scholarly journals A method to enrich reprocessed uranium with various initial contents of even-numbered isotopes

2019 ◽  
Author(s):  
Andrei Smirnov ◽  
Vladislav Gusev ◽  
Georgy Sulaberidze ◽  
Vladimir Nevinitsa
Keyword(s):  
Reprocessed Uranium

Estimation of 90Sr activity in reprocessed uranium from the PUREX process

2007 ◽  
Vol 272 (1) ◽  
pp. 123-126
Author(s):  
S. Ravi ◽  
A. K. Deepa ◽  
B. Surekha ◽  
S. Susheela ◽  
P. V. Achuthan ◽  
...  
Keyword(s):  
Purex Process ◽  
Reprocessed Uranium ◽  
90Sr Activity

Evaluation of multiple, self-recycling of reprocessed uranium in LWR

2010 ◽  
Vol 240 (5) ◽  
pp. 1028-1032 ◽  
Author(s):  
J.R. Coleman ◽  
T.W. Knight
Keyword(s):  
Reprocessed Uranium

Development of Evaluation Models of Manpower Needs for Dismantling the Dry Conversion Process-Related Equipment in Uranium Refining and Conversion Plant (URCP)

2013 ◽  
Author(s):  
Sari Izumo ◽  
Hideo Usui ◽  
Mitsuo Tachibana ◽  
Yasuyuki Morimoto ◽  
Nobuo Takahashi ◽  
...  
Keyword(s):  
Project Management ◽  
Evaluation System ◽  
Conversion Process ◽  
Actual Data ◽  
Main Process ◽  
Nuclear Facility ◽  
Energy Agency ◽  
Evaluation Models ◽  
Reprocessed Uranium ◽  
Manpower Needs

Evaluation models for determining the manpower needs for dismantling various types of equipment in uranium refining and conversion plant (URCP) have been developed. The models are widely applicable to other uranium handling facilities. Additionally, a simplified model was developed for easily and accurately calculating the manpower needs for dismantling dry conversion process–related equipment (DP equipment). It is important to evaluate beforehand project management data such as manpower needs to prepare an optimized decommissioning plan and implement effective dismantling activity. The Japan Atomic Energy Agency (JAEA) has developed the project management data evaluation system for dismantling activities (PRODIA code), which can generate project management data using evaluation models. For preparing an optimized decommissioning plan, these evaluation models should be established based on the type of nuclear facility and actual dismantling data. In URCP, the dry conversion process of reprocessed uranium and others was operated until 1999, and the equipment related to the main process was dismantled from 2008 to 2011. Actual data such as manpower for dismantling were collected during the dismantling activities, and evaluation models were developed using the collected actual data on the basis of equipment classification considering the characteristics of uranium handling facility.

REPROCESSED URANIUM EXPOSURE AND LUNG CANCER RISK

2010 ◽  
Vol 99 (3) ◽  
pp. 308-313 ◽  
Author(s):  
Irina Guseva Canu ◽  
Sophie Jacob ◽  
Elisabeth Cardis ◽  
Pascal Wild ◽  
Sylvaine Caër-Lorho ◽  
...  
Keyword(s):  
Lung Cancer ◽  
Cancer Risk ◽  
Lung Cancer Risk ◽  
Reprocessed Uranium

scholarly journals Reprocessed Uranium Influence on Clearance Application in Uranium Fuel Fabrication Plant

2012 ◽  
Vol 11 (3) ◽  
pp. 222-232
Author(s):  
Hiromichi FUMOTO ◽  
Keiji SUZUKI ◽  
Nobuo YAMANARI ◽  
Hideshi FUJINAGA
Keyword(s):  
Uranium Fuel ◽  
Fuel Fabrication ◽  
Reprocessed Uranium

scholarly journals A new approach to the recycling of spent nuclear fuel in thermal reactors within the REMIX concept

2020 ◽  
Vol 6 (2) ◽  
pp. 93-98
Author(s):  
Nikita V. Kovalev ◽  
Boris Ya. Zilberman ◽  
Nikolay D. Goletsky ◽  
Andrey B. Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Natural Uranium ◽  
Spent Fuel ◽  
High Concentration ◽  
Energy Potential ◽  
New Approach ◽  
Reprocessed Uranium

A review of simulated nuclear fuel cycles with mixed uranium-plutonium fuel (REMIX) was carried out. The concept of REMIX fuel is one of the options for closing the nuclear fuel cycle (NFC), which makes it possible to recycle uranium and plutonium in VVER-1000/1200 thermal reactors at a 100% core loading. The authors propose a new approach to the recycling of spent nuclear fuel (SNF) in thermal reactors. The approach implies a simplified fabrication of mixed fuel when plutonium is used in high concentration together with enriched natural uranium, while reprocessed uranium is supposed to be enriched and used separately. The share of standard enriched natural uranium fuel in this nuclear fuel cycle is more than 50%, the share of mixed natU+Pu fuel is 25%, the rest is fuel obtained from enriched reprocessed uranium. It is emphasized that the new approach has the maximum economic prospect and makes it possible to organize the fabrication of this fuel and nuclear material cross-cycling at the facilities available in the Russian Federation in the short term. This NFC option eliminates the accumulation of SNF in the form of spent fuel assemblies (SFA). SNF is always reprocessed with the aim of further using the primary reprocessed uranium and plutonium. Non-recyclable in thermal reactors, burnt, reprocessed uranium, the energy potential of which is comparable to natural uranium, as well as secondary plutonium intended for further use in fast reactors, are sent as reprocessing by-products to the storage area.

Method for Enriching Reprocessed Uranium in a Cascade of Gas Centrifuges with Simultaneous Decrease in the 232,234,236U Content

2018 ◽  
Vol 81 (8) ◽  
pp. 1233-1236 ◽  
Author(s):  
A. Yu. Smirnov ◽  
G. A. Sulaberidze ◽  
A. A. Dudnikov ◽  
V. A. Nevinitsa
Keyword(s):  
Reprocessed Uranium ◽  
Simultaneous Decrease
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