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Zhou X, Liu Z, Cao L, Cao L, Wu H, Han Y, Tang C. Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2020. [DOI: 10.1115/1.4045035] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Abstract
The constructive solid geometry (CSG) method is widely used in the Monte Carlo community because of its geometry flexibility. As the requirements of designing new reactors and development of deterministic methods, the CSG method is adopted for the geometry modeling in the deterministic numerical nuclear reactor physics codes to construct complex geometries in recent years. In the new developed numerical nuclear reactor physics code NECP-X, the CSG method is also implemented to expand its geometric modeling capability, but it is difficult to efficiently calculate the volume of complex geometries. This work develops a new efficient method for calculating volume of arbitrarily complex geometries for NECP-X. Rather than implementing the sampling method, the new developed method is based on the characteristic ray information, which is used for the method of characteristics (MOC) sweeping in NECP-X. The implementation shows that this method is very convenient to be applied to the MOC codes. A set of cases such as pin-cell and hexagonal rod-bundle assembly problems are tested to show the accuracy and performance.
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Affiliation(s)
- Xinyu Zhou
- School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049, China
| | - Zhouyu Liu
- School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049, China
| | - Lu Cao
- School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049, China
| | - Liangzhi Cao
- School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049, China
| | - Hongchun Wu
- School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi 710049, China
| | - Yu Han
- Core Design Department, Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
| | - Chuntao Tang
- Core Design Department, Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
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Liu Z, Wu H, Cao L. Geometry pretreatment method for the 3D modular characteristic method based on AutoCAD. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.05.039] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Filippone WL, Smith MS, Woolf S, Garth JC. The Streaming Ray Formulation of Electron Transport. NUCL SCI ENG 2017. [DOI: 10.13182/nse87-a20430] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- W. L. Filippone
- University of Arizona, Department of Nuclear and Energy Engineering, Tucson, Arizona 85721
| | - M. S. Smith
- University of Arizona, Department of Nuclear and Energy Engineering, Tucson, Arizona 85721
| | - S. Woolf
- Arcon Corporation, Waltham, Massachusetts 02154
| | - J. C. Garth
- Rome Air Development Center, Solid State Sciences Division, Hanscom AFB, Massachusetts 01731
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Affiliation(s)
- S. P. Monahan
- University of Arizona Department of Nuclear and Energy Engineering, Tucson, Arizona 85721
| | - W. L. Filippone
- University of Arizona Department of Nuclear and Energy Engineering, Tucson, Arizona 85721
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A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.07.012] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Liu Z, Wu H, Cao L, Chen Q, Li Y. A new three-dimensional method of characteristics for the neutron transport calculation. ANN NUCL ENERGY 2011. [DOI: 10.1016/j.anucene.2010.09.021] [Citation(s) in RCA: 36] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Development and verification of an MOC code employing assembly modular ray tracing and efficient acceleration techniques. ANN NUCL ENERGY 2009. [DOI: 10.1016/j.anucene.2009.06.007] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Cho NZ, Chang JH. SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION. NUCLEAR ENGINEERING AND TECHNOLOGY 2009. [DOI: 10.5516/net.2009.41.4.381] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Lee GS, Cho NZ. Two-dimensional whole-core transport calculationsof the oecd benchmark problem C5G7 MOX by the CRX code. PROGRESS IN NUCLEAR ENERGY 2004. [DOI: 10.1016/j.pnucene.2004.09.008] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Suslov I. Improvements in the long characteristics method and their efficiency for deep penetration calculations. PROGRESS IN NUCLEAR ENERGY 2001. [DOI: 10.1016/s0149-1970(01)00014-2] [Citation(s) in RCA: 10] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Hong SG, Cho NZ. CRX: A code for rectangular and hexagonal lattices based on the method of characteristics. ANN NUCL ENERGY 1998. [DOI: 10.1016/s0306-4549(97)00113-8] [Citation(s) in RCA: 46] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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Germogenova TA. Development of numerical methods in problems of radiation propagation. ATOM ENERGY+ 1990. [DOI: 10.1007/bf02086948] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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