Dissertation
Dissertation > Industrial Technology > Nuclear technology > Engineering of Nuclear Reactors > Reactor physics and design, calculation > Reactor theory calculations > Calculation method

Research on Neutron Distribution in Reactor and Design of Radiation Shielding

Author YangJiaYin
Tutor ShenMingQi
School Harbin Engineering University
Course Radiation protection and environmental protection
Keywords MCNP code Hexagonal core Core physics calculations Shielding calculation
CLC TL329.2
Type Master's thesis
Year 2010
Downloads 324
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Due to the rapidly increasing demand of energy , nuclear power world wide attention to the sharp increase in the number of nuclear power plants , reactor type innovation . Reactor design based on our long-term consideration of autonomy , the existing mature type of reactor and reactor physics calculations and analysis, and assessment of the safety of the reactor . In this paper, Monte Carlo ( MC ) calculation code MCNP core physical characteristics , including the critical state of the neutron multiplication factor Keff , neutron spectrum , neutron and photon flux density distribution of the power density distribution of these parameters . Due to the relatively large size of the reactor , the neutron and photon flux density in the core and reactor components by many orders of magnitude difference , the results are not satisfactory critical source power density nodal method to calculate this deep penetration shielding calculation , basket , pressure vessels , the average neutron flux density . The nodal method using a common source, and the need to give the correct source description . The results show that the core neutron and photon flux density on the radial and axial distribution are in good agreement with the actual , more gentle pressure vessels and the flux density in a heap outside the detection area , the shielding effect is ideal . First , calculate the power density distribution , and the calculation result as the second step shielding calculation data base provides a reasonable solution for large-scale reactor shielding .

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