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A Conceptual design study for active nondestructive assay system by photon interrogation for uranium-bearing waste with MVP code and evaluated photonuclear data

光核反応を用いる廃棄体中のウラン濃度検認システムのモンテカルロコードMVPと光核反応データを用いた概念検討

櫻井 健; 小迫 和明*; 森 貴正

Sakurai, Takeshi; Kosako, Kazuaki*; Mori, Takamasa

A feasibility design work has been carried out with a Monte Carlo transport code on an active nondestructive assay system for low-level uranium-bearing waste from uranium enrichment facilities. Delayed neutrons from photofission of uranium isotopes in the metal waste are counted with this system to confirm that the activity of this waste is below the clearance level. The design work needs a coupled neutron/photon transport code which can simulate the photonuclear reaction and the resultant emission of neutrons. We have modified a continuous-energy Monte Carlo transport code MVP and equipped it with the function to simulate the emission of photoneutrons along with the delayed neutrons from photofission. The photonuclear data library for the modified MVP code was prepared on the basis of evaluated photonuclear data by IAEA. For the delayed neutron yields and spectra, the decay constants and relative abundances of six precursors group from uranium isotopes, JENDL Photonuclear Data File 2004 was adopted. With this code system, a time dependent simulation of neutron counts was made for the assay system, which consisted of a 15 MeV end-point bremsstrahlung photon source, helium-3 neutron detectors and the waste. The present paper describes the modification of the MVP code and the results of the simulation.

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