Advanced SearchSearch Tips
Calculation of Initial Sensitivity for Vanadium Self-Powered Neutron Detector (SPND) using Monte Carlo Method
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
 Title & Authors
Calculation of Initial Sensitivity for Vanadium Self-Powered Neutron Detector (SPND) using Monte Carlo Method
CHA, Kyoon Ho; PARK, Young Woo;
  PDF(new window)
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 (Top-mount In-core Instrumentation) which might be used in the SMART and SMR.
SPND;neutron sensitivity;self-shielding effect;beta escape probability;space charge effect;MCNP;
 Cited by
Monte Carlo 방법을 이용한 로듐 및 바나듐 자발 중성자계측기의 연소에 따른 민감도 평가,차균호;박영우;

센서학회지, 2016. vol.25. 4, pp.264-270 crossref(new window)
Depletion Sensitivity Evaluation of Rhodium and Vanadium Self-Powered Neutron Detector (SPND) using Monte Carlo Method, Journal of Sensor Science and Technology, 2016, 25, 4, 264  crossref(new windwow)
John W. Hilborn, "Self-Powered Neutron Detectors for Reactor Flux Monitoring", Nucleonics, Vol. 22, No. 2 - February, 1964.

H. D. Warren, "Calculational model for self-powered neutron detector," Nucl. Sci. Eng., Vol. 48, p. 331, 1972. crossref(new window)

W. Jaschik and W. Seifritz, "Model for calculating prompt-response self-powered neutron detectors," Nucl. Sci. Eng., Vol. 53, p. 61, 1974. crossref(new window)

H. D. Warren and N. H. Shah, "Neutron and gamma-ray effects on self-powered in-core radiation detectors," Nucl. Sci. Eng., Vol. 54, p. 395, 1974. crossref(new window)

L. L. Carter, "Self-Shielding factors for FFTF flux measurements," Trans. Am. Nucl. Soc., Vol. 43, p. 710, 1982.

International Standards, "Nuclear power plants - In-core instrumentation - Characteristics and test methods of self-powered neutron detectors," CEI/IEC 61468, 1st edition, 2000-03.

A. M. Weinberg and E. P. Wigner, "The Physical Theory of Neutron Chain Reactors", p707, The University of Chicago Press, Chicago, 1958.