Robert Barletta - Academia.edu (original) (raw)
Papers by Robert Barletta
A new approach, termed SIPS (Small In-Tank Erocessing System), that enables the intank processing... more A new approach, termed SIPS (Small In-Tank Erocessing System), that enables the intank processing and separation of high-level tank wastes into high-level waste (HLW) and lowlevel waste (LLW) streams that are suitable for vitrification, is described. Presently proposed pretreatment systems, such as enhanced sludge washing (ESW) and TRUEX, require that the high-level tank wastes be retrieved and pumped to a large, centralized processing facility, where the various waste components are separated into a relatively small, radioactively concentrated stream (HLW), and a relatively large, predominantly non-radioactive stream (LLW). In SIPS, a small process module, typically on the order of 1 meter in diameter and 4 meters in length, is insetted into a tank. During a period of approximately six months, it processes the solifliquid materials in the tank, separating them into liquid HLW and liquid LLW output streams that are pumped away in two small diameter (typically 3 cm 0.d.) pipes. The SIPS module would be serviced by six small diameter (-3 cm 0.d.) pipesthe two output pipes for the HLW and LLW streams mentioned above, a water input pipe, a nitric acid (-3 M) input pipe, and input/output pipes to hydraulically loadunload ion exchange beads. An illustrative SIPS processing cycle is described. During the first half of the cycle, solifliquid slurry from the tank is admitted to an internal compartment in the module (Compartment "B"), where the material is water washed.
![Research paper thumbnail of Evaluation of the radiation resistance of high-density polyethylene. [Gamma Rays]](https://attachments.academia-assets.com/98076774/thumbnails/1.jpg)
](DE84 010515 Mechanical tests following gamma Irradiation and creep tests during Irradiation have ... more DE84 010515 Mechanical tests following gamma Irradiation and creep tests during Irradiation have been conducted on high-density polyethylene (HOPE) to provide data to help assess the adequacy of this material for use 1n high integrity containers (HICs). Two types of HOPE, a highly cross-linked rotationally molded material and * non-cross-1 Inked blow molded material, were used in.these tests. Gamma-ray Irradiations were performed at several dose rates in envrionments of air, BarnweiV and Hanford backfill soils, and ion-exchange resins. The results of tensile and bend tests on these materials following Irradiation are presented along with results on creep during irradiation.
Strippable coating material considered for use in the TMI-2 reactor building decontamination has ... more Strippable coating material considered for use in the TMI-2 reactor building decontamination has been tested for Sr, Cs, and Co leachability, for radiation stability, and for resistance to biodegradation. It was also immersion tested in water, a water solution saturated with toluene and xylene, toluene, xylene, and liquid scintillation counting (LSC) cocktail. Leach testing, performed using a modified IAEA procedure, resulted in all of the Cs and Co activity and most of the Sr activity being released from the coating in just a few days. Immersion resulted in swelling of the coating in all of the liquids tested. Gamma irradiation of the coating did not produce any apparent physical changes in the coating to a dose of 1 x 10 8 rad, however, radiolytic gas generation of H2, CO, and CO2 was observed. Biodegradation testify was performed in soil samples from the Barnwell, South Carolina, and Hanford, Washington, low-level waste disposal sites. Progress of the biodegradations was monitored using the CO2 produced from microbial respiration. Biodegradation of xbQ coating occurs readily in both soils although somewhat faster in Hanford soil. These test results indicate that strippable coating radwaste of itself will not meet the requirements for stabilized Class B waste outlined in 10 CFR 61 (proposed) and the NRC Draft Branch Technical Position on Waste Form. *Work carried out under the auspices of the Nuclear Regulatory Commission,
The leachabllty of Cs and Sr from cement solidified ion exchange media claimed Co be representati... more The leachabllty of Cs and Sr from cement solidified ion exchange media claimed Co be representative of Che Epicor-II prefilterc (D-m't) ia presented. The Cs and Sr release 1B significantly lower than that typically observed for organic ion exchange resin/cement compositea. The effect of radiation up to a total dose of 10 7 Gy upon the leachabllity and mechanical integrity (aa measured by HCC-11) of Dmix/cement composites has been investigated. No deleterious effects were found.
