Consider the following statements regarding the specific challenges of the Thorium fuel cycle:
1. Thorium fuel cycles inevitably produce trace amounts of Uranium-232, which rapidly decays into daughter isotopes that emit intense, hard gamma radiation.
2. The intense hard gamma radiation emitting from Thorium spent fuel inherently makes it safer to process manually without heavy lead shielding.
3. Thorium dioxide possesses a significantly higher melting point and superior thermal conductivity compared to Uranium dioxide, offering distinct safety advantages.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 3 are correct. Statement 2 is incorrect: The hard gamma rays (specifically from Thallium-208, a decay product of U-232) make the fuel highly dangerous to handle, requiring heavy shielding and fully automated, remote processing facilities. (This paradoxically acts as a natural proliferation deterrent).
Consider the following statements regarding the physics and manufacturing of heavy water:
1. India's industrial heavy water plants, such as those at Manuguru and Thal, utilize distinct chemical exchange processes like the Hydrogen Sulphide-Water or Ammonia-Hydrogen exchange.
2. Heavy water (D2O) possesses a significantly lower boiling point and a lower density compared to ordinary light water (H2O).
3. The primary role of heavy water when acting as a moderator is to reduce the kinetic energy of neutrons without excessively absorbing them.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 3 are correct. Statement 2 is incorrect: Heavy water is denser than light water by roughly 11% (hence 'heavy') and has a slightly higher boiling point (101.4°C vs 100°C).
Consider the following statements regarding fuel recycling plants in India:
1. The Plutonium Plant at Trombay, commissioned in 1964, was India's first indigenous facility built to reprocess spent fuel and recover Plutonium.
2. The Power Reactor Fuel Reprocessing (PREFRE) facilities located at Tarapur and Kalpakkam treat spent fuel from commercial PHWRs to yield plutonium for the fast breeder program.
3. Reprocessing plants are a crucial mechanical linchpin in India's nuclear program, enabling the physical transition from the first stage to the second stage.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. Reprocessing closes the fuel cycle. The extraction of Plutonium-239 from Stage 1 thermal spent fuel provides the vital core inventory needed to start up Stage 2 breeder reactor systems.
Consider the following statements regarding isotopic enrichment physics:
1. The separation of Uranium-235 from Uranium-238 during enrichment is easily achieved by passing the raw solid ore through standard paper coffee filters.
2. India's gas centrifuge uranium enrichment facilities are completely open to the public and function as tourist landmarks in Central Delhi.
3. The Nuclear Suppliers Group explicitly mandates that all non-NPT states must enrich their domestic uranium to over 99% U-235 before using it in civilian power plants.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. Uranium enrichment is highly complex and requires gaseous processing (via uranium hexafluoride) inside high-speed centrifuges. Enrichment plants are top-secret strategic assets located away from public view (such as the Rare Materials Plant near Mysuru). Civilian power plants run on un-enriched (natural) or low-enriched uranium (~3-5%); 99% enrichment is weapons-grade and never used for basic civilian grids.
Consider the following statements regarding the fundamental nuclear materials used in India's program:
1. Natural uranium mined from the earth contains less than one percent of the fissile isotope Uranium-235.
2. When Thorium-232 captures a neutron inside a nuclear reactor, it eventually transmutes into the fissile isotope Uranium-233.
3. Plutonium-239 is virtually non-existent in nature and is artificially produced inside nuclear reactors from Uranium-238.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. Natural uranium is roughly 99.3% U-238 and only 0.7% U-235. Thorium-232 absorbs a neutron to become Th-233, which decays into Pa-233 and then fissile U-233. Pu-239 is a synthetic element created when U-238 absorbs a neutron.
Consider the following statements regarding Uranium enrichment and related technologies in India:
1. India's civilian nuclear power grid relies heavily on Highly Enriched Uranium (HEU) containing over 90% U-235 for standard electricity generation.
2. The Rare Materials Plant (RMP) at Rattehalli utilizes gaseous diffusion technology, which is considered highly modern and energy-efficient compared to gas centrifuges.
3. India is expressly forbidden by international treaty law from constructing domestic uranium enrichment facilities because it is a non-signatory to the NPT.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: Civilian reactors use Natural Uranium (0.7% U-235) or Low Enriched Uranium (LEU, ~3-5%). HEU is reserved for nuclear submarines and weapons. Statement 2 is incorrect: RMP utilizes gas centrifuges, which are far more modern and energy-efficient than obsolete gaseous diffusion plants. Statement 3 is incorrect: As a non-signatory to the NPT, India is not legally bound by its prohibitions and maintains indigenous enrichment capabilities.
Consider the following statements regarding basic atomic fission and fusion rules:
1. Nuclear fission and nuclear fusion are identical thermodynamic processes that differ only in the chemical brand of water utilized.
2. The United Nations Security Council passed a binding resolution in 2022 declaring Thorium processing a crime against humanity, completely shutting down global research.
3. Uranium-238 is a highly fissile isotope that can easily sustain a continuous chain reaction when exposed to regular domestic sunlight.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. Fission is splitting heavy nuclei; fusion is merging light elements. There is no UN ban on Thorium research; it is seen globally as a safer nuclear fuel alternative. Uranium-238 is fertile and requires energetic fast neutrons to fission; it is completely unreactive to ambient sunlight.
Consider the following statements regarding the Dhruva research reactor at Trombay:
1. The Dhruva research reactor located at BARC Trombay is a high-flux reactor utilized heavily for the indigenous production of medical radioisotopes and weapons-grade plutonium.
2. Dhruva utilizes natural uranium fuel and heavy water as both a moderator and a coolant, structurally resembling a scaled-down PHWR.
3. Dhruva was constructed completely under the joint operational management and ownership of the International Atomic Energy Agency (IAEA).
