Analysis of Control Rod Reactivity Worths for AVR Power Plant at Cold and Hot Conditions.

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概要

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• The control rod worths of the AVR power plant for the cold and hot conditions were analyzed to verify an analysis method of reflector control rod worths. In the analysis method, the neutron-flux-weighting method was used to obtain the effective group constants of the control rod inserted in the graphite nose. The control rod worths were calculated with the core analysis code system for the High Temperature engineering Test Reactor (HTTR). <BR>The experimental values of the control rod worths were 6.47 and 6.81%.4 for the cold and hot conditions, respectively. The differences between the experimental and analytical values for the cold and hot conditions were 2 and 10%, respectively. From these results, it was made clear that the analysis method applied here predicts well the control rod worth of the AVR power plant and is applicable for the nuclear designs of reflector control rods of future small HTGRs.

著者

• MURATA Isao

  Japan Atomic Energy Research Institute

• SHINDO Ryuichi

  Japan Atomic Energy Research Institute

• YAMASHITA Kiyonobu

  Japan Atomic Energy Research Institute

• WERNER Heinz

  Forschungszentrum fillich GmbH, Institut fur Reaktor Sicherheit

• TOKUHARA Kazumi

  Fuji Electric Co., Ltd.

関連論文

• Importance Determination Method for Geometry Splitting with Russian Roulette in Monte Carlo Calculations of Thick and Complicated Core Shielding Structure
• Analysis of Control Rod Reactivity Worths for AVR Power Plant at Cold and Hot Conditions.
• Evaluation of Local Power Distribution with Fine-mesh Core Model for High Temperature Engineering Test Reactor (HTTR).

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