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Neutronics Calculations of Prismatic High-temperature Gas Cooled Reactor by Deterministic Method Using DONJON and DRAGON Codes and Comparison with Results of Probabilistic Methods (Monte Carlo).

Mansouri Hassan Abadi, Javad | 2014

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 46463 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Ghofrani, Mohammad Bagher
  7. Abstract:
  8. HTGRs are considered as 4th generation reactors which have prominent characteristics such as inherent safety, lower safety costs, High efficiency and high temperature applications. the most important challenges in developing these reactors is providing appropriate codes in design, simulating their performance and analysis of them. In this thesis, a japanese prismatic HTTR reactor has been selected as a reference reactor and the neurotic’s calculations implementation studied at cold zero power (CZP) and hot full power (HFP) states using DRAGON cell calculation codes and DONJON core computations. At CZP state, One group and two group radial & axial flux distribution, control rod critical height and effective multiplication factor at experimental critical height with & without consideration of nitrogen as impurity in fuel blocks. Moreover, at HFP state, effective multiplication factor and prompt neutron life time (lp) have been calculated. finaly Isothermal temperature coefficients have been calculated. verification of evaluated results showed good consistency with available experimental results. Finally, results of the deterministic calculation and probabilistic methods (Monte Carlo) were compared. Comparative calculations showed relatively close results between methods of deterministic and probabilistic showing that even in some cases, results has been improved in comparison to the probabilistic (Monte Carlo). Also high-speed run of the deterministic codes caused preference of this method to probabilistic methods (Monte Carlo)
  9. Keywords:
  10. Cold Zero Power (CZP)State ; Hot Fuu Power (HFP) State ; Probabilistic Methods ; Monte Carlo Method ; High Themprature Gas-Cooled Reactor (HTGR) ; DRAGON Cell Calculation Code ; DANJON Core Calculation Code

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