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct. Statement 3 is incorrect: Dhruva is a fully indigenous facility developed exclusively by Indian scientists and is classified as an un-safeguarded strategic/military research facility under sole national oversight.
Consider the following statements regarding international nuclear treaty frameworks:
1. The International Atomic Energy Agency (IAEA) directly funds the physical construction of all commercial nuclear power plants in non-NPT signatory states like India.
2. India signed the Nuclear Non-Proliferation Treaty (NPT) in 2015 to secure absolute permanent membership in the Nuclear Suppliers Group (NSG).
3. The Comprehensive Nuclear-Test-Ban Treaty (CTBT) has been fully ratified by all permanent members of the UN Security Council, making it binding on India.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. The IAEA acts as a nuclear safety watchdog and advisory body; it does not fund commercial power plant construction. India has consistently refused to sign the NPT on the grounds that it is discriminatory. The CTBT has not entered into force globally because several key countries, including permanent UN Security Council members like the United States and China, have signed but never ratified it.
Consider the following statements regarding Molten Salt Breeder Reactors (MSBRs):
1. Molten Salt Breeder Reactors (MSBRs) are being evaluated as a potential technological variant for India's third stage due to their capability to process thorium in a liquid state.
2. In an MSBR, the nuclear fuel is dissolved directly in a carrier salt (such as lithium-beryllium fluoride) which functions simultaneously as the fuel matrix and the primary coolant.
3. A major operational advantage of molten salt systems is their low operating pressure, which significantly mitigates the structural risk of catastrophic high-pressure pipe ruptures.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. MSBRs are a major focus for Stage 3 thorium optimization. Dissolving thorium in molten fluoride salts removes fuel fabrication limits, and low-pressure operations eliminate the mechanical stresses seen in high-pressure water systems.
Consider the following statements regarding the First Stage of India's nuclear program:
1. Stage 1 relies entirely on Pressurized Heavy Water Reactors (PHWRs) fueled by natural, unenriched uranium.
2. In a Pressurized Heavy Water Reactor, heavy water acts strictly as a coolant and regular light water is utilized as the moderator.
3. The byproduct of Stage 1 is Plutonium-239, which is permanently disposed of in deep geological repositories as high-level nuclear waste.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct. Statement 2 is incorrect: In PHWRs, heavy water (Deuterium Oxide) serves as both the coolant and the moderator. Statement 3 is incorrect: The Plutonium-239 byproduct is not disposed of; it is reprocessed and serves as the vital starting fuel for Stage 2 of the program.
Consider the following statements regarding the overarching architecture of India's nuclear strategy:
1. The Three-Stage Nuclear Power Programme was formulated by APJ Abdul Kalam in the 1970s to achieve energy security.
2. The ultimate objective of the program is to utilize India's vast domestic Uranium reserves to achieve absolute energy independence.
3. India has currently successfully commercialized all three stages of the nuclear program and integrated them into the national grid.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: The program was conceptualized by Homi J. Bhabha in the 1950s. Statement 2 is incorrect: The ultimate objective is to utilize India's vast Thorium reserves, as domestic Uranium reserves are comparatively modest. Statement 3 is incorrect: Only Stage 1 (PHWRs) is fully commercialized; Stage 2 (FBR) is in the prototype phase, and Stage 3 is largely experimental.
Consider the following statements regarding reactor safety systems and environmental dynamics:
1. Pressurized Heavy Water Reactors (PHWRs) possess a strong negative void coefficient of reactivity, inherently reducing reactor power if boiling occurs in the coolant.
2. Modern passive safety systems in nuclear reactors rely on natural phenomena like gravity, natural convection, and compressed gases rather than active mechanical pumps.
3. The primary structural purpose of a reactor containment building is to shield the inner reactor core from incoming solar radiation and atmospheric cosmic rays.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 2 is correct. Statement 1 is incorrect: PHWRs possess a positive void coefficient, meaning if coolant is lost or boils, reactivity slightly increases, requiring highly responsive active safety systems. (Light Water Reactors have a negative void coefficient). Statement 3 is incorrect: Containment buildings are designed to keep radioactive materials inside during an accident, not to block external cosmic radiation.
Consider the following statements regarding metallurgical engineering inside FBR cores:
1. High-density energetic fast neutrons in a Fast Breeder Reactor subject structural core materials to intense radiation damage, inducing phenomena like void swelling and helium embrittlement.
2. To withstand this harsh radiation and thermal environment, India utilizes specialized advanced materials like modified Ferritic-Martensitic steel for FBR fuel cladding and core components.
3. The degradation of structural materials under prolonged neutron irradiation is a key engineering factor that dictates the ultimate operational lifespan of a nuclear reactor vessel.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. Fast neutron bombardment alters metal lattices on an atomic scale. Developing specialized materials like Ferritic-Martensitic steels is a crucial step to extend core longevity and handle high thermal stresses without structural swelling or cracking.
Consider the following statements regarding India's Civil-Military Nuclear Separation Plan:
1. Under India's Civil-Military Nuclear Separation Plan formulated after the 2005 Indo-US joint statement, India placed all its operational Fast Breeder Reactors under permanent international safeguards.
2. The Global Centre for Nuclear Energy Partnership (GCNEP) in Haryana is an Indian initiatives-driven research facility focusing on nuclear safety, security, and advanced safeguards.
3. India's unique 'Separation Plan' allowed civilian nuclear facilities to utilize imported uranium while preserving domestic uranium strictly for strategic or un-safeguarded military reactors.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 2 and 3 are correct. Statement 1 is incorrect: India explicitly excluded its indigenous fast breeder reactor program and facilities (like IGCAR and the PFBR) from the civilian list, keeping them out of international safeguards to preserve strategic autonomy.
