Hydrology of waste disposal, National Reactor Testing Station, Idaho, with special reference to the Idaho Chemical Processing Plant area and the Materials Testing Reactor--Engineering Test Reactor area

1963 ◽  
Author(s):  
P.H. Jones
1995 ◽  
Vol 412 ◽  
Author(s):  
Darryl D. Siemer ◽  
Barry E. Scheetz ◽  
Mary Lou Gougar

AbstractProperly prepared cementitious waste forms can be hot-isostatically-pressed into materials that exhibit performance equivalent to typical radwaste-type glasses. The HIPing conditions (temperature/pressure) required to “vitrify” these concretes are quite mild and therefore consistent with both safety and good productivity. This paper describes both the process and its products with reference to potential application to Idaho Chemical Processing Plant (ICPP) reprocessing wastes.


1987 ◽  
Vol 112 ◽  
Author(s):  
Roseanne S. Baker ◽  
Bruce A. Staples ◽  
Dieter A. Knecht ◽  
Julius R. Berreth

AbstractCandidate products are being evaluated to immobilize the routinely calcined waste at the Idaho Chemical Processing Plant (ICPP). A potential product with minimal volume for immobilizing ICPP high-level waste (HLW) for final disposal is a high-waste-loading and high-density glass-ceramic. Glass-ceramics are formed by Hot Isostatic Pressing (HIPing) the HLW with selected additives, such as SiO2, B2O3, Li2O, Na2O, and Y2O3. Glass-ceramic products have been formed with calcine loa ings up to 80 wt% and densities up to 3.4 g/cm3. Crystalline phases observed in the glass-ceramic products include calcium fluoride, monoclinic and cubic zirconia, calcium- and yttrium-stabilized zirconia, and zircon. An interstitial amorphous phase also exists consisting of the oxides of silicon, aluminum, boron, and alkalis. The glass-ceramic waste forms give leach rates comparable to simulated HLW glass products.


1995 ◽  
Vol 412 ◽  
Author(s):  
Krishna Vinjamuri

AbstractCurrently, at the Idaho Chemical Processing Plant (ICPP) there are about 6800 m3 of liquid sodium-bearing and liquid high-level wastes (HLW), and 3800 m3 of solid calcined HLW. One of the waste processing options under consideration includes separation of the HLW into high activity and low activity (LAW) wastes, followed by immobilization. Preliminary glasses were synthesized for the sodium-bearing, alumina-bearing, and the zirconia-bearing LAW fractions after radionuclide separations. The glasses were formed by crucible melting of a mixture of reagent chemicals representative of the LAW waste streams and frit additives at 1200 °C for 5 hours, followed by overnight annealing at 550 °C and furnace cooling of the melt. These glasses were characterized for density, elastic property, viscosity, chemical durability, structural parameters, and glass phase separation. The results are compared with that of the Hanford's standard glass ARM-i, Savannah River's benchmark glass EA, and the ICPP's grout waste form prepared using the simulated non-radioactive sodium-bearing waste fraction.


2015 ◽  
Vol 1113 ◽  
pp. 388-397 ◽  
Author(s):  
Ain Munirah Ahmad ◽  
Zulkifli Abdul Rashid ◽  
Azil Bahari Alias ◽  
M. Shahnor Bani ◽  
Ruslan Hashim ◽  
...  

In this work, the prediction of the overpressure resulting from a vapor cloud explosion (VCE) will be conducted from external area of a chemical process plant. Based on Feyzin Refinery disaster, this study will analyzed and focused on the spillage from a delayed ignition causing a VCE from the T61-443 sphere tank. TNT Mass Method and Baker-Strehlow models are used to estimate the overpressure of the explosion. The results are presented in the form of table and figures to compare the two methods and justify the overpressure predicted.


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