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Senecha, V. K.

Paper Title Page
TUPMA115 Simulations of Non-uniform High Density Electronegative Plasma for Optimization of H- ions and their Extraction 265
 
  • A . Kumar, S. Kotaiah
    RRCAT, Indore (M. P.)
  • V. K. Senecha
    KEK, Ibaraki
 
  Numerical simulations of radio frequency multi-cusp volume type H- ion source have been performed under non-uniform electronegative plasma equilibrium conditions in order to understand the physics of formation of various ion species (H+, H-, e- etc.) and for optimization of H- ion formation and extraction. Coupled momentum balance equations along with continuity equations were solved in a cylindrical geometry to obtain the density profile of various ion species. The relevant cross-section data available in the literature as a function of temperature has been used in the computation. The hydrodynamic model of plasma in equilibrium with background neutral gas has been used. Low degree of ionization ( ~1%) has been assumed. The collision less sheath formation, penetration of electric and magnetic field and power requirement to sustain the plasma has been worked out numerically. An effort has been made to give a self-consistent numerical scheme for the solution of inductively coupled plasma (ICP) in equilibrium, and the results obtained have been presented  
THPMA111 Target Assembly Design and Neutronics Study for Indian Spallation Neutron Source Using NMTC/JAM Code 797
 
  • V. K. Senecha, M. Kawai
    KEK, Ibaraki
 
  Target-moderator-reflector assembly (TMRA) design studies for the best neutronics performance of the proposed Indian Spallation Neutron Source(ISNS) have been carried out using high energy particle transport code NMTC/JAM. The issues relevant for TMRA design like selection of target material, effect of target shape and dimensions and placement of moderator, suitable material for reflector its size have been addressed using the code calculations. NMTC/JAM code calculations have shown that the neutron yield per proton for thick Pb target for varying target lengths are in good agreement within the error limit with the results reported by experimental group and matching with the results of JAERI code calculations (JAERI 'Data/code 2001-07). Different geometrical configurations for TMRA were attempted and resulted tally's for track-length, surface crossing, nuclide yield, heat deposition, and time tallies for the neutron have been calculated. It has been observed that wing type structure of moderator position with respect to the target is suitable for optimum neutron yield in the pulsed mode.

(1) NMTC/JAM, JAERI code 2001-007, Koji Niita et al.(2001).(2)Development of target for KENS, M. Kawai et al. Procd. 2nd Workshop on Materials Tech. for spallation neutron source,141(2001).