نتایج جستجو برای: spent fuel

تعداد نتایج: 102934  

Journal: :Transactions of the JSME (in Japanese) 2021

Journal: :Nuclear Instruments and Methods in Physics Research 2021

The upcoming disposal of spent nuclear fuel in Finland creates new challenges for safeguards. Part the national safeguards concept geological repositories, developed by STUK — Radiation and Nuclear Safety Authority, is non-destructive assay (NDA) verification all items before disposal. proposed system a combination PGET (Passive Gamma Emission Tomography), PNAR Neutron Albedo Reactivity) weight...

2014
S. Jacobsson Svärd T. A. White L. E. Smith V. Mozin P. Jansson A. Davour S. Grape S. Holcombe H. Trellue N. Deshmukh R. S. Wittman

Assessment of gamma emission tomography (GET) for spent nuclear fuel verification is the task in IAEA MSP project JNT1955. In line with IAEA Safeguards R&D plan 2012-2023, the aim of this effort is to “develop more sensitive and less intrusive alternatives to existing NDA instruments to perform partial defect tests on spent fuel assemblies prior to transfer to difficult to access storage". The ...

Journal: :Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 1998

2013
Daniel Metlay

The president realized that the nation lacked a clear policy for developing a deep-mined geologic repository for high-level radioactive waste and spent nuclear fuel. New legislation would be required to chart a more promising path forward. The views of multiple parties had to be taken into account. He decided to create a high-level body to ventilate the issues involved and to make recommendatio...

2016
Naoki Sugiyama

Uranium 236 is a long-lived radionuclide which is created from the naturally occurring trace isotope 235U (0.72% abundance) by thermal neutron capture. This process leads to a natural abundance of 236U in the range from 10-14—10-13 relative to the major 238U isotope (236U/238U). 236U is also created during the process of uranium enrichment for nuclear fuel or weapons, and as a waste product fro...

2001
T. K. Kim

An assessment of the radiotoxicity of spent nuclear material and the fuel handling issues associated with plutonium (Pu) or transuranics (TRU) multi-recycling in PWRs using the CORAIL assembly concept has been performed. This necessitated the development of an analytical approach to solve directly for the equilibrium state of repeated recycle, including higher actinide content. The equilibrium ...

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