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CIRUS reactor

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Article Genealogy
Parent: Atoms for Peace Hop 4
Expansion Funnel Raw 48 → Dedup 14 → NER 2 → Enqueued 2
1. Extracted48
2. After dedup14 (None)
3. After NER2 (None)
Rejected: 12 (not NE: 12)
4. Enqueued2 (None)
CIRUS reactor
NameCIRUS reactor
LocationBhabha Atomic Research Centre, Trombay
StatusDecommissioned
Construction began1955
Commission date1960
Decommission date2010
OwnerDepartment of Atomic Energy
OperatorBhabha Atomic Research Centre
Reactor typeResearch reactor
Power thermal40 MW

CIRUS reactor. The CIRUS reactor was a 40 MWth research reactor located at the Bhabha Atomic Research Centre in Trombay, India. It was a cornerstone of India's early nuclear research and plutonium production, playing a pivotal role in the nation's strategic program. The reactor's name was an acronym representing the collaborative effort behind its construction: Canada, India, Reactor, United States.

History and development

The genesis of the reactor stemmed from the Atoms for Peace initiative launched by U.S. President Dwight D. Eisenhower. Under this policy framework, an agreement was signed in 1956 between the Government of India, the Government of Canada, and the United States Atomic Energy Commission. The project was a significant example of international nuclear cooperation during the Cold War. The design was based on the Canadian National Research Experimental reactor, with Canada providing the heavy water moderator and the United States supplying the initial load of enriched uranium fuel under safeguards. Key Indian scientists like Homi J. Bhabha and Vikram Sarabhai were instrumental in negotiating the terms and overseeing the project's integration into India's nascent atomic energy establishment.

Design and specifications

CIRUS was a tank-type, thermal neutron reactor using natural uranium as fuel, heavy water as the moderator and primary coolant, and light water as a secondary coolant. Its core consisted of several hundred aluminum-clad fuel rods arranged in a calandria, a design principle shared with other reactors like the Douglas Point Generating Station. The reactor achieved a maximum thermal power output of 40 megawatts. It was equipped with multiple beam ports and irradiation facilities for producing radioisotopes for medicine and industry, and for conducting experiments in solid-state physics and nuclear chemistry. A key design feature was its ability to produce significant quantities of plutonium-239 by irradiating uranium-238 blankets placed around the core.

Operational history

The reactor achieved first criticality in 1960 and began full-power operation shortly thereafter. For decades, it served as a primary workhorse for India's civilian nuclear research program, supporting a wide array of scientific investigations. It was used extensively for neutron activation analysis, materials testing, and the production of isotopes such as iodine-131 and cobalt-60 for use in cancer therapy and industrial radiography. The reactor also provided crucial training for generations of Indian nuclear scientists and engineers. Its operations were managed by teams from the Bhabha Atomic Research Centre, contributing to the development of expertise that would later support India's larger power reactors like those at Tarapur Atomic Power Station and Rajasthan Atomic Power Station.

Role in India's nuclear program

The reactor's most historically significant role was in producing the plutonium used in India's first nuclear device, Smiling Buddha, tested in 1974 at the Pokhran Test Range. This event dramatically altered global perceptions of the Atoms for Peace program and led to major changes in international nuclear export controls, culminating in the creation of the Nuclear Suppliers Group. The use of plutonium from a reactor built with foreign assistance for a weapons test caused severe diplomatic friction with Canada and the United States, which subsequently cut off nuclear cooperation. Despite this, the reactor continued to operate for civilian purposes, and the experience gained from its operation directly informed the design and construction of India's first indigenous plutonium production reactor, Dhruva reactor, also located at Trombay.

Decommissioning and legacy

After fifty years of service, the reactor was permanently shut down in 2010. The decommissioning process, overseen by the Department of Atomic Energy, involves the safe removal of nuclear fuel, the draining and processing of heavy water, and the eventual dismantling of radioactive components. The legacy of the reactor is profoundly dual-purpose. It is remembered as a vital instrument for scientific advancement in India and a key contributor to the nation's strategic capabilities. Its history underscores the complexities of nuclear technology transfer and the thin line between peaceful and military applications, themes central to international agreements like the Treaty on the Non-Proliferation of Nuclear Weapons. The site remains an important part of India's nuclear history.

Category:Research reactors Category:Nuclear technology in India Category:Bhabha Atomic Research Centre