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Research Reactors: Apsara,Cirus,Kamini,Purnima I,Purnima II,Purnima III and Zerlina
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  • Purnima III
  • Zerlina
Dhruva and Cirus

Apsara Reactor at BARC

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Dhruva & Cirus Reactors

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APSARA REACTOR

ApsaraApsara

 
     
 

No.

Item

Description

1

Reactor Type 

Swimming pool type/ Thermal Reactor

2

Date of Criticality 

August 4,1956

3

Reactor Power (Th)

1 MW (Maximum)

4

Fuel Material

Enriched uranium -aluminium alloy

5

Fuel Element

Plates

6

Fuel Cladding

Aluminium alloy

7

Total weight of Fuel

4.5 kg 

8

Core Size

560 mm X 560 mm X 615 mm(H) 

9

Max Neutron Flux 

1013n/cm2/sec

10

Moderator

Light water

11

Coolant

Light water

12

Shut off Rods

Cadmium

13

Uses

Production of isotopes; basic research; shielding experiments; neutron activation analysis; neutron radiography; testing of neutron detectors

The Reactor was permanently shutdown in 2010.

Upgraded 2 MWth Reactor with LEU fuel is under construction
.

 
 
 
     
 

CIRUS REACTOR


CIRUS Research Reactor
 
 

The CIRUS reactor was commissioned on 10th July 1960. It was built in collaboration with Canada under the leadership of Dr. Homi Jahangir Bhabha. This reactor was extensively used for condensed matter research, using neutron beams extracted from its core. The reactor was also extensively used for material irradiation, fuel testing, neutron activation analysis and production of radioisotopes for application in the fields of medicine, agriculture and industry. CIRUS reactor proved to be an excellent platform for training of engineers and scientists and in understanding the intricacies of managing natural uranium, heavy water, reactor systems which eventually evolved into the Indian pressurized heavy water reactor programme. After 50 years of successful operation, it was decided to permanently shut-down the reactor in December 2010.

 
     
 

No.

Item

Description

1

Reactor Type 

Vertical Tank Type / Thermal Reactor

2

Date of Criticality 

July 10,1960

3

Reactor Power (Th)

40 MW (Maximum)

4

Fuel Material

Natural Uranium Metal

5

Fuel Element

Rods

6

Fuel Cladding

Aluminium

7

Total weight of Fuel

10.5 T

8

Core Size

2.67m (D) X 3.14m(H)

9

Max Neutron Flux

6.5x1013n/cm2/sec

10

Moderator

Heavy water

11

Coolant

Light water

12

Shut off Rods

Boron Cadmium

13

Uses

Production of isotopes ; R & D in reactor technology; manpower training; neutron beam research; neutron activation analysis; development and testing of fuel assemblies; testing of neutron detectors

The Reactor was permanently shutdown on 31.12.2010.

 
 
 
     
 

DHRUVA REACTOR


DHRUVA Research reactor
 
 

During early 1970s a strong need was felt for building a research reactor with higher neutron flux to meet the growing demand of radioisotopes and advanced research in basic sciences. This led to the setting up of a research reactor at BARC which was named Dhruva by Dr. Giani Zail Singh, the then President of India. Construction of DHRUVA was an important milestone in the development and implementation of indigenous nuclear technology in India. The reactor incorporates several features catering to the requirements of a broad-based multidisciplinary user community as also in the production of radioisotopes of high specific activity. Dhruva has been declared as a National Facility for Neutron Beam Research to cater to the needs of Indian scientific community where scientists from BARC, other units of the Department of Atomic Energy (DAE), universities and national laboratories work under collaborative projects. Many of the collaborations are supported by the University Grants Commission – DAE Consortium for Scientific Research (UGC-DAE-CSR), the Board of Research in Nuclear Sciences (BRNS) and other agencies. At present there are about 40 active projects running under the UGC-DAE-CSR scheme.

 
     
 

No.

Item

Description

1

Reactor Type 

Vertical Tank Type / Thermal Reactor

2

Date of Criticality 

August 8,1985

3

Reactor Power

100 MW (Maximum)

4

Fuel Material

Natural Uranium Metal

5

Fuel Element

Clusters

6

Fuel Cladding

Aluminium

7

Total weight of Fuel

6.35 T

8

Core Size

3.72m(D) x 3.87m(H)

9

Max Neutron Flux 

1.8x1014n/cm2/sec

10

Moderator

Heavy water

11

Coolant

Heavy water

12

Shut off Rods

Cadmium

13

Uses

Basic research; isotope production; manpower training; neutron activation analysis; testing of neutron detectors

 
 
 
     
 

KAMINI - REACTOR

 
     
 

No.

