Institute For Plasma Research Research Articles

Neutron emission characterization of IPR 14 MeV neutron generator

Accelerator-based neutron sources are being developed worldwide due to their wide applications. Institute for Plasma Research in India has developed an accelerator-based high-yield 14 MeV neutron generator based on deuterium-tritium (D-T) reaction to perform fusion-related benchmark experiments. This neutron generator is designed to produce 1012 neutrons per second in both mode continuous and pulse. The emission of neutrons from an accelerator-based neutron generator is not isotropic due to target geometry and angular dependency of reaction cross-section. A detailed and accurate description of neutron source emission and distribution is required to use such a neutron generator for various experiments. The neutron generator is characterized using experiments and simulations to accomplish the request. Energy and angular distributions of emitted neutrons are measured using a calibrated single crystal diamond (SCD) detector. Experimental data of neutron distributions are used to validate source neutron definition for Monte Carlo N Particle (MCNP) simulation. An accurate model of the Titanium Tritide (TiT) target and its holder geometry is prepared for the simulation. Finally, to validate the simulation model, simulated neutron fluxes are compared with measured ones by the SCD detector. This paper discusses the methodology adopted to characterize emitted neutrons and its results.

Development and testing of lab-scale atmospheric molecular sieve bed with zeolite 4A adsorbent

Tritium Extraction System (TES) is one of the most important systems of fusion blanket. The two basic systems of TES are Atmospheric Molecular Sieve Bed (AMSB) and Cryogenic Molecular Sieve Bed (CMSB). AMSB removes ppm levels of water vapour (Q2O), while CMSB removes hydrogen isotopes (Q2), oxygen, and nitrogen from helium purge gas. Though detailed parametric study of AMSB is very important for fuel cycle technology, such studies are very limited. In this work, a lab-scale AMSB is designed and developed at Institute for Plasma Research, Gandhinagar, using Zeolites 4A as an adsorbent material. Experimental break through curves for the adsorption of various concentrations of moisture (H2O) (up to ∼20,000 ppm) at flow rates (1–3 NLPM) from helium gas at room temperature have been generated and compared with theoretical estimation. Adsorption capacity of lab scale AMSB has been estimated at various operating conditions. The effects of the initial moisture concentrations and flow rates on breakthrough curves are studied in detail.

A CFD analysis of the rotating target holder of the 14-MeV neutron generator

An accelerator based 14-MeV neutron generator is installed at Institute for Plasma Research, Gandhinagar to generate high energy neutrons by using a water-cooled rotating tritium target. In this device, neutrons would be generated from the nuclear reaction 3H(D, n)4He by bombarding accelerated deuterium ions on a solid tritium target. The rotating target holder mainly consists of a rotating copper disc water-cooled case mounted on the rotating shaft. The high-energy deuterium ion beam impacted on solid TiT target fitted on the copper case imparting its energy to the case. This energy is taken away from the system through the water passing through the annulus cavity of the shaft. This paper presents details of the engineering CFD (computed fluid dynamics) analysis carried out for optimizing two important parameters of the rotating target. Firstly optimization of the location of flow parameters of the water as mass flow rate and Secondly optimization of speed of the rotating target and the design of fins inside the copper case.

Development of lead lithium (Pb-16Li) alloy production system and characterization of the produced alloy

A lead lithium (Pb-16Li) production facility of capacity ∼75 kg has been developed at Institute for Plasma Research (IPR). Pb-16Li ingots were produced from an in-house developed Pb-16Li production system using the MHD stirring technique. The produced ingots were characterized analytically and microstructurally to determine the composition as well as to verify the homogeneity. Inductive Coupled Plasma-Optical Emission Spectrocopy (ICP-OES) analysis result shows the eutectic Li composition of 0.59±0.04 wt% which suggests the formation of Pb-16Li eutectic. To further confirm the eutectic formation, the eutectic temperature of the produced ingots had been determined by the Differential Scanning Calorimetry (DSC) and Pb-16Li solidification curve. The DSC analysis results and the solidification curve of the Pb-16Li samples indicate the melting temperature in the range of 235–238 °C which is similar to the Pb-16Li eutectic temperature ∼235 °C as reported in the literature and hence confirm the formation of Pb-16Li eutectic. A total of ∼750 kg of Pb-16Li ingots were produced from the system, and the produced Pb-16Li is being used as a process fluid in the various experimental systems at IPR.