Consider the following statements regarding the timeline and inheritance of the FBTR:
1. The Fast Breeder Test Reactor (FBTR) at Kalpakkam attained its first criticality in the year 1985, serving as the foundational testbed for India's second-stage metallurgy.
2. The FBTR design was heavily modeled on the French Rhapsodie experimental fast reactor.
3. FBTR has consistently operated at an uninterrupted capacity factor of 100% since 1985 without undergoing any maintenance shutdowns.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct: The FBTR was commissioned in 1985 based on French technological foundations. Statement 3 is incorrect: As an experimental testbed, it has undergone numerous planned cycles, fuel reconfigurations, and research adjustments over its multi-decade operational history.
Consider the following statements regarding the historical administration of the AEC:
1. The Atomic Energy Commission (AEC) of India was established in 1948 with Dr. Vikram Sarabhai appointed as its very first ex-officio chairman.
2. The Union Minister of Environment, Forest and Climate Change serves as the permanent ex-officio chairman of the Atomic Energy Commission.
3. The AEC is constitutionally mandated to publish every single detail of its strategic defense inventory on a public website every Monday morning.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. Dr. Homi J. Bhabha was the founding chairman of the AEC in 1948. The Secretary to the Department of Atomic Energy serves as the ex-officio chairman, reporting directly to the Prime Minister. Strategic data is classified under the Official Secrets Act for national defense security.
Consider the following statements comparing loop-type and pool-type reactor designs:
1. The planned Jaitapur Nuclear Power Project in Maharashtra is designed to deploy French-designed Evolutionary Power Reactors (EPRs), which are advanced pressurized water reactors.
2. Unlike the pool-type design of India's fast breeders, the foreign-sourced EPR and VVER reactors are loop-type thermal reactors utilizing light water.
3. Foreign technology collaborations at Jaitapur and Kudankulam are executed via equity partnerships where foreign companies retain 51% ownership of the physical power plants.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct. Statement 3 is incorrect: Indian statutory laws do not permit foreign or private entities to own or operate nuclear utilities; NPCIL retains 100% ownership and operational control over these plants.
Consider the following statements regarding the institutional framework of the Department of Atomic Energy (DAE):
1. The Department of Atomic Energy (DAE) functions directly under the administrative purview of the Prime Minister of India.
2. The Institute for Plasma Research (IPR) is an autonomous research and development institute functioning under the DAE, primarily focused on nuclear fusion technology.
3. The DAE relies entirely on the Ministry of Defence for the budgetary funding and administrative oversight of all civilian nuclear power plants.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct. Statement 3 is incorrect: The DAE has its own budget allocation and administrative independence. The civilian nuclear power plants are funded and operated by NPCIL (a PSU under DAE), completely separate from the Ministry of Defence.
Consider the following statements regarding the Third Stage and Advanced Heavy Water Reactors (AHWR):
1. Advanced Heavy Water Reactors (AHWRs) are designed to serve as a transitional technological bridge to the third stage of the program.
2. Thorium-232 is a highly fissile material that can directly and independently sustain a nuclear chain reaction without any prior conversion.
3. India imports its entire requirement of Thorium from Kazakhstan to fuel its upcoming third-stage nuclear reactors.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: AHWRs are a bridge to Stage 3. Statement 2 is incorrect: Thorium-232 is fertile, not fissile; it cannot sustain a chain reaction until it absorbs a neutron and transmutes into fissile Uranium-233. Statement 3 is incorrect: India holds some of the world's largest domestic reserves of Thorium in the form of monazite sands along its southern coasts.
Consider the following statements regarding alternative nuclear physics theories and fuel limits:
1. A standard Thorium-232 nucleus can be induced to undergo spontaneous nuclear fission simply by exposing it to low-energy radio waves.
2. Commercial cold fusion technology has been successfully integrated into India's national power grid since 2020, producing over 10% of total electricity.
3. Unlike Uranium, the fission of a Uranium-233 nucleus absorbs more neutrons than it releases, preventing any sustained chain reaction.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. Thorium-232 requires neutron absorption to transmute into a fissile isotope; radio waves carry zero nuclear force. Cold fusion remains an unproven laboratory hypothesis and is not commercialized anywhere. Uranium-233 releases approximately 2.5 neutrons per fission, making it highly capable of sustaining a chain reaction.
Consider the following statements comparing Thorium and Uranium fuel cycles:
1. Thorium is naturally significantly more abundant in the Earth's crust than Uranium, offering a larger prospective energy reserve.
2. Thorium-based fuel cycles inherently generate a substantially lower volume of long-lived transuranic radioactive waste compared to standard Uranium-Plutonium cycles.
3. The intrinsic weaponization potential of a Thorium-U233 fuel cycle is considered lower due to the unavoidable presence of high-energy gamma-emitting decay isotopes.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. Thorium is roughly 3-4 times more abundant than Uranium. Because Thorium is lighter (atomic number 90), it requires multiple neutron captures to reach the heavy, long-lived transuranic elements (like Americium or Curium) produced easily in Uranium cycles. The U-232 byproduct makes weapons manufacturing exceedingly difficult and hazardous due to gamma radiation.
Consider the following statements regarding the classification of nuclear isotopes:
1. A fertile material is one that cannot sustain a fission chain reaction by itself but can be converted into a fissile material upon absorbing a neutron.
2. Uranium-235 is technically classified as a fertile material because it is naturally abundant in the earth's crust.
3. Plutonium-239 is a naturally occurring fissile isotope that is heavily concentrated in high-grade pitchblende ores.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct. Statement 2 is incorrect: Uranium-235 is a fissile material (capable of sustaining a chain reaction), whereas Uranium-238 is fertile. Statement 3 is incorrect: Plutonium-239 is an artificial isotope generated in reactors, not naturally occurring in minable ores.
