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Coupling of ANISN & MCNP Computer Codes for Neutron Importance Calculation

Hassanzadeh, Reza | 2012

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 43350 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Vosoughi, Naser
  7. Abstract:
  8. For many reasons the Montecarlo method is chosen for investigation of problems like shielding. Nowadays, superiority of utilizing the codes based upon Montecarlo methods such as using cross sections with continuous energy or using exact models of complex geometries, is obvious for everyone. But obtaining results with least possible variance is extremely important. variance reduction methods usedfor achieving exact results with less calculating time. Up to now in the MCNP codes, many methods have been utilized for reducing the variance. One of the methods which have recently attracted attentions is using the importance function. For obtaining importance function we need to solve the deterministic transport equation and also in its adjoint form. The deterministic ANISN code has been choosed for this purpose. But making use of this code could be completely sophisticated and time consuming, and also it requires the user to have knowledge about deterministic codes. Therefore, we have worked on special method which automatically generates the input files for the ANISN codes. Hence, the importance functions are derived from the output of this code and then they are imposed to the input of the MCNP code. Finally, with running the corrected MCNP input, we would obtain outputs with smaller variance. ANISN has a multigroup library but MCNP’s library is continuous. For solving this problem we produced multigroup library in suitable format for this codes. Finally with short running time, reach to low variance.

  9. Keywords:
  10. Variance Reduction ; Monte Carlo N-Particle (MCNP)Code ; ANISN Code ; Importance Function

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