Applied Plasma Physics Experiments in Linear (APPEL) device for plasma surface interaction studies

The APPEL device (Applied Plasma Physics Experiments in Linear Device), recently commissioned at the Institute for Plasma Research (IPR), is an intermediate setup towards building a Plasma Material Interaction (PMI) facility. A particular application of this device is to develop and test high-density, low-pressure plasma sources that can be operated under magnetic fields; optimize the plasma sources for working under various magnetic field configurations; and perform physics experiments relevant to electron heating and plasma interactions with external electrodes. The setup consists of 16 electromagnets that provide a flexible, steady-state axial magnetic field in excess of 0.4 T over an axial distance of 3.5 m, with 2 % radial uniformity across 32.0 cm diameter. This paper gives a brief overview of the APPEL device, emphasizes on the APPEL magnet system, and presents the characteristics of a 3.5 m long, high-density (1017–1018 m−3) helium plasma column, using a hollow cathode plasma source obtained in the pressure range below i.e., p < 2.0 Pa. The corresponding ion flux is found to be in the range of 1021 -1022 m−2s−1, similar to other linear systems currently in use for plasma surface interaction studies. A qualitative discussion is given to explain the characteristics of the plasma column.

High Heat Flux Testing of Brazed W/CuCrZr Monoblock in High Heat Flux Test Facility

The Institute for Plasma Research (IPR) is involved in the development of various technologies for fabrication and testing/qualification of tungsten (W)–based plasma-facing components for ITER-like applications. As a part of these activities, a small-scale W/Cu/CuCrZr monoblock test mock-up is prepared by using a vacuum brazing process. Further, thermal fatigue testing of this test mock-up is performed using the High Heat Flux Test Facility at IPR under an absorbed heat flux of ~9.5 MW/m2 for 1200 thermal cycles. Thermal-hydraulic analysis and computational fluid dynamics (CFD) simulations are also performed to understand the heat flux testing scenario. Nondestructive testing of the test mock-up after thermal cyclic heat flux testing indicates that there are no defects in the test mock-up except for minor cracks on the surface of W tiles. The results of thermal cyclic testing, finite element analysis, CFD analysis, and postanalysis of the High Heat Flux test are presented in the paper.

Development of prototype power supply for ohmic transformer system of SSST

The conceptual design of Small Scale Spherical Tokamak (SSST) has been completed at Institute for Plasma Research (IPR). It consists of poloidal field (or Equilibrium) field coils, Toroidal field coils and Ohmic Transformer (OT) system. The poloidal magnets are used for the plasma shaping and equilibrium. The plasma current ramp up and sustenance up to 20 ms is achieved by OT system. The OT system comprises of Central Solenoid (CS) and compensating coils TR1, TR2 & TR3. The Preliminary design for power supply for OT system has been finalized and a prototype OT power supply has been developed at IPR. The conceptual design of prototype Ohmic Transformer Power Supply (OTPS), its philosophy of operation, simulation results and experimental results are presented in this paper.

Characterizing a Ka-Band FMCW Reflectometer

A Ka-Band ultra-fast, ultra-wide band Frequency Modulated Continuous Wave (FMCW) reflectometer to measure the plasma density profile has been designed and developed at Institute for Plasma Research (IPR). We present here the need for ultra-fast and ultra-wide frequency of operation and estimate expected beat frequencies for the instrument. Three distinct corrections are made to the obtained frequencies. Firstly, inherent non-linearity of the frequency source is removed by shifting non-linearity to the tuning voltage of the hyper-abrupt varactor tuned oscillator and then correcting mismatch of the absolute values of frequency by introducing a delay line to account for the difference in length between active and reference paths for producing the beat frequencies. Using code developed based on the short time Fourier transform we extract the beat frequency to measure various known distances and verify with our beat frequency estimations and also show that range resolution obtained is very close to the theoretical one obtained.

Design, manufacturing, and testing of 0.35/25kV, 20kHz transformers for particle accelerators.

