Problems of Radioactive Sodium Removal and Disposal From Decommissioning LMFR Equipment

MRS Proceedings ◽

10.1557/proc-506-1001 ◽

1997 ◽

Vol 506 ◽

Author(s):

Yu. Ye. Shtynda ◽

V. I. Polyakov

Keyword(s):

Radioactive Wastes ◽

Primary Circuit ◽

Minimum Volume ◽

Safe Disposal ◽

Radionuclide Sorption ◽

Sodium Removal ◽

Radioactive Sodium

ABSTRACTPreparing for safe disposal of the LMFR primary circuit equipment and sodium reprocessing for storage and burial with minimum volume of radioactive wastes resulted in testing of radionuclide sorption trapping, distillation and rinsing with water under vacuum used for safe sodium removal and decontamination of equipment.

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Approach to Derivation of Waste Acceptance Criteria for Mochovce Disposal Facility

9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3 ◽

10.1115/icem2003-4797 ◽

2003 ◽

Author(s):

V. Hanusˇi´k ◽

Z. Kusovska´ ◽

J. Bala´zˇ ◽

A. Mrsˇkova´

Keyword(s):

Fission Products ◽

Total Activity ◽

Safety Analysis ◽

Radioactive Wastes ◽

Primary Circuit ◽

Radiological Protection ◽

Waste Streams ◽

Acceptance Criteria ◽

Near Surface ◽

Dose Limits

In Slovakia, low and intermediate level radioactive wastes are disposed in a near-surface repository at Mochovce site. The repository, which was commissioned in September 2001, has a disposal capacity 22,320 m3. It is a vault-type concrete structure repository with reinforced concrete containers as the final waste packages. The Mochovce repository is designed to receive acceptable radioactive wastes from decommissioned A-1 power plant at Jaslovske´ Bohunice, operational waste from NPPs V-1 and V-2 at Jaslovske´ Bohunice site and NPP Mochovce, as well as institutional radioactive wastes. Generally, calculation endpoint of disposal facilities performance assessment is radiological impact on humans and environment. In that case, starting points of assessment are the waste activity concentrations and inventory activity. The acceptance of radioactive waste in Mochovce repository is one of the many elements that directly contribute to the safety of the disposal system. In Mochovce repository safety analysis, end points are both the concentration per package and total activity values. On the other hand, radiological protection criteria are the starting points of the calculation. This approach was developed and applied because the actual inventory that will be disposed of is highly uncertain. As a result of the accidents, the primary circuit was contaminated by fission products. Some auxiliary circuits and facilities were also contaminated. The complicated problem is the relatively high content of long-lived radionuclides (inclusive transuranic elements) in some waste streams. After two technological incidents at NPP A-1 uncertainties in waste inventory are large because of variability in the types of waste streams and variability in the quality and completeness of the waste characterization data. This paper presents the philosophy of safety analysis, development of scenarios, their modelling and approach that have been used to derive waste acceptance criteria, specifically limits of activity. The approach consists of the determination of radionuclides important for safety, the use of relevant safety scenarios, the setting of dose limits associated with scenarios, the calculation of activity limits and application of the simple summation rule. Finally, information is provided about short operation of the repository.

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The Safe Disposal of Radioactive Wastes

Royal Society of Health Journal ◽

10.1177/146642406008000405 ◽

1960 ◽

Vol 80 (4) ◽

pp. 214-219

Author(s):

R.H. Burns

Keyword(s):

Radioactive Wastes ◽

Safe Disposal

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Solubility study of Tc(IV) in a granitic water

Radiochimica Acta ◽

10.1524/ract.2007.95.9.523 ◽

2007 ◽

Vol 95 (9) ◽

Cited By ~ 5

Author(s):

D. J. Liu ◽

J. Yao ◽

B. Wang ◽

C. Bruggeman ◽

N. Maes

Keyword(s):

Fission Product ◽

Radioactive Wastes ◽

Geological Disposal ◽

Safe Disposal ◽

Solubility Study ◽

Deep Geological Disposal ◽

High Level

The deep geological disposal of the high level radioactive wastes is expected to be a safe disposal method in most countries. The long-lived fission product

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