the control rod and its drive, charge and discharge of spherical fuel, helium circulator, and the steam generator. In addition, the reprocessing technology of thorium fuels is under development. But the HTGR breeder project was stopped at the end of 1970 due to various reasons, mainly the financial problem. The second phase of HTGR research and development program was in the period of the 5 year plan (1981 to 1985). The State Science and Technology Connnission gave support to continue some basic technology development and to investigate the possibilities of nuclear process steam and heat for industry application. The work was concentrated in certain areas:
.
To continue the coated particle fuel technology development and to some laboratory facilities.
.
To investigate the HTR module concept design and to develop design tools, e.g., the computer codes for physics, thermohydraulics, and safety analysis.
.
Investigation of the application possibilities of HTGR for heavy oil recovery, chemical industry, refinery, oil-shale retorting, and coal gasification.
improve
The present research and development program on HTGR (third phase) is covered in the high technology research and development program, as part of the development of nuclear energy in the next century in China. It is important to develop the advanced
DAZHONGWANG et al
160
reactors which have inherent safety, economical viability, and high fuel utilization. The high-temperature gas-cooled reactor (HTGR) is one of these advanced reactors to be selected to carry out research and development work for future applications. The main topics of this program include: .
HTR fuel technology development, preparation and manufacture of fuel kernels, coated particles and fuel elements on a laboratory scale, characterization and qualification as well as the irradiation testing of coated particles and fuel elements,
.
Graphite,
.
Helium
.
Charging
and
discharging
.
Research technique.
work
on the
.
Application
metallic, technology
study
and and
of
ceramic
materials
components
development.
technique
for
thorium-uranium
the
Modular
development.
spherical fuel
HTR for
cycle
fuel
elements.
and HTR fuel
different
potential
reprocessing
users.
For management and coordination of the HTR research and development program a special unit was established. The institutions which take part in this program are the Institute of Nuclear Energy Technology (INET), Beijing Institute of Nuclear Engineering (BINE), South-West Center of Reactor Research (SWCR), and Shanghai Institute of Nuclear Research (SINR) and others. The aims of this program are to research and develop the key technologies and to investigate the possibility of constructing a demonstration Modular HTR plant. THE 10 MW HTR TEST MODULE CONCEPT 2. In order to introduce and develop the Modular HTR technique in practice, a joint project was started on construction of a 10 MW HTR test module, with collaboration CmbH, and the Nuclear among the INET of Tsinghua University PRC, Siemens-Interatom The 10 MW test module will be constructed at the Research Center Juelich (KFA) FRG. site of INET located in the north-west of Beijing. The main object of the test module is to verify and demonstrate the unique features of Modular HTR at a nuclear test facility. Therefore, the test module have been defined jointly as follows:
relevant the aims
and for
.
The test module will be designed for a wide range of possible applications, e.g., electricity, steam and district heat generation in the first operation phase, and process heat generation and methane reforming in the second phase.
.
The relevant components can be e.g., graphite core structure, handling facility.
.
Verification of the inherent tive temperature coefficient passive decay heat removal, ingress.
.
The test module is capable of withstanding extremely so that fuel element mass-test could be carried out conditions at temperatures up to 1600°C.
tested steam
and proven under helium generator,
nominal blower,
safety features of the HTR-Module such as negatemperature limitation due to of reactivity, and limitation of power excursion due to water
high under
core temperatures, nominal reactor
The conceptual design of the 10 MW test module was carried out jointly The main data of the test module are as follows: and INET in 1988. Maximum thermal power Average thermal power Primary helium pressure Helium temperature Secondary steam pressure Live steam temperature Power density
conditions, and the fuel
20 MW 10 MW 30 bar 250’ and 35 bar 43s”c 2 MU/m3
7OO’C
by
Interatom
Current statusand piansfor the HTGR Core diameter Average core height Height/diameter radio Number of fuel elements Heavy metal content Average burnup Fuel element in-core time Loading scheme
161
190 cm 176 cm 0.93 27,000 5 g/fuel element 80,000 Mu(t) 1078 EFPD OTTO
Figures 1 and 2 show the cross sections of the reactor and the the test module. It has the following important design features.