A high voltage, high frequency transformer unit has been designed and built for powering the Cockcroft-Walton voltage multiplier to be used as part of a particle accelerator power supply at the Institute For Plasma Research, India, for the nuclear fusion research facility. A novel combination of high voltage (25kV), high frequency (20kHz), and high power (70kVA) specifications makes its design distinctive and more challenging. The complete unit is composed of two 0.350/25kV amorphous core transformers connected in center-tap configuration and immersed in an oil-filled tank. To facilitate an iterative design procedure, a spreadsheet method was utilized. The design involved a methodical approach for the core and winding selection, followed by the magnetic analysis and high voltage insulation layout through the finite element method. All the magnetic, electrical, and thermal parameters have been evaluated in detail, assuring a continuous stable operation having an efficiency of greater than 95%. Finally, the transformers were made, and preliminary experiments, including turns ratio, short-circuit, and dielectric tests, were carried out to verify the accuracy of the proposed design. The unit was also field tested under actual load conditions, and the test results were presented and corroborated with the design calculations.

Test Results of a Prototype HTS Current Lead With MgB2 and NbTi Superconducting Joints

Conventional vapor cooled current leads (CL) based on low temperature superconductor are the major consumer of liquid helium in large-scale superconducting magnets based nuclear fusion devices. Use of conduction cooled, high temperature superconductors (HTS) current leads enable operation up to 80 K and saves significant cold capacity of cryo plant. Recently at Institute for Plasma Research, India, a 3.3 kA rated prototype HTS CL pair is developed with the help of Indian industries. It exploits various superconducting materials operating from 5 K to 80 K. HTS module is based up on commercially available rare earth cuprate oxide superconductor based BSCCO-2223 tapes. For testing purpose, we have developed bottom lap joints using composite magnesium diboride (MgB <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sub> ) wires as an intermediate between HTS module and NbTi: Cu cable that act as a shunt between CL pair. Such a hybrid concept is adopted as a next step to developing MgB <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sub> superconducting current feeder which could be operated near 20 K and save cryogenic cost in future fusion machines. Here, we report the salient features, basic details of HTS CL, superconducting joints fabrication, its test set-up and experimental results. The inference from test results are then reported and discussed in detail.

Thermostructural Analysis of Large Cryopumping Test Facility

To create high and ultra-high vacuum environments in large-size chambers for applications in space research, nuclear fusion, accelerators, etc., vacuum pumps with fast pumping speeds are essentially required. To cater to this need, one promising solution is the cryopump, which offers efficiency, a low cost, and applicability. The Institute for Plasma Research is working to develop large-size cryopumps and to develop performance testing and design validation for such cryopumps. In this paper, the Large Cryopumping Test Facility (LCTF) is conceptualized. It houses a large cryopump designed to achieve the pumping speed of ~50 000 L/s for nitrogen gas. The LCTF includes a dome chamber to make the pumping speed measurements per the American Vacuum Society standard and a hybrid cryopump with a 1250-mm opening diameter. The present work illustrates the configuration of the cryopump and its subsystems. The pump will be cooled by liquid nitrogen (LN2) to an 80-K temperature and a Gifford-McMahon cryocooler for up to a 10-K temperature. Here, a new geometrical concept for the pump is considered where the annulus LN2 bath cools the array panels and baffles and also acts as a radiation shield to protect the 10-K cryopanels from radiation heat load. A detailed investigation of the thermal and structural analysis for the LCTF is discussed to validate the performance of the pump and the robustness of the system.

Design, analysis, fabrication and testing of 100 kV, 100 mA DC full-wave voltage multiplier (FWVM) modular unit for accelerator power supply

The 100 kV, 100 mA DC full-wave voltage multiplier (FWVM) modular unit is being developed for accelerator power supply and other plasma applications at Institute for Plasma Research (IPR). The high voltage engineering design involved in fabrication architecture and assembly of 100 kV, 100 mA DC FWVM module is the main focus of this paper. This FWVM module has 2 stages of Cock-Croft Walton voltage multiplier circuit considering the required optimum number of stages for final 500 kV voltage output. The FWVM unit is fed by a center tapped High Voltage High Frequency (HVHF) transformer. Electrical circuit simulations have been carried out to ensure the electrical performance parameters. The maximum value of the fault current during ground fault is 50 A as per simulation results. The 100 kV, 100 mA FWVM module is designed, fabricated and tested at 100 kV. Simulation Results, fabrication details, engineering design details and test results have been presented in this paper.

