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Acknowledgements | Team Profile | Assessment

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Text Box: Component Three
There are two different sources from which Plutonium-239 can be extracted. There is the high level radioactive waste, as well as spent nuclear fuel. In our project, we had to choose whether to concentrate our plutonium-reprocessing on the HLW or the spent nuclear fuel. Below, find the comments of our technical advisor.
 
-----Original Message----- 
From: Ivan G. Tananaev [mailto:geokhi@mail.ru] 
Sent: Tue 1/20/2004 3:51 PM 
To: Mu_Lun 
Cc: 
Subject: Re: ISTF
 
Friends,
Thank you for your project. Please, find my considerations:
There are two parts in your document. First position is yours conclusions why we must isolate Pu-239.  I think also that this hazard, and long-live radionuclide with specific properties must be isolate and storage/use from….
From…? 
In Component 1 we must understand well and itemize direct FROM which object we want isolate Pu for different cases. 
There are two Pu sources today – (1) the spent nuclear fuel - SNF; (2) and the radioactive waste (RW), about 80% of which were accumulated for military purposes within 50 years. 
If the aim of your Proposal is to return Pu from SNF, the Second part of Component 1 is clear. For this purpose you prepare information about Yucca Mountain history. 
However, as I known, in U.S. the “opened” nuclear cycle is used. (Please, find the attached file sub21 about nuclear cycles in many countries, U.S. include). The SNF is not converted in U.S. to new nuclear fuel. In this case your future project is to offer the “closed” nuclear cycle in America, and realize a radiochemical plant for SNF retreatment with Pu and U isolation, HLW partitioning, and Cs, Sr, and minor actinides immobilization (such as France, Russia, Japan, GB). The schemes of SNP retreatment (PUREX-process, for example) are known...   
If you will plan isolate of Pu from accumulated HLW, the data of Germany's HLW storage is correct. If you have interest, I sent you file sub22-25 connected with information about HLW storage in Russia.
If you will plan isolate Pu from object (1) and (2) simultaneously, your future project will be too much. We must choose. 
Regards,
Ivan Tananaev
 
To incorporate uranium waste into the process, and lower the waste amount of that as well, a process called MOX can be added to our product.
 

Plutonium can be combined with uranium and turned into a mixed oxide fuel called Mox. 
Each six-gramme pellet holds the equivalent energy of one tonne of coal. British Nuclear Fuel (BNFL) says three pellets can provide a family's needs for an entire year. 

Mox is a way of using up the otherwise unusable plutonium.

British Nuclear Fuel (BNFL) says reprocessing ensures 97% of nuclear waste can be recycled and sent back to customers. If it was not reprocessed it would have to be stored on site. 

Reprocessing one ton of fuel saves about 100,000 barrels of oil, according to BNFL. 

It also helps conserve the world's uranium supplies, which are currently estimated to last 175 years. 
 
 

Our advisor Mr. Ivan Tananaev, readily agreed with us. He told us that his lab in Moscow, Russia would be happily willing to test out anything and work in collaboration with us.
 
-----Original Message----- 
From: Ivan Tananaev [mailto:tananaev@geokhi.ru] 
Sent: Thu 12/11/2003 1:35 PM 
To: Mu_Lun 
Cc: 
Subject: Future collaboration
 
Dear Lun Mu:
Thank you very much for your e-mail dated on December, 1.
My name is Ivan Tananaev; I am working at the Vernadsky Institute, Radiochemical Laboratory under scientific leadership of Professor Boris F. Myasoedov. I am a deputy chief of this Laboratory and he asked me for answer your e-mail.
Vernadsky Institute represents the well-known school of inorganic and radiochemistry, and has a large experience on the radionuclides separations. Within 10+ years we realized an original extraction and separation schemes for isolation and recovery of necessary Tc-99, Am-243, and, of course, Pu-238. Our technical schemes of Pu-238 separation had been applied in industry at the Siberian Chemical Plant Site and at the Production Association “Mayak” Site.  
Hence, we have great interest on establishment of our scientific and/or technical cooperation with you connected with fabrication, separation, and application of Pu-238 samples. We would be honored to serve as the advised or mentor on this proposal. Our laboratory is ready for joint collaboration on development of original schemes of accumulation of this radionuclide, and we are willing also to make an examination of a future Projects to make sure that this one is correct. 
However, we asked you about more details on your future Project, and what aim you will attain. 
With the best wishes,
Ivan Tananaev
tananaev@geokhi.ru; geokhi@mail.ru
19, Kosygina Street, 119991, Moscow, Russia
Vernadsky Institute of Geochemistry and Analytical Chemistry Russian Academy of Sciences

 

 
 
 
 
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