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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2005.1
- 수록면
- 25 - 78 (54page)
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As a key and core knowledge for the design of various types of nuclear reactors, the discipline of reactor physics has been advanced continually in the past six decades and has led to a very sophisticated fabric of analysis methods and computer codes in use today. Notwithstanding, the discipline faces interesting challenges from next-generation nuclear reactors and innovative new fuel designs in the coming.
After presenting a brief overview of important tasks and steps involved in the nuclear design and analysis of a reactor, this article focuses on the currently-used design and analysis methods, issues and limitations, and current activities to resolve them as follows:
(1) Derivation of the multigroup transport equations and the multigroup diffusion equations, with representative solution methods thereof.
(2) Elements of modern (now almost three decades old) diffusion nodal methods.
(3) Limitations of nodal methods such as transverse integration, flux reconstruction, and analysis of UO2-MOX mixed cores. Homogenization and related issues.
(4) Description of the analytic function expansion nodal (AFEN) method.
(5) Ongoing efforts for three-dimensional whole-core heterogeneous transport calculations and acceleration methods.
(6) Elements of spatial kinetics calculation methods and coupled neutronics and thermal-hydraulics transient analysis.
(7) Identification of future research and development areas in advanced reactors and Generation-IV reactors, in particular, in very high temperature gas reactor (VHTR) cores.
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참고문헌 (34)
참고문헌 신청
/ 1966. / Iterative Solution of Elliptic Systems
/ 1972 / A Characteristics Formulation of the NeutronTransport Equation in Complicated Geometries 1108
/ 1975. / The MIT Press
/ 1977 / InterfaceCurrent Techniques for Multidimensional ReactorCalculations 30 : 123 ~
/ 19781978 / A New approach to Homogenization and GroupCondensation : 303 ~
/ 1972 / A Characteristics Formulation of the NeutronTransport Equation in Complicated Geometries 1108
/ 1975. / The MIT Press
/ 1977 / InterfaceCurrent Techniques for Multidimensional ReactorCalculations 30 : 123 ~
/ 19781978 / A New approach to Homogenization and GroupCondensation : 303 ~
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