Boron Carbide as High-Energy Radiation Shielding Material for ITER

Boron carbide (B4C) has emerged as a potential material, which can be used for high-energy radiation shielding in International Thermonuclear Experimental Reactor (ITER). This is one of the hardest ceramic materials with required properties, such as low density, high hardness, high toughness, high melting point, chemical inertness, outstanding thermal–electrical characteristics, and most importantly having a high cross section for the absorption of neutrons. Recently, ITER-India, Institute for Plasma Research (IPR) initiated prototype activities for the development of hot-pressed B4C blocks/pellets. ITER-India with support from an Indian Industry has demonstrated the manufacturing capability for large-scale, vacuum-hot-pressed blocks with machining feasibility for the final product (shielding block). Development activities have been carried out as per ASTM C750 (Nuclear Grade B4C Powder), ASTM C751 (Nuclear Grade B4C blocks/pellets), and other stringent requirements of ITER. The B4C blocks/pellets have been fabricated in a vacuum at the high-temperature range of 2050 °C–2100 °C and high pressure of ~30 MPa. To qualify this material as per ITER requirements, its chemical composition, mechanical, and physical properties are studied and validated. Scanning electron microscopy (SEM) studies were conducted to calculate the grain size in the microstructure. As this material is to be used in an ultrahigh vacuum (UHV) environment in ITER ports and systems, the outgassing rate of B4C is also determined. We ascertained outgassing rate <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$\le1\,\,\times \,\,10^{-8}$ </tex-math></inline-formula> Pam <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$^{3}\text{s}^{-1}\text{m}^{-2}$ </tex-math></inline-formula> at 100 °C of B4C as per the ITER vacuum handbook (IVH) as well as ITER-derived requirements for ports. The main reason to achieve this outgassing rate is the process of fabrication used as it does not include any sintering aids and additives; hence, it is a unique hot-pressing technique, which is better suited for nuclear applications. This article describes the details of the study related to B4C blocks/pellets development and toward the qualification as per shielding material requirements for ITER.

Design and development of LN2 cooled cryopump for application in high heat flux test facility

• A liquid nitrogen cooled sorption cryopump is developed for the High Heat Flux Test Facility at IPR. • Design details, fabrication details, operational concept and thermo-structural analysis results are described. • The pump geometrical concept is novel because it provides ease of assembly, integration and trouble free operation in horizontal and vertical direction mounting. • The pump has 250 mm opening and offers pumping speed of ∼5106.6 l/s for water vapour and ∼1197 l/s for nitrogen using liquid nitrogen as coolant. • The pump integration and operation with High Heat Flux Test Facility is discussed. High Heat Flux Test Facility (HHFTF) at Institute for Plasma Research is established for testing thermal performance of Plasma Facing Components (PFC) and Plasma Facing Materials (PFM) that are expected to withstand steady-state and transient heat flux of the order of 10 MW/m 2 and 20 MW/m 2 , respectively, expected in plasma fusion devices. During high heat flux testing of PFCs and PFMs, water vapour and other trapped gases are released. For the pumping need, a cryocooler based commercial cryopump and a turbo-pump is used. In addition to that, an indigenously developed liquid nitrogen cooled cryopump is mounted to the High Heat Flux (HHF) test facility. The developed cryopump has 250CF inlet flange and mounted vertically downward to an angle port (50°) to the D-shaped vacuum chamber of the HHF facility. The pump has integrated liquid nitrogen bath to provide stable cooling to the cryopanels and radiation shield. Cryopanels are made of copper and coated with micro-porous activated charcoal. The pump's geometrical concept is novel because it provides ease of assembly, integration and trouble free operation in horizontal and vertical direction mounting. The pump offers pumping speed of ∼5106.6 l/s for water vapour and ∼1197 l/s for nitrogen using liquid nitrogen as coolant. The pump geometry, thermal and structural analysis, fabrication and experimental details are discussed in this paper. After integrating the cryopump to the HHF test facility, performance studies were carried out and initial test results are also discussed.