Consider the following statements regarding domestic uranium mining assets:
1. The Jaduguda mine, located in the state of Rajasthan, was the first industrial-scale uranium mine opened in India.
2. Indian uranium ores mined at Singhbhum are exceptionally high-grade, containing over 50% pure Uranium oxide by weight.
3. The exploration and mapping of all domestic atomic mineral resources in India are managed by the Geological Survey of India, completely independent of the Department of Atomic Energy.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. The Jaduguda mine is located in Jharkhand, not Rajasthan. Indian uranium deposits are notoriously low-grade, typically yielding less than 0.1% uranium extract by weight. Exploration is managed by the Atomic Minerals Directorate for Exploration and Research (AMD), a dedicated wing under the DAE.
Consider the following statements regarding the structural engineering of Indian PHWRs:
1. In Indian Pressurized Heavy Water Reactors (PHWRs), the reactor core is contained within a large cylindrical horizontal stainless steel vessel known as the Calandria.
2. The fuel bundles in a PHWR are housed within individual high-pressure zircaloy tubes called pressure tubes, which pass horizontally through the Calandria.
3. Zircaloy is chosen for fuel cladding and pressure tubes because of its combination of high mechanical strength, corrosion resistance, and exceptionally low absorption of thermal neutrons.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. The horizontal calandria design allows individual pressure tubes to carry high-pressure heavy water across fuel bundles. Zircaloy is the ideal material choice because it does not waste neutrons through parasitic absorption.
Consider the following statements regarding the institutional reporting structure of the DAE:
1. The Nuclear Power Corporation of India Limited (NPCIL) reports directly to the Ministry of Power for its corporate governance and operational mandates.
2. Commercial generation of electricity from nuclear power plants currently contributes more than 50% of India's total installed power capacity.
3. The Indian Space Research Organisation (ISRO) holds the final statutory authority to approve the core safety modifications of all nuclear reactors in India.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All statements are incorrect. NPCIL is a public sector enterprise directly under the Department of Atomic Energy (DAE), which answers to the PMO. Nuclear energy accounts for roughly 2-3% of India's total generation mix, not 50%. Safety approvals are handled indigenously by the Atomic Energy Regulatory Board (AERB).
Consider the following statements regarding the mechanical linkages between the three stages of the nuclear program:
1. The plutonium extracted from the reprocessed spent fuel of Stage 1 PHWRs is essential to initiate the reactor cores of Stage 2 Fast Breeder Reactors.
2. During Stage 2 operations, Thorium-232 is introduced in the reactor's blanket region to be subjected to neutron irradiation and converted into Uranium-233.
3. The resultant Uranium-233 generated and extracted during the second stage serves as the primary fissile fuel for the reactors designed for the third stage.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements accurately describe the sequential dependency of Homi Bhabha's three-stage nuclear program. Stage 1 creates Pu-239. Stage 2 uses Pu-239 to breed more Pu-239 and simultaneously breeds U-233 from a Thorium blanket. Stage 3 then uses U-233 and Thorium to achieve a self-sustaining cycle.
Consider the following statements regarding specific historical and operational reactors in India:
1. APSARA, recognized as Asia's first nuclear reactor, was a large-scale Pressurized Heavy Water Reactor designed entirely with indigenous Indian technology.
2. The Kudankulam Nuclear Power Plant located in Tamil Nadu generates electricity utilizing indigenous Fast Breeder Reactor technology.
3. The CIRUS research reactor was built in collaboration with the United States and was legally placed under permanent IAEA safeguards from its inception.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: APSARA was a light-water moderated, swimming-pool-type reactor built with assistance from the United Kingdom. Statement 2 is incorrect: Kudankulam utilizes VVER technology (Pressurized Water Reactors) imported from Russia, not indigenous fast breeders. Statement 3 is incorrect: CIRUS (Canada India Reactor Utility Services) was built with Canadian assistance and operated without IAEA safeguards (which allowed the U.S. supplied heavy water to be used in producing plutonium for the 1974 test).
Consider the following statements regarding the exploration and history of nuclear resources in India:
1. India's largest uranium deposit discovered at Tummalapalle is located in the state of Telangana.
2. The Atomic Energy Act of 1962 strictly prohibits any private participation in the core mining of prescribed substances like Uranium.
3. India's first nuclear power station at Tarapur was built using indigenous Pressurized Heavy Water Reactor (PHWR) technology.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 2 is correct: The Atomic Energy Act reserves the mining of strategic atomic minerals exclusively to public sector corporations controlled by the central government. Statement 1 is incorrect: The Tummalapalle uranium mine is located in Andhra Pradesh, not Telangana. Statement 3 is incorrect: Tarapur Units 1 and 2 are Boiling Water Reactors (BWRs) constructed by General Electric (USA) using imported technology.
Consider the following statements regarding the regulatory and administrative structure of India's nuclear sector:
1. The Atomic Energy Commission (AEC) functions as the apex executive body governing the formulation of nuclear policy in India.
2. The Atomic Energy Regulatory Board (AERB) is structurally completely independent of the executive and reports directly to the Supreme Court of India.
3. The Nuclear Power Corporation of India Limited (NPCIL) is a public sector enterprise responsible for the design, construction, and operation of commercial nuclear power plants.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 3 are correct. Statement 2 is incorrect: The AERB reports to the Atomic Energy Commission (AEC). Its lack of total statutory independence from the DAE/AEC has frequently been a subject of administrative debate, but it certainly does not report to the Supreme Court.
Consider the following statements regarding foreign-assisted nuclear installations in India:
1. The Kudankulam Nuclear Power Plant utilizes Russian-designed VVER-1000 pressurized water reactors, which operate on a thermal neutron spectrum.
