COUNTING RATE EVALUATING METHOD FOR IN-LINE NEUTRON MONITOR

Japanese Patent JP3263154

B2

PURPOSE: To accurately determine the relation between the counting rate and the nuclear fuel material density with a real machine simulating/calibrating device by using the isotope nuclide composition ratio of a nuclear fuel material as a parameter for evaluating the absolute value of the nuclear fuel material density from the counting rate of an in-line neutron monitor.
CONSTITUTION: A neutron source 4 having the known intensity is arranged in a real machine simulating/calibrating device 1 simulating a real machine nuclear fuel container system to obtain the counting rate measured value (CSM), and the counting rate calculated value (CSC) when the neutron source 4 is arranged or the neutron flux calculated value (&phiv SC) at the position of a neutron detector is calculated via the neutron flux calculation code. The counting rate calculated value (CLC) or the neutron flux calculated value (&phiv LC) is calculated via the neutron flux calculation code on the assumption that the composition, density, and distribution of the nuclear fuel are known for the real machine nuclear fuel container system, and the counting rate (CLM) is obtained as the product of the function of (CSM/CSC) and (CLCO or the product of the function of (CSM/&phiv SC) and (&phiv LC).

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Shigeto Kikuchi
Sei Ueda
Toshiyuki Tamura

JP30851092A

March 04, 2002

November 18, 1992

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Toshiba Corporation

G01T3/00; (IPC1-7): G01T3/00

JP61228374A
JP6128885A
JP2205792A
JP458184A
JP4151590A
JP5232238A
JP6148335A
JP6160587A
JP614980U

Yoshiaki Inomata

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