Numerical prediction of the operating point for the cryogenic twin-screw hydrogen extruder system

An extruder-type cryogenic pellet injector system for plasma fuelling is under research at Institute for Plasma Research (IPR), India. A twin-screw extruder is a most stable device in the form of closed volumes of hydrogen between screw threads and promising process due to continuous production of hydrogen pellet for plasma reactor. In the present investigation, a non-Newtonian, non-isothermal CFD model was developed which modeled the shear rate and temperature-dependent viscosity in the Herschel Bulkley model. Brinkman number (Br) varies from 0.15 to 0.46 at 5 and 15 rpm respectively. Due to increasing the screw rotation speed for a given throughput, the shear rate increases (therefore, also the Br) and results in larger viscous dissipation. Solid hydrogen temperature is predicted at the location of the flight gap and intermeshing zone for the different barrel temperatures under varying screw rotation speeds (5–15 rpm). Prediction of hydrogen temperature at the intermeshing zone of the extruder system plays a vital role to decide the barrel temperature. Due to more number of moving surfaces at the intermeshing zone of the extruder system, the temperature of solid hydrogen is higher and increases above the melting point temperature. The effect of barrel wall temperature and screw rotation speeds (5–15 rpm) on the viscous dissipation rate and pressure development at required throughput was also examined for an extruder system. It is important to estimate the barrel wall temperature to get an operating point and corresponding viscous dissipation rate, which determines the cooling load required for extruder-die set-up. The results show that as the die wall temperature increases, the viscous dissipation, as well as the pressure drop decreases in the die. The investigation showed that the die’s wall temperature and screw rotation speed affect the operating point of the extruder-die system.

Experimental investigations on electrical-insulation performance of Al2O3 coatings for high temperature PbLi liquid metal applications

Electrical-insulating coatings are of great importance for applications in liquid metal breeder/coolant based systems relevant to nuclear fusion power plants. In specific to lead–lithium eutectic (Pb-16Li), a candidate breeder material, such coatings are being actively investigated worldwide for their criticality in addressing various functionalities including, but not limited to, reduction in Magneto-Hydro Dynamics (MHD) pressure drop, corrosion resistance to structural materials and development of specific diagnostics, like two-phase detection techniques. For such applications, a candidate coating must be demonstrated for its compatibility with corrosive media, endurance towards high operational temperatures and integrity of electrical-insulation over long operational durations without substantial degradation. Further, quantitative performance assessment of coated substrates within PbLi environment over long operational durations is rendered difficult due to scarcity of relevant in-situ insulation resistance data. To address this shortfall, a preliminary experimental study was performed at Institute for Plasma research (IPR) towards application of AlPO4 bonded high-purity alumina (Al2O3) coatings on SS-316L substrates and further rigorous validation in static PbLi environment. The adopted coating process required a low temperature heat treatment (<430 °C) and could yield average coating thicknesses in the range of ∼ 100 µm – 500 µm. Coated samples were validated for their electrical-insulation integrity in static PbLi over two test campaigns for continuous durations of over 700 h and 1360 h, including thermal cycling, at operational temperature in the range of 300 °C-400 °C. Volumetric electrical-resistivity, estimated through high-voltage insulation resistance measurements at relevant temperatures, remained of the order of 109-1011 Ω-cm without significant degradation. In-situ estimations of thermal derating factors establish good electrical-insulation characteristics after long term exposure to liquid PbLi. This paper presents details of utilized coating application methods, coating thickness estimations, liquid metal test set-up, insulation performance and critical observations from SEM/EDX and XRD analysis on the tested samples.

DPEx-II: a new dusty plasma device capable of producing large sized DC coulomb crystals

The creation of a spatially extended stable DC complex plasma crystal is a big experimental challenge and a topical area of research in the field of dusty plasmas. In this paper we describe a newly built and commissioned dusty plasma experimental (DPEx-II) device at the Institute for Plasma Research. The device can support the formation of large sized Coulomb crystals in a DC glow discharge plasma. The plasma in this L-shaped table-top glass chamber is produced between a circular anode and a long tray shaped cathode. It is characterized with the help of various electrostatic probes over a range of discharge conditions. The dust particles are introduced by a dust dispenser to form a strongly coupled Coulomb crystal in the cathode sheath region. The unique asymmetric electrode configuration minimizes the heating of dust particles and facilitates the formation of crystalline structures with a maximum achievable dimension of 40 cm × 15 cm using this device. A larger crystal has numerous advantages over smaller ones, such as higher structural homogeneity, fewer defects, lower statistical errors due to finite size effects etc. A host of diagnostics tools are provided to characterize the Coulomb crystal. Results of a few initial experiments aimed at demonstrating the technical capabilities of the device and its potential for future dusty plasma research, are reported.