2. Unlike India's indigenous PHWRs, the VVER reactors at Kudankulam utilize low-enriched uranium oxide as their primary fuel.
3. The entire Kudankulam installation is completely exempt from IAEA safeguards because it was constructed via a bilateral government-to-government agreement.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct: VVERs are Russian light-water pressurized reactors that require enriched uranium. Statement 3 is incorrect: Because Kudankulam relies on imported fuel and components under a foreign framework, it is explicitly subject to IAEA item-specific safeguards.
Consider the following statements regarding the utilization of liquid sodium in fast reactors:
1. Liquid sodium is utilized as a coolant in Fast Breeder Reactors precisely because it slows down neutrons effectively to thermal energy levels.
2. A critical safety and engineering challenge with liquid sodium coolant is its highly reactive chemical nature, causing violent fires upon exposure to air or water.
3. To entirely prevent radioactive sodium from reacting with water in the steam generator, the PFBR utilizes a single-loop direct cooling mechanism.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 2 is correct. Statement 1 is incorrect: Sodium is chosen specifically because it does not moderate (slow down) neutrons, preserving the fast neutron spectrum needed for breeding. Statement 3 is incorrect: To prevent radioactive sodium from contacting water, FBRs use a multi-loop system featuring a primary radioactive sodium loop, an intermediate non-radioactive sodium loop, and a tertiary water/steam loop.
Consider the following statements regarding nuclear waste immobilization via vitrification:
1. Vitrification is an advanced waste management technology implemented by India to immobilize high-level radioactive liquid waste by incorporating it into a durable borosilicate glass matrix.
2. India's operational vitrification plants are completely mobile units mounted on trucks that treat nuclear waste while driving along national highways.
3. The vitrified glass blocks lose 100% of their radioactivity within 24 hours, allowing them to be safely disposed of in municipal landfills.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: India uses borosilicate vitrification to lock up high-level waste at sites like Tarapur and Trombay. Statement 2 is incorrect: Vitrification plants are highly secure, permanent, stationary concrete industrial complexes. Statement 3 is incorrect: The blocks remain highly radioactive for centuries and require long-term interim monitoring followed by deep geological disposal.
Consider the following statements regarding the Prototype Fast Breeder Reactor (PFBR) architecture:
1. Bharatiya Nabhikiya Vidyut Nigam Limited (BHAVINI) is wholly owned by the Government of India under the Department of Atomic Energy.
2. The structural design of India's Prototype Fast Breeder Reactor (PFBR) utilizes a pool-type configuration where the entire primary coolant circuit is contained within a single large reactor vessel.
3. To mitigate the risk of high-pressure chemical interactions, an intermediate sodium loop is placed between the radioactive primary sodium loop and the steam generator water loop.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. BHAVINI handles Stage 2 commercial fast reactors. The pool-type configuration keeps the radioactive primary loop safe inside one main vessel. The secondary, intermediate non-radioactive sodium loop acts as an essential buffer to separate radioactive sodium from water lines.
Consider the following statements regarding tritium isotope dynamics in heavy water reactors:
1. The absolute separation of the primary coolant system from the secondary steam-generating system in a PHWR prevents radioactive tritium from entering the external turbine circuit during normal operations.
2. Tritium is a naturally occurring stable isotope of hydrogen that is heavily mined in the Himalayas to act as an emergency reactor shutdown agent.
3. Tritium emissions from nuclear plants are completely harmless to human health and require zero monitoring or containment protocols.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: The dual-loop separation retains any activation product inside the reactor vault. Statement 2 is incorrect: Tritium is an un-mined, radioactive isotope of hydrogen with a 12.3-year half-life generated inside reactors via neutron absorption by deuterium. Statement 3 is incorrect: Tritium is a low-energy beta emitter that can present internal radiation biohazards if inhaled or ingested, requiring rigorous monitoring.
Consider the following statements regarding the technical design of the Advanced Heavy Water Reactor (AHWR):
1. India's upcoming Advanced Heavy Water Reactor (AHWR) features vertical pressure tubes and utilizes a passive gravity-driven water pool for emergency core cooling.
2. The AHWR operates on a fast neutron spectrum, completely eliminating the need for any neutron moderator.
3. The fuel configuration of the AHWR relies entirely on enriched plutonium, completely excluding Thorium-232 from its core design.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: The AHWR is an advanced design with vertical pressure tubes and incorporates top-tier passive safety systems like the Gravity Driven Water Pool. Statement 2 is incorrect: The AHWR is a thermal reactor that uses heavy water as a moderator. Statement 3 is incorrect: A core objective of the AHWR is to maximize the utilization of Thorium-232 by transmuting it to Uranium-233.
Consider the following statements regarding Fast Breeder Reactors (FBRs) in the Second Stage:
1. A Fast Breeder Reactor uses slow, thermalized neutrons to efficiently sustain the nuclear fission chain reaction.
2. Stage 2 reactors are fueled primarily by naturally occurring Thorium-232 extracted directly from coastal monazite sands.
3. Fast Breeder Reactors consume more fissile material than they produce during their standard operational fuel cycle.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: FBRs use 'fast' unmoderated neutrons to sustain fission and breed new fuel. Statement 2 is incorrect: Stage 2 is fueled by a Mixed Oxide (MOX) of Plutonium-239 and depleted Uranium, though Thorium is later introduced in a blanket. Statement 3 is incorrect: Breeder reactors are named such because they 'breed' (produce) more fissile material than they consume.
Consider the following statements regarding Homi Bhabha's strategic vision and global nuclear trends:
1. India's historical decision to adopt the closed fuel cycle was fundamentally driven by the geographical reality of modest domestic uranium reserves contrasted with vast thorium reserves.