primary
circuit
of
The reactor core and steam generator are housed in two separate steel vessels and positioned side-by-side in a staggered arrangement. The graphite cylinder core which holds the pebble bed has a diameter of 1900 mm and a height of approximately 2200 sun. This is adequate for the required volume of the active core which amounts to 5 m3. The new fuel elements are charged from the top of the core via five charging tubes. The fuel elements are removed from the core-bottom via a fuel element discharge tube with an inner diameter 500 mm. Decay heat is removable by surface coolers outside the reactor vessel. The surface cooler system is subdivided into two trains. It is sufficient to dissipate decay heat by means of passive heat transfer mechanisms to the simple surface coolers. The primary helium pressure of 30 bar is chosen. The inlet and outlet temperatures of the core are 250’ and 7OO’C. A secondary pressure of 35 bar and a live steam temperature of 435’C are chosen SO that the small standard industrial turbines can be used. The average thermal power of the test module plant is set to be IO MJ. In order to enhance the experimental flexibility the maximum thermal power output is set to be 20 MW. Some variants of the secondary heat sink have been evaluated. Figure 3 shows the heat flow diagram for district heating and electricity generation with the maximum thermal power of 20 MW. The respective figures for the normal operation case (10 MU) are given in brackets. The basic
data
of
the
steam
generator
Helium flow (shell side) Helium pressure Helium temperature Water/steam flow (tube side) Water/steam pressure Water/steam temperature Steam generation rate
are: 8.6 (4.3) kg/s 30 bar 250’ and 7OO’C 7.5 (3.75) kgls 40 to 35 bar 150° to 435oc 27 (13.5) t/h
Figure 4 shows the time schedule of the whole cooperation program. The 10 Mu test module will take 5 years for design, construction, installation, and connrissioning. The basic design will be performed jointly after this project is approved by both the Chinese and German governments. Major .
topics
during
the
basic
design
phase
are:
Design of the test module with the aim of preparing adequate documents for the preliminary safety analysis report.
.
Start
.
Cost review for the test module program with special emphasis on the definition of the local/import sharing.
.
First evaluation of application concepts in the field of electricity generation, cogeneration of electricity, and process steam and tertiary oil recovery.
of
research and development as well as training programs.
A period of about 1 year is assumed for completion of this phase.
162
DAZHOUG WANG et al
4 aJ
163
Current status and plans for the HTGR
Fig.
2.
Cross
section
of
the
primary
of
circuit
1 _@
the
teat
module.
.,,o,v
l-z?-
Fig.
3.
Heat
flow
diagram
-
district
heating
and
power
generation.
DALHONGWANG et al
164
COOPERATICN
PHASES I
111
rCn* -
.N,
,,,,,m .,/,#_
*InmoN . RYISt . OUY 1RIvM
1:
I:
wm
STEAMCEwEnAlon
WlTNSTEW IKFQIVtR
I
1
I
Fig. 4. Overall time schedule test module China.
m
El Q 0
Fig. 5. Production schedule at Shanjasi.
steam Sook Steam
DriveCmv Steam Drive WTR Wotef llooding
165
Currentstatus and plansfor the HTGR
APPLICATION STUDY OF HTR IN HEAVY OIL RECOVERY AND CHEMICAL INDUSTRY 3. Since the beginning of the 8Os, The heavy oil reserve is relatively rich in China. heavy oil recovery by injection steam had been developed in several oil fields in But conventional thermal recovery of order to increase the crude oil production. heavy oil needs a great quantity of high temperature steam at high pressure. About 30% to 40% of the produced crude oil would be consumed to supply these amounts of the injecting steam with a In some pilot areas of thermal recovery, injecting steam. temperature of 355'C and pressure of 170 bar is produced from the small oil-fired of oil-fired boilers can save a great amount boilers. Therefore, using HTR instead of crude oil. For the investigations on the use of the HTR in heavy oil recovery, the Shanjasi section of Shengli oil field has been selected to serve as a reference case for this The initial OIP in Shanjasi section is 66 x lo6 tons. The exploration for study. oil is not finished and 100 x lo6 tons of OIP is expected. The crude oil is very heavy and does not flow at reservoir conditions. Therefore, the heavy oil has been extracted by the steam-soak process since October 1984. The production planning aims at an output of one million tons heavy oil per year with subsequent upgrading in a special refinery. The main
aims
of
the
application
.
