Pakistan Atomic Research Reactor

Pakistan Atomic Research Reactor
The PARR-I is similar to North Carolina State University's Pulstar Nuclear Reactor
Location of Pakistan Atomic Research Reactor
Operating Institution	Pakistan Institute of Nuclear Science and Technology (PINSTECH)
Location	Nilore, Islamabad, Pakistan
Coordinates
Type	Pool-type reactor Materials Test Reactor Miniature neutron source reactor (MNSR) SLOWPOKE reactor
Power	10 MW (PARR-I) 30 Kw (PARR-II) 15MW (PARR-III) (Thermal-nuetron)
Construction and Upkeep
Construction Cost	Unknown
Construction Began	8 July 1965 (1965-07-08)
Time to Construct	5 months
First Criticality	21 December 1965 (1965-12-21)
Shutdown date	N/A
Decommission date	N/A
Staff	Classified
Operators	Classified
Refuel Frequency	N/A
Technical Specifications
Max Thermal Flux	1.05E+13 n/cm^2-s
Max Fast Flux	1.70E+14 n/cm^2-s
Cooling	light water
Neutron Moderator	light water
Neutron Reflector	heavy water, graphite, beryllium
Control Rods	8 Rods
Cladding Material	Aluminium Alloy

The Pakistan Atomic Research Reactor or (PARR) are three nuclear research reactors and two other experimental neutron sources located in the PINSTECH Laboratory, Nilore, Islamabad, Pakistan.

The first nuclear reactor was supplied and financially constructed by the Government of United States of America in the mid 1960s. The other two reactors are built and supplied by Pakistan Atomic Energy Commission (PAEC) in the 1970s and 1980s, respectively. Supervised by the United States and International Atomic Energy Agency (IAEA), the first two reactors are subject to IAEA safeguards and its inspections.

History of PARR-Reactors

See also: Pakistan Institute of Nuclear Science and Technology

The PARR-I Reactor was supplied by the United States government in 1965 under the Atoms for Peace program. The PINSTECH institute was designed by American architect Edward Durrell Stone, when noted Pakistani scientists, Abdus Salam and Ishrat Hussain Usmani traveled to the United States of America in the early 1960s. The first reactor was supplied by the American Machine and Foundry as its contractors, and the first reactor was built by the American nuclear engineer Peter Karter.

In the first stage, reactor building and ancillary facilities were completed with the reactor becoming critical on 21 December 1965. The second stage, consisting of various laboratories, workshop, library and auditorium, became operational in 1974. The facility was last upgraded by PAEC chairman and noted nuclear scientist, Mr. Munir Ahmad Khan in 1989.

PARR-I Reactor

The PARR-I Reactor was the first reactor that was supplied by American Machine and Foundry. Peter Karter had personally supervised the construction of the reactor. The PARR-I is a swimming pool-type and Materials Test Reactor (MTR) type research reactor. Originally based on a design to utilize the Highly Enriched Uranium (HEU) fuel, the HEU fuel utilize the ~93% enriched in ²³⁵U at a power level of 5 MW. The first reactor went critical on December 21, 1965 under the supervision of Abdus Salam, Hafeez Qureshi, Samar Mubarakmand, Naeem Ahmad Khan and Dr. Hameed Ahmad Khan.

The PARR-I Reactor attained its full power on June 22, 1966. In PARR-I, it is virtually impossible to adopt secure the fresh supplies of the HEU fuel. However, to ensure the continuity of the nuclear fuel, PARR-I was converted to utilize the ~20% Low-Enriched Uranium (LEU) from the ²³⁵U in October 1991 The nuclear fuel conversion program was led by the PAEC chairman Mr. Munir Ahmad Khan. The PAEC chairman Munir Ahmad Khan also upgraded the reactor's power level from 5 MW to 10 MW.

The program was carried out in order to meet demands of higher neutron fluxes for experimental research purposes and the isotope production. The upgraded reactor was also made available to compensate for the decrease in neutron flux due to higher concentration of ²³⁸U in the LEU fuel as compared to the HEU fuel. The reactor was made critical on October 31, 1991 under the supervision of dr. Ansar Pervaiz and dr. Iqbal Hussain Qureshi, and attained power level of 10 MW on May 7, 1992. The core configuration attained its equilibrium configuration in February 1995.

PARR-II Reactor

The PARR-II Reactor is an indigenously designed and constructed reactor owned by the Pakistan Atomic Energy Commission. The PARR-II Reactor's design is similar to Miniature neutron source reactor (MNSR) and SLOWPOKE reactor. The reactor was indigenously designed by the PAEC as the chairman Munir Ahmad Khan and his team of engineers and scientists also led the construction of the reactor. The PARR-II Reactor had gone critical and began operating on January 21, 1974. The PARR-II Reactor is a tank-in-pool reactor with a rated power of 27-30 kW. Same as the first reactor, the reactor is design to utilize the High Enrich Uranium (HEU) fuel. The HEU fuel utilize the ~90% ²³⁵U at a power level of 30 kW. The demineralized light water is used as a coolant moderator and the reactor core is reflected by metallic Be⁴.