2. In reactor physics, a 'breeding ratio' greater than 1 indicates that a nuclear reactor produces more fissile material than it consumes during its operation.
3. Currently, developed nations like the United States and France derive over 80% of their national electricity strictly from commercial Thorium Breeder Reactors.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct. Statement 3 is incorrect: Globally, Thorium commercialization is still in its infancy. The United States and France rely on conventional Uranium-fueled Light Water Reactors for their nuclear energy; neither country operates commercial Thorium Breeder Reactors.
Consider the following statements regarding refueling methodologies across reactor types:
1. Online refueling, which allows a reactor to be continuously refueled at full power without shutting down, is a distinct operational feature of Indian PHWRs.
2. Boiling Water Reactors (BWRs) like those at Tarapur Units 1 & 2 also possess the exact same mechanical capability of online refueling.
3. Fast Breeder Reactors using liquid sodium coolant require open top venting and continuous online refueling through vacuum tubes every 24 hours.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: The horizontal pressure tube setup in PHWRs allows fueling machines to isolate and swap bundles while online. Statement 2 is incorrect: BWRs have large high-pressure vessels that must be completely depressurized and shut down for fuel swaps. Statement 3 is incorrect: FBR fuel cycles run for months, and sodium must be handled under strict inert argon blankets to avoid fires.
Consider the following statements regarding reactor components and their specific functions:
1. The primary function of a moderator in a thermal nuclear reactor is to slow down fast-moving neutrons to increase the probability of nuclear fission.
2. Light water reactors generally require enriched uranium fuel because ordinary light water absorbs more neutrons than heavy water does.
3. Liquid sodium is frequently utilized as a primary coolant in Fast Breeder Reactors because of its excellent heat transfer properties and low neutron absorption cross-section.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. Moderators thermalize neutrons so U-235 can easily capture them. Light water (H2O) tends to absorb some neutrons (forming Deuterium), so the fuel must be enriched to compensate. Liquid sodium is ideal for FBRs because it doesn't slow down (moderate) the fast neutrons required for breeding.
Consider the following statements regarding key research institutions and developmental milestones:
1. The Bhabha Atomic Research Centre (BARC) is the premier institution leading the design and development of the Advanced Heavy Water Reactor (AHWR).
2. Kamini (Kalpakkam Mini) is an experimental research reactor in India that successfully utilizes Uranium-233 as its primary fuel.
3. The Indira Gandhi Centre for Atomic Research (IGCAR) plays the pivotal role in the design and technological development of Fast Breeder Reactors.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. BARC designs the AHWR. KAMINI at Kalpakkam is a globally unique U-233 fueled research reactor. IGCAR is the specialized hub for fast reactor technology and the closed fuel cycle.
Consider the following statements regarding Light Water Reactors (LWRs) and their role in India:
1. The VVER reactors installed at Kudankulam utilize enriched uranium as fuel, alongside light water functioning as both coolant and moderator.
2. Indiaâs indigenous three-stage nuclear power program was formulated to natively rely on Light Water Reactors (LWRs) for its foundational first stage.
3. In a Pressurized Water Reactor (PWR), the primary coolant water is kept under immense pressure to physically prevent it from boiling inside the reactor core.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 3 are correct. Statement 2 is incorrect: India's indigenous program natively relies on Pressurized Heavy Water Reactors (PHWRs) for the first stage because they run on natural uranium, circumventing the need for expensive enrichment facilities.
Consider the following statements regarding nuclear safety safeguards and fuel reserves:
1. India signed and ratified an IAEA Additional Protocol in 2014, which applies specifically to its designated civilian nuclear facilities.
2. To avoid sudden disruptions in power generation, India maintains a Strategic Uranium Reserve composed of both domestic and imported uranium inventories.
3. The Nuclear Suppliers Group (NSG) waiver granted to India in 2008 allows NSG member states to transfer nuclear material and technology to India despite India not being an NPT signatory.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. The 2014 Additional Protocol enhances tracking at civilian sites. The reserve insulates the grid from geopolitical shifts, and the 2008 NSG waiver integrated India into global clean energy commerce.
Consider the following statements regarding the PURNIMA research reactor series:
1. The PURNIMA series of experimental research reactors built at BARC played an invaluable role in studying the physics of fast reactors and verifying the behavior of Plutonium and Uranium-233 fuels.
2. PURNIMA-II was a unique experimental reactor that utilized a liquid solution of enriched plutonium nitrate dissolved in heavy water.
3. The entire PURNIMA series was imported as pre-fabricated modules from Canada under the Colombo Plan.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: The Purnima reactors provided essential data for the breeder and thorium loops. Statement 2 is incorrect: Purnima-II was a homogeneous solution reactor that used Uranium-233 fuel, not plutonium. Statement 3 is incorrect: The entire Purnima series was built indigenously by the reactor physics teams at BARC.
Consider the following statements regarding India's civil nuclear diplomacy and international agreements:
1. The Indo-US Civil Nuclear Agreement officially designated and recognized India as a 'Nuclear Weapons State' under the framework of the Non-Proliferation Treaty (NPT).
2. India's indigenous three-stage program reactors are mandatorily placed under the permanent safeguards of the International Atomic Energy Agency (IAEA).
3. India was granted a unique waiver by the Nuclear Suppliers Group (NSG) in 2008, enabling it to engage in global civil nuclear commerce without signing the NPT.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 3 is correct. Statement 1 is incorrect: The NPT defines a Nuclear Weapons State strictly as one that manufactured and exploded a nuclear device prior to Jan 1, 1967; India is not recognized as such under the NPT. Statement 2 is incorrect: India's indigenous strategic program (including FBRs) remains outside IAEA safeguards; only civilian reactors utilizing imported fuel are under IAEA safeguards.
