Monte Carlo 방법을 이용한 바나듐 자발 중성자계측기 초기 민감도 계산
Calculation of Initial Sensitivity for Vanadium Self-Powered Neutron Detector (SPND) using Monte Carlo Method
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Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Topmount In-core Instrumentation) which might be used in the SMART and SMR.
Abstract
Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Topmount In-core Instrumentation) which might be used in the SMART and SMR.
참고문헌 (7)
- John W. Hilborn, "Self-Powered Neutron Detectors for Reactor Flux Monitoring", Nucleonics, 22(2) (1964)
- H. D. Warren, "Calculational model for self-powered neutron detector", Nucl. Sci. Eng., 48, pp.331~ (1972)
- W. Jaschik, "Model for calculating promptresponse self-powered neutron detectors", Nucl. Sci. Eng., 53, pp.61~ (1974)
- H. D. Warren, "Neutron and gamma-ray effects on self-powered in-core radiation detectors", Nucl. Sci. Eng., 54, pp.395~ (1974)
- L. L. Carter, "Self-Shielding factors for FFTF flux measurements", Trans. Am. Nucl. Soc., 43, pp.710~ (1982)
- International Standards, "Nuclear power plants - In-core instrumentation - Characteristics and test methods of selfpowered neutron detectors", CEI, 2000
- A. M. Weinberg, "The Physical Theory of Neutron Chain Reactors", pp.707~ (1958), The University of Chicago Press