Simultaneous measurement of effective thermal conductivity and effective thermal diffusivity of Li2TiO3 pebble bed using transient hot-wire technique

Lithium-based ceramics in the form of pebble beds have been considered for tritium breeder material in the fusion reactor's breeder blanket. It is essential to study the thermal characteristics of these ceramic pebble beds subjected to fusion relevant conditions. Effective thermal conductivity (k), effective thermal diffusivity (α) and effective specific heat (cp) of a packed bed are some of the crucial parameters for the design of breeder blanket module. In the present study, the transient hot-wire technique was used to measurek, α and cp of lithium metatitanate (Li2TiO3) pebble bed fabricated at Institute for Plasma Research, India. Thermal properties of Li2TiO3 pebble bed (1 ± 0.15 mm pebble diameter and ∼63% packing fraction) are measured within the temperature range of 45 °C to 800 °C in stagnant helium gas environment. The filling gas pressure variation effect on the Li2TiO3 pebble bed's thermal properties for the pressure range of 0.105 MPa to 0.4 MPa has also been studied. Equations are suggested for k and α of Li2TiO3 pebble bed as a function of temperature at different pressure in the helium gas environment.

Numerical study of 3D MHD flow of Pb-Li liquid metal in a rectangular U-bend

The eutectic Pb-Li alloy has been chosen as a candidate material for the liquid breeder blanket, as it offers a unique combination of tritium breeding neutron absorbing and neutron multiplying capabilities. In fusion blanket, molten Pb-Li moves under plasma confining toroidal magnetic field, producing an induced electric current inside the liquid metal due to the interaction of the moving fluid with the magnetic field. The coupling of induced electric current and magnetic field generates a Lorentz force opposite to the flow direction, and this in turn, modifies the flow profile. The experimental and numerical flow studies of liquid Pb-Li under transverse magnetic field are of great importance, as it directly impacts the blanket performance. A liquid Lead Lithium MHD loop is being developed at Institute for Plasma Research (IPR), Gujarat, India for isothermal and thermo-fluid MHD studies in blanket relevant flow geometries such as sudden expansion/contraction, coupled channels and multiple bends. A test mockup with rectangular flow cross-section and having bends perpendicular to the magnetic field has been fabricated. A 3D MHD flow analysis has been performed numerically for the test mock up at a magnetic field of 1.4T (Hartmann number of order of 1500). The fabrication details of test mockup and the results of the Pb-Li flow analysis are presented and discussed. The flow field and pressure distribution in the presence and absence of the magnetic field are also compared. The existence of recirculation zones and their redistribution in the presence of magnetic field are discussed.

Radioactivation analysis of 14 MeV neutron generator facility

Institute for Plasma Research (IPR) is establishing an intense neutron generator facility. It is an accelerator-based 14 MeV neutron generator that produces 1012 neutrons per second. The neutron generator facility has various components that are made of different kinds of materials. It gets radio-activated due to the direct interaction of neutrons and secondary radiations. The radio activation of components has short term and long term effects in neutron generator operation and maintenance. The facility is built with concrete shielding. It will be operated at atmospheric pressure. The concrete walls and air in the hall also face neutron irradiation, which needs to be estimated for precautionary safety measures during maintenance. Long term operation of neutron generator can also affect the ground soil. The production of tritium in the soil can also become an issue for the general public health and can create a safety concern. Therefore, the simulation has been carried out to estimate the radio-activation of the neutron generator facility, which may impact neutron generator operation and maintenance. The estimation will also provide the level of radioactive waste generated due to the long term operation of the neutron generator. The operational licensing of the neutron generator is also required the estimation of radionuclide and dose rates after irradiation. The present work contains the neutron activation of neutron generators components that are present in the hall. The analysis is conducted for air activation, soil activation, concrete wall activation, and doors activation. The generation of ozone due to radiation interaction with air is also estimated to avoid ozone hazards during the maintenance. The simulation has been carried out using the Monte Carlo radiation transport tool and radionuclide inventory estimation tool FISPACT. Estimated results are compared with the regulatory limits. The analyses conclude that the facility is safe for long term operation.