U.S. Department of Energy’s Initiatives for Proliferation Prevention in Russia: Results of Radioactive Liquid Waste Treatment Project, Year 2 Y. Pokhitonov,

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U.S. Department of Energy’s Initiatives for Proliferation Prevention in Russia: Results of Radioactive Liquid Waste Treatment Project, Year 2 Y. Pokhitonov, V. Kamachev V.G. Khlopin Radium Institute, Russia D. Kelley Pacific Nuclear Solutions, USA

Purpose of Project IPP sponsored by DOE to engage Russian weapons scientists in peaceful use of existing and newly developed technologies (17 projects underway) DOE’s IPP program is a mechanism for U.S. private sector companies to enter Russian market: radwaste treatment Introduce USA environmental technology to weapons sector and seek joint technologies – first foreign firm Investigate solutions for Russia & USA liquid radwaste problems resulting from Cold War DOE compensates scientists to participate in program Long-term, commercialize project, employ scientists

Project Participants Russia – Russian State Atomic Energy Corporation (ROSATOM) – VG Khlopin Radium Institute (project manager) – Seversk (SCC ), Zheleznogorsk (MCC), Ozersk (MAYAK), Gatchyna – 90+ participants, 68 weapons scientists USA – Department of Energy (GIPP) – Argonne National Lab – Pacific Nuclear Solutions (project manager) International Science & Technology Center (ISTC) – Project administrator, Moscow

Polymer Technology Variety of polymers for all organic, oil and aqueous streams Solidification of LLW, ILW & HLW Packaging: – Standard drums / B-25 box – Encapsulation in cement Disposal options: – Short term, intermediate term – Final storage – Incineration Advantages: – No special equipment, low cost to process / treat – High performance, long term stability, no degradation – Waste minimization: oil 2:1 or 3:1 bonding ratio (liquid : polymer) – Safe to use, safe for transport

Solidification Process

Experiments Stability (Differential Thermal Analysis) Irradiation Gas generation Polymer solidification /capacity / evaporation Encapsulation in cement

Differential Thermal Analysis Polymers: N910, N930, N960 Solidified samples with nitric acid and sodium nitrate possess high thermal stability

Irradiation Tests / Results Extensive irradiation testing conducted, required for ROSATOM certification – Over 25 irradiation tests – All similar outcomes with China, USA tests All high dose rates Cobalt 60 gamma irradiator One example: nitric / organic solution, solidified 30 rad per second 30 days = 77 M Rad + 73 days = 270 M Rad Brittle, size reduction, no degradation / leaching Conducted for gas generation tests

Irradiation Tests

Stability and Irradiation Cobalt 60, gamma installation, dose rate 3.9·10⁶ gray N960 polymer, HNO₃, 1M, after irradiation N910 polymer, oil + TBP, after irradiation

Gas Generation Tests Tests required to determine fire and explosion safety conditions Tests carried out under static conditions in sealed glass ampoules N960 polymer + nitric solution: no changes in the solidification and no gas release N910 polymer + TBP / oil: variable results Preliminary judgment: polymers are not gas generators

Rate of gas release during irradiation of sample: N910 polymer + 50%-TBP / 50%-oil

Characteristic (composition) of wastes Conditions of solidification Results Volume of waste used, ml Amount of # 960 used, g Amount of # 910 used, g 4232 Sludge residue from the bottom of the apparatus (aqueous phase). U- 80g., NaNO ₃~­ 200g, HNO ₃ -0,8 M/I 680,5 Successfully solidified 4231 Sludge residue from the top of the apparatus (occurrence of organic phase is probable). U-80g., NaNO ₃~­ 200g, HNO ₃ -0,8 M/I. Very thick black liquid. 680,5 Successfully solidified 4237 LL decontaminationg solution with low amounts of organic substances, U-153 g/l, NaNO ₃~­ g, HNO ₃­ 2,5 M/I 1280,5 Successfully solidified 4238 LL decontaminating solution with low amounts of organic substances. U-153 g/l, NaNO ₃~­ g, HNO ₃­ 2,5 M/I 2042 Successfully solidified 4125 U-20 g, NaNO ₃­ 40g, HNO ₃­ 1,2 M/I. There was a precipitate in the solution ,5 Successfully solidified 4283 Uranium re-extracts. U-70g, HNO ₃­ 0,07 M/I Successfully solidified

No Relationship between the mass of polymer and the mass of liquid phase, M p :M j Loss of weight after aging samples, during 21 days, % Amount of water absorbed by samples after solidification during 21 days. (weight of water/1 gram solidified sample) H₂OH₂O 12:133,7All water has been absorbed by the sample 21:266,47All water has been absorbed by the sample 31:583,26All water has been absorbed by the sample NaOH, 0,1M 41:153,91All water has been absorbed by the sample 51:266,25All water has been absorbed by the sample 61:582,76All water has been absorbed by the sample HNO ₃, 1,0M 71:149,73All water has been absorbed by the sample 81:266,34All water has been absorbed by the sample 91:582,88All water has been absorbed by the sample

Solidified sample after addition of water Solution: HNO₃ 1,0M No volumetric increase

Polymer Solidification/ Capacity / Evaporation: Conclusions Polymer technology is irreversible, liquid permanently immobilized in polymer matrix Advantage: direct application of polymer to waste without conditioning / additives Little or no volumetric increase in the process Appreciable volume reduction through evaporation; no measurement of water vapor Polymers slow the evaporation process Polymers are versatile, solidify aqueous / organic waste of varying acidities, specific activities, suspensions and sludge types & salts

Encapsulation of Polymer Solidification Cementation tests at AREVA & Sellafield successfully completed, with 90% organic / 10% aqueous streams When aqueous is above 10%, new technique for encapsulation is required Encapsulation research underway: – additives to solidification – additives to cement – tests with inorganic materials encouraging

Conclusions Experiments conducted thus far provide greater understanding of polymer’s capabilities Validates the polymer’s application with ILW / HLW waste First actual project planned for 1 st Q, 2011 – ILW aqueous waste with some organic material Results of work 3 sub-sites will be presented in 2011