Requirement of Temperature Dependent Nuclear Cross  Sections for MCNP Calculation

CHAI Xiao-ming; WANG Kan; YU Gang-lin

doi:10.11804/NuclPhysRev.23.02.111

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Volume 23 Issue 2

Jun. 2006

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Article Navigation > Nuclear Physics Review > 2006 > 23(2): 111-114

CHAI Xiao-ming, WANG Kan, YU Gang-lin. Requirement of Temperature Dependent Nuclear Cross Sections for MCNP Calculation[J]. Nuclear Physics Review, 2006, 23(2): 111-114. doi: 10.11804/NuclPhysRev.23.02.111

Citation:

CHAI Xiao-ming, WANG Kan, YU Gang-lin. Requirement of Temperature Dependent Nuclear Cross Sections for MCNP Calculation[J]. Nuclear Physics Review, 2006, 23(2): 111-114. doi: 10.11804/NuclPhysRev.23.02.111

Requirement of Temperature Dependent Nuclear Cross Sections for MCNP Calculation

doi: 10.11804/NuclPhysRev.23.02.111

Department of Engineering Physics, Tsinghua University, Beijing 100084, China

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2006-06-20

Abstract

Due to the advantage of geometry simulation and nuclear data, the code MCNP is now widely used in the reactor analysis. Based on our calculation of the fuel temperature reactivity coefficient benchmark, it is quantificationally proved that MCNP with its own cross section library can＇ t be used to simulate the reactor accurately and to calculate the temperature reactivity coefficient. Furthermore, we use MCNP- 4C with a database that contains temperature dependent nuclear cross sections to calculate the benchmark. The results are well agreement with benchmark results. This means that, with the temperature dependent nuclear cross sections library, MCNP can calculate the temperature reactivity coefficient and reactor multiplication factor accurately. So the temperature dependent nuclear cross section library should be processed to meet the requirement of reactor calculation.
- （MCNP code,
- nuclear cross section library,
- multiplication factor,
- temperature reactivity coefficient,
- benchmark）
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通讯作者: 陈斌, bchen63@163.com

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沈阳化工大学材料科学与工程学院沈阳 110142

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Requirement of Temperature Dependent Nuclear Cross Sections for MCNP Calculation

doi: 10.11804/NuclPhysRev.23.02.111

Department of Engineering Physics, Tsinghua University, Beijing 100084, China

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2006-06-20

Key words:

Abstract: Due to the advantage of geometry simulation and nuclear data, the code MCNP is now widely used in the reactor analysis. Based on our calculation of the fuel temperature reactivity coefficient benchmark, it is quantificationally proved that MCNP with its own cross section library can＇ t be used to simulate the reactor accurately and to calculate the temperature reactivity coefficient. Furthermore, we use MCNP- 4C with a database that contains temperature dependent nuclear cross sections to calculate the benchmark. The results are well agreement with benchmark results. This means that, with the temperature dependent nuclear cross sections library, MCNP can calculate the temperature reactivity coefficient and reactor multiplication factor accurately. So the temperature dependent nuclear cross section library should be processed to meet the requirement of reactor calculation.

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