The physical properties steam injection, i.e.,
.
The nuclear steam fired boilers.
is
of oil
study
are
the Shanjasi recovery by
economic
compared
to
find
out
reservoir steam drive to
whether: are suited process.
conventional
steam
for
a continuous
generated
by oil-
The evaluation of the physical properties of Shenjasi reservoir with respect to the steam drive process was a major effort of the study. For calculation of the reservoir properties a numerical simulation computer code (NUMSIP model) has been developed by INET. Based on the results of calculation and evaluation, an option of using two HTRs with total thermal output of 400 MW for steam and electricity generation was proposed.
As shown in Fig. 5 the oil production capacity of one million tons per year (about 20,000 bblld) may last up to 13 years with steam soak and partly steam drive. Then steam soak will decrease and the production by steam drive will be maintained for another 20 years. This means in total a duration of about 33 years with a nearly continuous oil production of 0.5 million tons per year. According to preliminary investigations a ratio of four tons steam to one ton oil can be expected. With this boundary condition a steam production of about two million tons per year (about 6000 t/d - 250 t/h) is needed. This steam amount can be generated by one HTR-module with a capacity of 200 MU thermal. Another HTR-module is necessary for electricity generation to meet the electricity demand in the oil-field area. Therefore, 2 x HTR-module plant is proposed as an energy source for the Shanjasi heavy oil-field. Figure 6 represents the flow scheme for such 2 x HTR-module plant. It is proposed to interconnect the feedwaterlsteam circuits of both HTR-modules to get a cogeneration plant generating injection steam for heavy oil recovery and elecgenerates about 77 kg/s live tricity for the Shengli grid. Each steam generator From there the steam steam with a pressure of 190 bar and temperature of 53O’C. The electrical output is about to injection wells and the turbine. steam leaving the turbine at different extractions is partly used for the (with preheaters to form a part of the feedwater. The other part of the feedwater 70 kg/s) is fed from outside via a water treatment station. is distributed 75 MW. The
The economic assessment is performed on the basis of the dynamic cost calculation. The most important results of this application study are as follows: .
Recoverable oil by steam drive using HTR nuclear steam supply system: imately 15 million tons in the total period of about 30 years.
.
Average oil year.
production
by
steam
drive:
approximately
0.5
million
tons
approx-
per
DAZHONG WANG et al
77 kg/s vm Guwafu
185 bar, 530 Oc iS4 kg/s
-w-c 70 kg/s 13-i kg/s
HTR-2 module
site
plan
and flow
scheme of
power
and steam
cogeneration.
Currentstatus and plansfortheHTGR
.
Additionally recoverable oil due approximately 4 million tons (25
to x
167
oil substitution by nuclear energy: lo6 bbl).
.
75 MW(e) of electricity could be supplied to the Shengli-oil field grid. The electricity production amounts to 600 million kWh per year which is equivalent to an oil consumption of about 140,000 t/a.
.
Electricity generated by the HTR-module plant will have nearly the same price (levelized cost) as generated by an oil-fired power plant.
The application study of the use HTR in heavy oil recovery has been carried out jointly by INET, Beijing and KFA, Juelich, and supported by Shengli oil field company on the Chinese side and by Siemens KWU/Interatom on the German side. It is well understood that the Shanjasi HTR application study is a preliminary evaluation of the technical and economical possibilities. But it can be regarded as an example, and other heavy oil fields with similar properties may also be potential candidates for the HTR application project. A similar investigation has also been carried out for use of the HTR in the chemical industry. The Yangshan Petrochemical Corporation located in the South-West of Beijing is selected as a reference user for this study. The total requirement of steam at different pressure and temperature ranges is approximately 730 t/h in summer and 1650 t/h in winter. The total annual consumption of electricity is about one billion KWh, which should be partly supplied from cogeneration power plants. A four-module HTR cogeneration plant with thermal power output 800 MW and a two-module HTGR-100 cogeneration plant with a thermal power output of 500 MW have been proposed by the joint application study between Chinese and German institutes and reactor companies. More detailed economic and safety studies for the applications of HTR in the chemical industry will be continued.