SYMPOSIA PAPER Published: 01 January 2007

Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel


Nondestructive and simple retrospective dosimetry method was developed. Mercuric iodide or cadmium zinc telluride detector was used as a detector to measure 54Mn, 58Co, and 60Co that were created in reactor internals and vessels. Detector is surrounded by tungsten collimator which shield background gamma rays and detect gamma rays from desired measuring point. Photopeak count rate of this detector were calculated using the MCNP-4C code. This response was calculated for each reactor internal geometry that was irradiated by unit neutron flux which energy spectrum was calculated by the TORT code. Neutron fluence is calculated using precalculated response, measuring time, decay time and reactor power history. We can also get Displacement per Atom (DPA), hydrogen and helium production simultaneously using neutron spectrum precalculated in reactor vessel. Because the time and cost of this method are much less than the sampling method, we can measure at many positions and even get a contour map.

Author Information

Hayashi, Katsumi
Hitachi Ltd., Ibaraki, Japan
Tayama, Ryuuichi
Hitachi Ltd., Ibaraki, Japan
Watanabe, Yoshio
Hitachi Ltd., Ibaraki, Japan
Nakamura, Tomomi
Hitachi Ltd., Ibaraki, Japan
Kubota, Isamu
Hitachi Engineering Company, Ibaraki, Japan
Hayashi, Haruhisa
Chubu Electric Power Co., Inc., Aichi, Japan
Yamasaki, Tadashi
Chubu Electric Power Co., Inc., Aichi, Japan
Yuya, Hideki
Chubu Electric Power Co., Inc., Aichi, Japan
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Developed by Committee: E10
Pages: 3–10
DOI: 10.1520/STP45420S
ISBN-EB: 978-0-8031-6242-6
ISBN-13: 978-0-8031-3412-6