Resources
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Type:JNMM
Volume:1
Issue:4
Abstract:A method has been developed which permits rapid assessment of 235U in effluents from uranium fuel fabrication facilities. Gross alpha…
Type:Annual Meeting Proceedings
Abstract:Over the past few years, with the maturing of the nuclear industry, increasing amounts of nuclear material are being processed through the…
Type:JNMM
Volume:1
Issue:4
Abstract:SCENIC can calculate and predict the assembly wise and batch wise burn-up distributions and isotopic inventories for the current and future…
Type:JNMM
Volume:1
Issue:4
Abstract:CONTROL PREFERENCE SURVEYS
D. W. Brady and D. A. Zollman
National The objective of this research 6,7,8 was to ascertain the extent of the…
Type:Annual Meeting Proceedings
Abstract:The overall objective of this paper is to describe a technique for improving the capability of taking accurate physical inventories in fuel…
Type:Annual Meeting Proceedings
Abstract:One of the problems of making safeguards decisions based on material balance accounting or shipper-receiver differences is that there is…
Type:Annual Meeting Proceedings
Abstract:The capability of the industry to handle, ship, and store spent fuel is reviewed. Potential problem areas and the current industry status…
Type:Annual Meeting Proceedings
Abstract:Important statistical aspects pertinent to high speed pellet by pellet rod scanners are discussed. The implications of these points on the…
Type:Annual Meeting Proceedings
Abstract:I am very pleased to have been invited to address this audience, and particularly so in this beautiful part of our country, where the sea,…
Type:Annual Meeting Proceedings
Abstract:The scale of plutoniura recycle should climb sharply in the next few years reaching a total of more than fifty reloads per year by 1980.…
Type:Annual Meeting Proceedings
Abstract:In early 1972 at the request of the Division of Nuclear Materials Security, 65 samples of plutonium were pulled from an AEC contractor…
Type:Annual Meeting Proceedings
Abstract:he £f fuei rocj assay system designed to measure the total fissile content of LWR fuel rods was described previously! along with some…
Type:Annual Meeting Proceedings
Abstract:The determination of random error components in a measurement process is frequently accomplished by a statistical testing procedure known…
Type:Annual Meeting Proceedings
Abstract:Whenever it is necessary to take a physical inventory for the purpose of establishing the amount of special nuclear material contained in…
Type:JNMM
Volume:1
Issue:2
Abstract:The approach commonly used to find the variance of material unaccounted for (MUF) involves expressing MUF as a linear combination of…
Type:Annual Meeting Proceedings
Abstract:The purpose of this report is to present a description of the desipn and of the operating characteristics of a calorimeter which was built…
Type:Annual Meeting Proceedings
Abstract:Anybody at all familiar with the operation of a nuclear fuel fabrication plant knows that it is quite presumptious to set up a…
Type:Annual Meeting Proceedings
Abstract:Good afternoon. Usually one is a bit apprehensive when he finds himself as the first speaker in the afternoon. The warm, full feeling is…
Type:Annual Meeting Proceedings
Abstract:The Mobile Nondestructive Assay Laboratory (MONAL, Fig. 1) was devel- oped by the Los Alamos Scientific Laboratory to test and demonstrate…
Type:Annual Meeting Proceedings
Abstract:As the Chairman of the Nuclear Materials Safeguard. Committee of the Atomic Industrial Forum, I am pleased to have the opportunity to…