Benchmark Analysis of TRIGA Mark II Reactivity Experiment Using a Continuous Energy Monte Carlo Code MCNP

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概要

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• The benchmark analysis of reactivity experiments in the TRIGA-II core at the Musashi Institute of Technology Research Reactor (Musashi reactor, 100 kW) was performed by a three-dimensional continuous-energy Monte Carlo code MCNP4A. The reactivity worth and integral reactivity curves of the control rods as well as the reactivity worth distributions of fuel and graphite elements were used in the validation process of the physical model and neutron cross section data from the ENDF/B-V evaluation. The calculated values of integral reactivity curves of the control rods were in agreement with the experimental data obtained by the period method. The integral worth measured by the rod drop method was also consistent with the calculation. The calculated values of the fuel and the graphite element worth distributions were consistent with the measured ones within the statistical error estimates. These results showed that the exact core configuration including the control rod positions to reproduce the fission source distribution in the experiment must be introduced into the calculation core for obtaining the precise solution. It can be concluded that our simulation model of the TRIGA-II core is precise enough to reproduce the control rod worth, fuel and graphite elements reactivity worth distributions.

• 一般社団法人 日本原子力学会の論文
• 2000-12-25

著者

• Matsumoto Tetsuo

  Atomic Energy Research Laboratory Musashi Institute Of Technology

• HAYAKAWA Nobuhiro

  Atomic Energy Research laboratory, Musashi Institute of Technology

• Hayakawa Nobuhiro

  Atomic Energy Research Laboratory Musashi Institute Of Technology

関連論文

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• Design of Neutron Beams for Boron Neutron Capture Therapy for TRIGA Reactor
• Benchmark Analysis of Criticality Experiments in the TRIGA Mark II Using a Continuous Energy Monte Carlo Code MCNP
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• Doppler and Self-Shielding Effects of Resonances in Unresolved Energy Region of Niobium
• Usefulness of single-crystal bismuth and silicon for neutron radiography facility.
• Measurements of total neutron cross sections at 24-keV by means of iron-filter method.

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