Assessment of the dose to the public from a near-surface radioactive waste disposal facility

Atomic Energy ◽  
1996 ◽  
Vol 80 (1) ◽  
pp. 53-56
Author(s):  
B. E. Serebryakov
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Radioactive Waste Disposal ◽  
Near Surface ◽  
The Public ◽  
Disposal Facility

How Thick Should Cover Layer be for Radioactive Waste Disposal Facility? The Case of the Yamin Plain, Israel

2017 ◽  
Vol 3 (3) ◽  
Author(s):  
Avraham Dody ◽  
Ravid Rosenzweig ◽  
Ran Calvo ◽  
Eyal Shalev
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Erosion Rate ◽  
Soil Surface ◽  
Radioactive Waste Disposal ◽  
Rain Event ◽  
Infiltration Depth ◽  
Near Surface ◽  
Cover Layer ◽  
Disposal Facility

Two main natural processes which control the migration of radioactive contaminants to the biosphere were studied in the Yamin Plain in order to evaluate the thickness of a cover layer needed for near-surface radioactive waste disposal facility. The first is the natural erosion of the cover layer, and the second is the infiltration during rain and runoff events. The erosion rate of the soil surface was studied by optical stimulation luminescence technique. It was found that during the last 14,000 years, the erosion rate was 0.3 mm/y which are 3 m for 10,000 years. The infiltration depth assessment was based on water content measurements and numerical modeling. It shows that under the most extreme rain event having an equivalent rain of 84 mm, infiltration depth was limited to 4.5 m. Taking into account the two processes, the effective cover layer thickness over 10,000 years should be at least 7.5 m thick.

A hydrochemical and isotopic case study around a near surface radioactive waste disposal

2007 ◽  
Vol 95 (1) ◽  
Author(s):  
Zs. Szántó ◽  
É. Svingor ◽  
I. Futó ◽  
L. Palcsu ◽  
M. Molnár ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Treatment ◽  
Radioactive Waste Disposal ◽  
Ion Chemistry ◽  
Continuous Transition ◽  
Near Surface ◽  
Disposal Facility ◽  
Treatment And Disposal ◽  
Site Characterisation

As part of the site characterisation program for the near surface radioactive waste treatment and disposal facility (RWTDF) at Püspökszilágy, Hungary, water quality and environmental isotope investigations have been carried out. Water samples for major ion chemistry, tritium,The chemical composition of groundwaters presented a continuous transition from waters situated on one side to waters on the top and on the other slope of the disposal suggesting the mixing of the three hydrochemical “endmembers”.Most of δ

scholarly journals UPPER FILLER MATERIAL APPLIED IN CAVERN TYPE RADIOACTIVE WASTE DISPOSAL FACILITY

2016 ◽  
Vol 72 (3) ◽  
pp. 234-248
Author(s):  
Shin-ichi TAKECHI ◽  
Toshiyuki SASAKI ◽  
Kosuke YOKOZEKI ◽  
Hiroshi SHIMBO ◽  
Yoshihiro AKIYAMA ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Radioactive Waste Disposal ◽  
Filler Material ◽  
Disposal Facility

scholarly journals Peculiarities of 137Cs Sorption/Desorption by Bentonite Clays of Cherkasy Deposit from Groundwater Model Solutions of Radioactive Waste Disposal Facilities at the “Vector” Production Complex

2021 ◽  
Vol 21 (2) ◽  
pp. 78-87
Author(s):  
B. H. Shabalin ◽  
◽  
К. К. Yaroshenko ◽  
S. P. Buhera
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Water Soluble ◽  
Radioactive Waste Disposal ◽  
Groundwater Model ◽  
Static Mode ◽  
Near Surface ◽  
Model Solutions ◽  
Production Complex ◽  
Bentonite Clays

The main feature of bentonite clays is their high sorption capacity with respect to various radionuclides. The study of sorption kinetics of 137Cs was performed in the static mode by natural and industrial soda modified (PBA-20) samples of bentonite clays of Cherkasy deposit of bentonite and paligorskite clays from groundwater model solutions of radioactive waste disposal facilities of “Vector” production complex under various pH and solution mineralisation. The desorption of occluded samples was studied in distilled water and acetateammonium buffer solution. The value of the degree of sorption (S) for 137Cs on the modified samples exceeds 90%, for natural bentonite this indicator is lower (about 83–85%). On both types of bentonite with increasing time of their contact with aqueous solution and pH, there is a redistribution of water-soluble, ion-exchange and fixed forms of radionuclide and the share of the latter, that is not participating in migration processes increases, indicating the ability of bentonites to immobilize effectively for a long time. It is shown that Na-modified bentonite has higher proportion of sorption in fixed form compared to natural one and its application increases the probability of irreversible fixation of migrating radionuclides under non-optimal conditions of sorption (high pH (>11) of water after prolonged contact with cement-concrete components of engineering barriers) and thus increases the environmental safety of the storage facility. It is shown that bentonite clays of the Cherkasy deposit can serve as an effective material for creating anti-migration barriers of I and II stages of surface/near-surface storage facilities for radioactive waste disposal at the “Vector” production complex. At the same time, the issue of practical application of bentonite clays of Cherkasy deposit for accurate predictions of securing radioactive waste disposal of Chornobyl origin requires further study of sorption-desorption properties of bentonite clay with respect to other fission products and actinides

Method of Designing Bentonite/Sand Mixture to Achieve the Target Permeability

1994 ◽  
Vol 353 ◽  
Author(s):  
Hitoshi Nakashima ◽  
Takashi Ishii ◽  
Tatsuro Nagasawa ◽  
Nobuhide Ogata ◽  
Hideo Komine
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Void Ratio ◽  
Radioactive Waste Disposal ◽  
Permeability Test ◽  
Sand Mixture ◽  
Compaction Test ◽  
Disposal Facility ◽  
Effective Component ◽  
Effective Void Ratio

AbstractBentonite/sand mixture is expected to be an effective component of barriers for radioactive waste disposal facility. Impermeable mixture can be obtained through enrichment of the bentonite content,but it is difficult to estimate a permeability of bentonite/sand mixture before permeability test. At designing of bentonite/sand mixture, we have to decide which sand to be used, and what bentonite content is. But.this means that designing will be a time-consuming task. In this report, we made many kinds of bentonite/sand mixtures using some kinds of sand with different bentonite content, and permeability tests were conducted for these mixtures. After examination of the permeability tests results, the effective void ratio of bentonite/sand mixture which was obtained by compaction test, is an efficient parameter for estimation of the permeability. Last of all, we propose the method of designing bentonite/sand mixture using the effective void ratio.

scholarly journals EVALUATION ON CONSTRUCTION QUALITY OF PIT FILLER MATERIAL OF CAVERN TYPE RADIOACTIVE WASTE DISPOSAL FACILITY

2014 ◽  
Vol 70 (1) ◽  
pp. 29-43
Author(s):  
Shin-ichi TAKECHI ◽  
Kosuke YOKOZEKI ◽  
Hiroshi SHIMBO ◽  
Kenji TERADA ◽  
Yoshihiro AKIYAMA ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Radioactive Waste Disposal ◽  
Filler Material ◽  
Construction Quality ◽  
Disposal Facility
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