A PARR-II consists of a core reactor, control rod, and nuclear reflectors, and it is enclosed in a water-tight cylindrical Al¹³ alloy vessel. The nuclear reactor core is an under-moderated aray with ¹H to ²³⁵U ratio of temperature of 20 °C and provides a strong Negative temperature coefficient and thermal volume coefficients of reactivity. The PAEC scientists and engineers also built and constructed the nuclear accelerator on April 9, 1989. The particle accelerator is heavily used to conduct research in nuclear technology.

New Labs

Unlike the PARR-I and PARR-II the New Labs is not subject to IAEA inspections. and is completely different from its parent reactors. It is a plutonium-fuel and reprocessing plant and works as a pilot ⁹⁴Pu reprocessing reactor with a capability to utilize the ~7% ²³⁹Pu, to handle the isotopes and utilize the ⁸⁶Kr emissions and radiation. It is also a reprocessing reactor to change <~7% ²³⁹Pu into <~7% weapon-grade ²⁴⁰Pu fuel. New Labs were designed and constructed indigenously by Pakistan Atomic Energy Commission (PAEC) under its Chairman Munir Ahmad Khan whereas it project-director was a mechanical engineer, Chaudhry Abdul Majeed. The construction of the facility was led by NESPAK.

In the 1960s, the British Nuclear Fuels (BNFL) contracted the project with PAEC, and the French's Saint-Gobain Techniques Nouvelles (SGN). The PAEC engineers and scientists led the initial designing for a large-scale reprocessing plant, one with a capacity of 100 tons of fuel per year. While the BNFL and SGN provided funds, technical assistance, and nuclear fuel. However, after the India's Operation Smiling Buddha, a nuclear test, both British and French consumer companies immediately canceled the project with PAEC. The scientists and engineers re-designed the reprocessing plant, this time completely different from first design. According to its scientists, the project was highly ambitious and larger than the original plan.

The plant was completed in 1981 and cold reprocessing tests for producing plutonium took place at New Labs in 1986. The New Labs came into limelight when Pakistan had secretly tested its plutonium weapon-based nuclear device in Kirana Hills. On May 30, 1999, the PAEC scientists, under renowned nuclear physicist Dr. Samar Mubarakmand, had tested a miniaturized nuclear device that is believed to be a Plutonium devices for which plutonium was most likely reprocessed by the Pakistani scientists into weapon-grade at the New Labs. The test yield of a nuclear devices was reported to be 12-40 kt.

Charged Particle Accelerator

In early 1983, Pakistani nuclear physicist dr. Samar Mubarakmand developed and established a neutron particle and nuclear accelerator to conduct the research of explosions of nuclear elements and isotopes in a nuclear device. Known as a Charged Particle Accelerator (CPA), the nuclear accelerator is a 250 keV Ion accelerator which can deliver all Gaseous ions such as ⁺H, ⁺N, ⁺O, ⁺He, ⁺Ne, ⁺Ar, ⁺Kr, ⁺Xe or molecular ions. The accelerator's energy range is highly flexible and ions between 50 to 250 keV can be delivered to a target of dimensions ranging from few mm to many cm.

The particle facility is designed to implantation of ⁴²⁺Mo,⁵¹⁺Sn, and⁴⁶⁺Pb ions into steel, friction can be reduced by up to ~50%. During the process of ion implanatation, the oxidation is inhibited by suitable ions such as ⁵⁺B,²⁰⁺Ca into metals. The PINSTECH accelerator can be used by mutual arrangement between PINSTECH and industry or any other organizations.

Fast-Neutron Generator

See also: D-T reaction

In 1961, the United States Government led the establishment of ICF-based Fusion power experimental source near at Nilore, before the establishment of PINSTECH Institute. The neutron generator was bought by the PAEC from Texas A&M Nuclear Science Center. The facility is capable of producing mono-energetic neutrons at 3.5-14.7MeV from deuterium-tritium reaction generated by the Fusion power. This fusion experimental devices has capability to capture the low neutron flux on the order of 10⁵ to 10⁸ neutrons per cm² per second, resulting in nucleosynthesis by the s-process (slow-neutron-capture-process). It is designed and planned to do fast neutron activation for elements such as oxygen and nitrogen as well as some rare earth isotopes.

External links

• PARR Reactors
• PARR-I
• PARR-II
• PARR Nuclear Reactors