Consider the following statements regarding the production and management of heavy water in India:
1. The Heavy Water Board (HWB), a constituent unit of the Department of Atomic Energy, is responsible for the production of heavy water (D2O).
2. Heavy water is extracted from seawater solely through a simple physical filtration process using advanced reverse osmosis membranes.
3. Despite indigenous efforts, India remains heavily dependent on imports from Russia to meet the domestic demand for heavy water required by PHWRs.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct. Statement 2 is incorrect: Heavy water is separated using complex chemical exchange processes (like the Hydrogen Sulphide-Water exchange process), not simple reverse osmosis. Statement 3 is incorrect: India is one of the world's largest producers of heavy water and is completely self-sufficient, frequently exporting it to other countries.
Consider the following statements regarding the 700 MWe indigenously developed PHWR units:
1. India's largest indigenous PHWR design has a capacity of 700 MWe, with the first commercial units successfully commissioned at Kakrapar, Gujarat.
2. The 700 MWe PHWR design completely scales up the older 220 MWe design without incorporating any new passive safety features.
3. The 700 MWe reactors require heavily enriched uranium fuel imported exclusively from Western Europe to sustain operations.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: The 700 MWe series represents a milestone in scaling up domestic civil technology at Kakrapar. Statement 2 is incorrect: It incorporates advanced passive decay heat removal systems that function without power supply. Statement 3 is incorrect: Like all standard PHWRs, it runs on natural, un-enriched uranium.
Consider the following statements regarding Monazite and Rare Earth resources in India:
1. Monazite sand is a primary mineral source of Uranium-235, accounting for over 90% of India's strategic uranium supply chain.
2. The export and commercial trade of Monazite sand from India is completely unrestricted and freely managed by private mining corporations.
3. Extracting Thorium from Monazite involves solely mechanical separation techniques using industrial magnets, requiring zero chemical processing.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: Monazite is a source of Rare Earth Elements (REEs) and Thorium, not Uranium-235. Statement 2 is incorrect: Monazite is classified as a 'prescribed substance' under the Atomic Energy Act; its mining and export are heavily restricted and monopolized by the state-owned IREL. Statement 3 is incorrect: Monazite is a chemically complex phosphate mineral requiring intensive chemical processing (leaching with strong acids or alkalis) to separate the Thorium and Rare Earths.
Consider the following statements regarding chemical processes and breeding definitions:
1. In the closed fuel cycle, the separation of plutonium from spent fuel is carried out by chemical solvent extraction techniques like PUREX.
2. The transmutation of Uranium-238 into Plutonium-239 involves a sequence of beta decays after neutron capture.
3. The breeding ratio of a nuclear reactor represents the ratio of fissile atoms produced to the fissile atoms consumed during operation.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. The PUREX process is used globally and in India to reprocess spent fuel. Uranium-238 captures a neutron to become U-239, which beta-decays to Neptunium-239 and then to Plutonium-239. A breeding ratio greater than 1 means the reactor breeds more fuel than it burns.
Consider the following statements regarding the reprocessing of spent nuclear fuel:
1. India strictly enforces a 'once-through' nuclear fuel cycle where highly radioactive spent fuel is permanently buried immediately after removal from the core.
2. The PUREX process is an advanced open-pit mining technique deployed to extract pure Thorium ore directly from granite rock formations.
3. India's domestic spent fuel reprocessing facilities are entirely operated by foreign private corporations under continuous mandatory IAEA surveillance.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: India relies on a 'closed fuel cycle' involving extensive reprocessing of spent fuel to extract Plutonium for Stage 2. Statement 2 is incorrect: PUREX (Plutonium Uranium Redox EXtraction) is a chemical reprocessing method used on spent fuel, not a mining technique. Statement 3 is incorrect: India's strategic reprocessing facilities are indigenous, run by BARC/DAE, and kept outside IAEA safeguards to protect national security.
Consider the following statements regarding reactor physics and neutron dynamics:
1. Thermal reactors utilize moderators to slow down neutrons because Uranium-235 has a significantly higher fission cross-section for thermalized neutrons.
2. Fast Breeder Reactors strictly avoid moderators because highly energetic fast neutrons are required to effectively transmute fertile U-238 into fissile Pu-239.
3. The small fraction of delayed neutrons released during fission is critical for human operators to maintain stable mechanical control over the chain reaction.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. Slow neutrons are more easily 'caught' by U-235. Fast neutrons are needed to hit U-238 hard enough to be absorbed without fissioning. If all neutrons were prompt (released instantly), the reaction would escalate too fast for physical control rods to react; delayed neutrons provide the necessary buffer time for reactor control.
Consider the following statements regarding the institutional infrastructure supporting India's nuclear fuel cycle:
1. The Uranium Corporation of India Limited (UCIL) is the public sector enterprise exclusively responsible for the mining and milling of uranium ore in India.
2. The Nuclear Fuel Complex (NFC) situated in Hyderabad manufactures and supplies nuclear fuel bundles and reactor core components.
3. Monazite sands, predominantly found in the coastal regions of Kerala and Tamil Nadu, serve as a major domestic source of Thorium.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. UCIL handles mining (e.g., in Jaduguda). NFC processes the mined materials into finished fuel assemblies. Coastal monazite sands are processed by Indian Rare Earths Limited (IREL) to extract Thorium.
Consider the following statements regarding nuclear liability legislations in India:
1. The Civil Liability for Nuclear Damage Act, 2010 features a unique provision (Section 17) that gives the operator a right of recourse against the equipment supplier under specific conditions.
2. The Act fixes absolute financial liability for nuclear damages exclusively on the foreign suppliers, completely exempting Indian operators from any financial burden.
