A. Mallick
A5069868131- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Nuclear physics research studies
- Nuclear Materials and Properties
- Radiation Detection and Scintillator Technologies
- Radiation Therapy and Dosimetry
- Graphite, nuclear technology, radiation studies
- Particle Detector Development and Performance
- X-ray Spectroscopy and Fluorescence Analysis
- Atomic and Subatomic Physics Research
- Superconducting Materials and Applications
- Nuclear Engineering Thermal-Hydraulics
- Particle accelerators and beam dynamics
- Particle Accelerators and Free-Electron Lasers
- Muon and positron interactions and applications
- Neutrino Physics Research
- Particle physics theoretical and experimental studies
- Radioactivity and Radon Measurements
- High-Energy Particle Collisions Research
- Nuclear and radioactivity studies
- Advanced NMR Techniques and Applications
- Astro and Planetary Science
Bhabha Atomic Research Center Hospital
2024
Bhabha Atomic Research Centre
2013-2023
Homi Bhabha National Institute
2019-2023
University of Hertfordshire
2017
Australian National University
2017
This work reports on accurate, high-resolution measurements of the $^{25}$Mg($n, \gamma$)$^{26}$Mg and tot$) cross sections in neutron energy range from thermal to about 300 keV, leading a significantly improved parametrization. The relevant resonances for $n+^{25}$Mg were characterized combined R-matrix analysis experimental data. resulted an unambiguous spin/parity assignment corresponding excited states $^{26}$Mg. With this information upper limits reaction rates $^{22}$Ne($\alpha,...
The 241Am(n,γ) cross section has been measured at the n_TOF facility CERN using deuterated benzene liquid scintillators, commonly known as C6D6 detectors, and time-of-flight spectrometry. results in resolved resonance range bring new constraints to evaluations below 150 eV, energy upper limit was extended from 320 eV with a total of 172 resonances not present current evaluations. thermal capture found be σth=678±68 b, which is good agreement most previous measurements. unresolved region...
Neutron-induced fission cross sections of 238U and 235U are used as standards in the fast neutron region up to 200 MeV. A high accuracy is relevant experimentally determine other reaction sections. Therefore, detection effciency should be corrected by using angular distribution fragments (FFAD), which barely known above 20 In addition, produced highly excited deformed nuclei an important observable investigate nuclear process.
The aim of this work is to provide a precise and accurate measurement the $^{238}\mathrm{U}$($n,\ensuremath{\gamma}$) reaction cross section in energy region from 1 eV 700 keV. This fundamental importance for design calculations nuclear reactors, governing behavior reactor core. In particular, fast which are experiencing growing interest their ability burn radioactive waste, operate high neutron spectrum. most recent evaluations disagree due inconsistencies existing measurements up 15%....
Abstract An experiment was carried out to study the feasibility of 99 Mo production using an electron accelerator based epi-cadmium neutron source. The neutrons were produced by interaction bremsstrahlung end-point energy 10 MeV with BeO blocks and thus moderated High Density Polyethylene blocks. Effective cross-section 98 Mo(n,γ) reaction measured foil activation method. enhancement in effective due resonances region observed. photons production/transport experimental set-up simulated FLUKA...
The $^{33}\mathrm{S}(n,\ensuremath{\alpha})^{30}\mathrm{Si}$ cross section has been measured at the neutron time-of-flight ($\mathrm{n}_\mathrm{TOF}$) facility CERN in energy range from 10 to 300 keV relative $^{10}\mathrm{B}(n,\ensuremath{\alpha})^{7}\mathrm{Li}$ cross-section standard. Both reactions were simultaneously with a set of micromegas detectors. flight path 185 m allowed us obtain high-energy resolution. An accurate description resonances performed by means multilevel...
The accuracy on neutron capture cross section of fissile isotopes must be improved for the design future nuclear systems such as Gen-IV reactors and Accelerator Driven Systems. High Priority Request List Nuclear Energy Agency, which lists most important data requirements, includes also sections 233,235U 239,241Pu. A specific experimental setup has been used at CERN n_TOF facility measurement 235U by a set micromegas fission detectors placed inside segmented BaF2 Total Absorption Calorimeter.
We measured the neutron capture-to-fission cross-section ratio ($\ensuremath{\alpha}$ ratio) and capture cross section of $^{235}\mathrm{U}$ between 0.2 200 eV at n_TOF facility CERN. The simultaneous measurement neutron-induced fission rates was performed by means ${\mathrm{BaF}}_{2}$ Total Absorption Calorimeter (TAC), used for detection $\ensuremath{\gamma}$ rays, in combination with a set micromegas detectors as tagging detectors. energy dependence obtained help $^{6}\mathrm{Li}(n,t)$...
Neutron capture cross sections are the key nuclear physics input to study slow neutron process, which is responsible for forming about half of elemental abundances above Fe. Stellar section can be measured by time-of-flight technique, or activation. Both techniques will discussed and recent experiments in Fe/Ni mass region presented.
Background: Stellar nucleosynthesis of elements heavier than iron is driven by neutron capture processes. $^{92}\mathrm{Zr}$ positioned at a strategic point along the slow path, given its proximity to magic number $N=50$ and position matching region between weak main processes.Purpose: In parallel with recent improved astronomical data, extraction accurate Maxwellian averaged cross sections (MACSs) derived from more complete set resonance parameters should allow for better understanding...
Monte Carlo neutron transport codes have traditionally used a fixed-source scheme to simulate subcritical system with an external source. The efficiency of this is known depend on the subcriticality level: lower is, worse efficiency. We investigated alternate iterative scheme, namely, k-source (IKS) for study multiplication. Our results show that not only as accurate, effective, and computationally efficient but also has additional advantage being weakly dependent level. Also, unaffected by...
Thin 33S samples for the study of 33S(n,α)30Si cross-section at n_TOF facility CERN were made by thermal evaporation powder onto a dedicated substrate kapton covered with thin layers copper, chromium and titanium. This method has provided first time bare sulfur few centimeters in diameter. The have shown an excellent adherence no mass loss after years sublimation vacuum room temperature. determination thickness been performed means Rutherford backscattering spectrometry. successfully tested...
A Neutron Transport Analysis Code (ν-TRAC) based on Method of Characteristics (MOC) has been developed for reactor physics studies at the lattice level. The code capabilities to model 1-D slab and 2-D hexagonal/square geometry cells with arbitrary arrangements fuel pins inside later. Widely used WIMS-D format nuclear data library is neutron transport simulation, making useful practical design studies. validated extensively by analyzing numerous benchmark problems. This paper presents...
The use of the Monte Carlo (MC) method for obtaining higher modes is an active area current research. faces several difficulties in its implementation practical problems. study simpler models this context may be expected to provide insights into some these This technical note describes development a fission matrix algorithm based on diffusion theory MC model obtain fundamental and λ eigenvalues eigenvectors (modes) reactor. A estimating variance estimated using first-order perturbation also...
The radiative capture cross section of 238U is very important for the developing new reactor technologies and safety existing ones. Here preliminary results 238U(n,γ) measurement performed at n_TOF with C6D6 scintillation detectors are presented, paying particular attention to data reduction background subtraction.
We have measured the radiative neutron-capture cross section and total neutron-induced of one most important isotopes for s process, 25Mg. The measurements been carried out at neutron time-of-flight facilities n_TOF CERN (Switzerland) GELINA installed EC-JRC-IRMM (Belgium). sections as a function energy up to approximately 300 keV, covering region interest process. data analysis is ongoing preliminary results show potential relevance