Item

Description

1

Nature  of Reactor  system

Vertical Tank Type / Thermal Reactor

2

Date of Criticality 

October 29,1996

3

Reactor Power (Th)

30 KW (Nominal)

4

Fuel Material

U-233-Al alloy

5

Fuel Elements

Plates

6

Fuel Cladding

Aluminium

7

Total fuel inventory

600 g

8

Core size

204 mm X 204 mm X 275 mm (H)

9

Total fuel inventory

600 g

10

Max Neutron Flux

~1013n/cm2/sec

11

Moderator/Coolant/Shield material

Light water

12

Core Cooling mode Natural convection

13

Control elements Cadmium plates

14

Users

Neutron radiography; calibration of detectors; material characterization; shielding experiments; irradiation studies on samples

 
 
 
     
 

PURNIMA - I REACTOR

 
     
 

No.

Item

Description

1

Reactor Type 

Fast Reactor

2

Date of Criticality 

May 18 , 1972

3

Reactor Power (Th)

1 W (Nominal) 

4

Fuel Material

Plutonium  oxide

5

Fuel Element

Pellets

6

Fuel Cladding

Stainless Steel 

7

Total weight of Fuel

21.6 kg

8

Core Size

180 mm(D) X 180 mm(H)

9

Max Neutron Flux 

~108n/cm2/sec

10

Moderator

None

11

Coolant

Air

12

Shut off Rods

Molybdenum

13

Uses

Fast reactor physics studies

14

Year of decommissioning

1973

 
 
 
     
 

PURNIMA - II REACTOR

 
     
 

No.

Item

Description

1

Reactor Type 

Vertical Tank Type / Thermal Reactor

2

Date of Criticality 

May 10,1984

3

Reactor Power (Th)

100 mW (Nominal) 

4

Fuel Material

Uranium-233 

5

Fuel Element

Uranyl Nitrate Solution

6

Fuel Cladding

None 

7

Total weight of Fuel

400 g

8

Core Size

148 mm(D) X (250-400) cm(H)

9

Max Neutron Flux 

107n/cm2/sec

10

Moderator

Light water

11

Coolant

Light water

12

Shut off Devices

Cadmium

13

Control Rods

Boron carbide

14

Uses

U-233 fuel studies; futuristic reactor evaluation 

15

Year of decommissioning

1986

 

 
 
 
     
 

PURNIMA - III REACTOR

 
     
 

No.

Item

Description

1

Reactor Type 

Vertical Tank Type / Thermal Reactor

2

Date of Criticality 

November 9,1990

3

Reactor Power (Th)

1 W (Maximum) 

4

Fuel Material

Uranium-233-aluminium alloy

5

Fuel Element

Plates

6

Fuel Cladding

Aluminium 

7

Total weight of Fuel

600 g

8

Core Size

204 mm X 204 mm X 275 mm (H)

9

Reflector material

Berillium oxide

10

Max Neutron Flux

~108n/cm2/sec

11

Moderator

Light water

12

Coolant

Light water

13

Control Elements

Cadmium plates

14

Uses

Mockup studies for Kamini reactor

15

Year of decommissioning

1991

 
 
 
     
 

ZERLINA REACTOR

 
     
 

No.

Item

Description

1

Reactor Type 

Vertical Tank Type / Thermal 

2

Date of Criticality 

January 14,1961

3

Reactor Power (Th)

100 W (Nominal) 

4

Fuel Material

Natural Uranium Metal

5

Fuel Element

Rods

6

Fuel Cladding

Aluminium

7

Total weight of Fuel

Variable(3.7 T in the first core) 

8

Core Size

2.29m (D) X 4.35m(H)

9

Max Neutron Flux 

0.5x108n/cm2/sec

10

Moderator

Heavy water 

11

Coolant

Heavy water

12

Shut off Rods

Cadmium

13

Uses

Reactor Lattice studies

14

Year of decommissioning

1983

 
 
 
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