3. To satisfy foreign suppliers, the Indian Parliament repealed Section 17 of the Act via a presidential ordinance in 2018.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is correct: Section 17 allows operators a right of recourse against suppliers if an accident is caused by defective equipment. Statement 2 is incorrect: The operator (NPCIL) bears primary financial liability up to a set cap, after which the state covers costs. Statement 3 is incorrect: Section 17 has never been repealed; instead, an Indian Nuclear Insurance Pool was formed to ease supplier risk.
Consider the following statements regarding the Prototype Fast Breeder Reactor (PFBR):
1. BHAVINI is the public sector undertaking specifically established to construct and eventually operate India's commercial Fast Breeder Reactors.
2. The 500 MWe Prototype Fast Breeder Reactor (PFBR) is currently located and undergoing commissioning at Tarapur, Maharashtra.
3. The PFBR design incorporates a blanket of depleted uranium around the core to capture stray neutrons and breed additional Plutonium-239.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 3 are correct. Statement 2 is incorrect: The PFBR is located at Kalpakkam in Tamil Nadu, not Tarapur (which houses BWRs and PHWRs).
Consider the following statements regarding the Fast Breeder Test Reactor (FBTR) at Kalpakkam:
1. The FBTR was the first reactor in the world to successfully use a unique mixed plutonium-uranium carbide fuel core.
2. The thermal efficiency of a Fast Breeder Reactor using liquid sodium coolant is lower than that of a standard Pressurized Heavy Water Reactor.
3. The Indira Gandhi Centre for Atomic Research (IGCAR) was established specifically to conduct R&D on fast breeder reactor technology and its associated fuel cycle.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 3 are correct. Statement 2 is incorrect: Liquid sodium coolants operate at much higher temperatures (around 500-550°C) without boiling compared to water coolants, allowing fast breeder reactors to achieve a higher thermal efficiency (approx 40%) than PHWRs (approx 30%).
Consider the following statements regarding the geopolitical history of India's nuclear development:
1. The Pokhran-I nuclear test in 1974 utilized weapons-grade plutonium that was derived from the spent fuel of the Canadian-supplied CIRUS reactor.
2. In direct response to Pokhran-I, the international Nuclear Suppliers Group (NSG) was formed specifically to control nuclear exports and curtail India's technological access.
3. India officially signed and ratified the Comprehensive Nuclear-Test-Ban Treaty (CTBT) in 1998 immediately following the Pokhran-II underground tests.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statements 1 and 2 are correct. Statement 3 is incorrect: India has consistently refused to sign the CTBT, arguing that the treaty is discriminatory and fails to provide a comprehensive framework for universal nuclear disarmament.
Consider the following statements regarding the concept of a 'Closed Fuel Cycle':
1. A closed fuel cycle involves the deliberate chemical reprocessing of spent nuclear fuel to extract useful fissile and fertile materials from the high-level waste.
2. India's three-stage nuclear program is fundamentally reliant on a closed fuel cycle to extract maximum energy potential from its limited domestic uranium reserves.
3. Reprocessing spent fuel significantly reduces both the volume and the long-term radiotoxicity of the final high-level radioactive waste requiring deep geological disposal.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. By recycling Pu and U from spent fuel, the closed cycle maximizes energy extraction (by a factor of ~60x compared to a once-through cycle) and isolates the highly radioactive, short-lived fission products from the long-lived actinides, reducing the required isolation time of the final waste from hundreds of thousands of years to mere centuries.
Consider the following statements regarding advanced international nuclear research projects:
1. The ITER (International Thermonuclear Experimental Reactor) mega-project currently under construction in France is designed to pioneer commercial Thorium-based fission technology.
2. India's participation status as a full member in the ITER project was unilaterally revoked in 2015 due to alleged violations of IAEA safeguards at domestic sites.
3. A Tokamak device relies on immense gravitational confinement, simulating the core of a star, to maintain a sustained nuclear fusion reaction.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: ITER is a nuclear fusion project, not a fission project, and does not use Thorium. Statement 2 is incorrect: India remains an active, contributing full member of the ITER project. Statement 3 is incorrect: Tokamaks rely on magnetic confinement (using powerful superconducting magnets) to contain the plasma, not gravitational confinement (which is how stars operate naturally).
Consider the following statements regarding Monazite sand and its regulation:
1. Indian Rare Earths Limited (IREL) is a central public sector undertaking responsible for processing beach sand minerals to isolate monazite.
2. Monazite is chemically a rare-earth phosphate mineral that contains significant percentages of both Thorium and rare-earth oxides.
3. Under the Atomic Energy (Working of the Mines, Minerals and Special Materials) Rules, monazite is designated as a 'prescribed substance' requiring strict central authorization for handling.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: All three statements are correct. IREL extracts monazite from beach sands. Monazite is a phosphate compound rich in light rare earth elements and Thorium. Due to its strategic nature under the Atomic Energy Act, it is highly regulated as a prescribed substance.
Consider the following statements regarding the technical specifications of the Advanced Heavy Water Reactor (AHWR):
1. The AHWR utilizes circulating liquid sodium as its primary coolant in order to achieve high thermal conversion efficiency.
2. The AHWR is structurally designed to be entirely dependent on imported enriched uranium to maintain continuous base-load operations.
3. India's AHWR is fundamentally designed as a fast breeder reactor with the primary objective of producing more weapons-grade plutonium than it consumes.
How many of the statements given above are correct?
- Only one
- Only two
- All three
- None
Explanation: Statement 1 is incorrect: The AHWR uses boiling light water as its primary coolant, while using heavy water as the moderator. Statement 2 is incorrect: It is designed to run primarily on Thorium (converted to U-233) mixed with Plutonium or low-enriched uranium, advancing self-reliance. Statement 3 is incorrect: The AHWR is a thermal reactor, not a fast breeder reactor.