An inventory has been compiled of the isotopes of half-life >5 years buried in eight o... more An inventory has been compiled of the isotopes of half-life >5 years buried in eight of the trenches at the Sheffield low-level waste burial site. This was accomplished through a search of the Sheffield radioactive shipment records (RSRs). Pertinent information from some 3200 fuel cycle RSRs and 1700 non-fuel cycle RSRs has been stored in a computerized data base and
Transactions of the American Nuclear Society
As a result of the U.S. weapons production program, there are now hundreds of large tanks contain... more As a result of the U.S. weapons production program, there are now hundreds of large tanks containing highly radioactive wastes. Safe disposal of these wastes requires their processing and separations into a small volume of highly radioactive waste (HLW) and a much larger volume of low-level waste (LLW). The HLW waste would then be vitrified and transported to a geologic repository. To date, the principal approach proposed for the separation envisions a large, centralized process facility. The small in-tank processing system (SIPS) is a proposed new, small modular concept for the in-tank processing and separation of wastes into HLW and LLW output streams suitable for vitrification. Instead of pumping the retrieved tank wastes as a solid/liquid slurry over long distances to a centralized process facility, SIPS would employ a small process module, typically â¼1 m in diameter and 4 m long, which would be inserted into the tank. Over a period of â 6 months, the module would process the s...
MRS Proceedings, 1993
Particle bed reactors (PBRs) have the potential for providing compact power sources for both spac... more Particle bed reactors (PBRs) have the potential for providing compact power sources for both space power and propulsion applications. The reactors operate in the temperature range of 2000 to 3000 K and, for propulsion systems, utilize hydrogen as a coolant. Given these overall operating conditions, the need exists to develop and verify the performance of various reactor components, particularly those which must operate at the more extreme conditions of temperature and hydrogen flow rate. These components must undergo multiple thermal cycles between cryogenic and exit temperatures. In addition, some of the components are subject to a thermal gradient of thousands of degrees Kelvin over a few centimeters.A number of approaches directed towards meeting these needs have been developed. These include both monolithic ceramics (e.g. boron nitride) as well as coated composites consisting of refractory carbides (ZrC, NbC and TaC) on carbon-based substrates. Full and partial scale components ...
As a part of the component development process for the particle bed reactor (PBR), it is necessar... more As a part of the component development process for the particle bed reactor (PBR), it is necessary to develop coatings which will be time and temperature stable at extremely high temperatures in flowing hydrogen. These coatings must protect the underlying carbon structure from attack by the hydrogen coolant. Degradation which causes small changes in the reactor component, e.g. hole diameter in the hot frit, can have a profound effect on operation. The ability of a component to withstand repeated temperature cycles is also a coating development issue. Coatings which crack or spall under these conditions would be unacceptable. While refractory carbides appear to be the coating material of choice for carbon substrates being used in PBR components, the method of applying these coatings can have a large effect on their performance. Two deposition processes for these refractory carbides, chemical vapor deposition (CVD) and chemical vapor reaction (CVR) have been evaluated. Screening tests for these coatings consisted of testing of coated 2-D and 3-D weave carbon-carbon in flowing hot hydrogen at one atmosphere. Carbon loss from these samples was measured as a function of time. Exposure temperatures up to 3000 K were used and samples were exposed in a cyclical fashion, cooling to room temperature between exposures. The results of these measurements are presented along with an evaluation of the relative merits of CVR and CVD coatings for this application.
This report was prepared as an account of work sponsored by an agency of the United States Govern... more This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressor implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. NOTICE PORlleHS gF ?HIS REPORT ARE ILLEGIBLE.' It has bssil reprQduced from the best awailable copy ta permit the broadest posstbk availnb!l?ty, DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government.
Spectrochimica Acta Part A: Molecular Spectroscopy, 1977
ABSTRACT
The Journal of Chemical Physics, 1977
The difference between the atomic force constant for oxygen in ice I and liquid water, and that i... more The difference between the atomic force constant for oxygen in ice I and liquid water, and that in the vapor phase is determined from an analysis of H2 16O/H2 18O isotope fractionation factors. It is shown that the force constants in liquid water depend explicitly upon the hydrogen-bond distribution in the liquid phase, and upon fusion the average number of hydrogen bonds per H2O decreases from 4 to 3. This result and the number of hydrogen bonds in water above the ice point are compared with the numbers obtained from molecular dynamics calculations and the cluster and lattice–gas theories of liquid water.
The Journal of Chemical Physics, 1979
ABSTRACT
A new approach, termed SIPS (Small In-Tank Erocessing System), that enables the intank processing... more A new approach, termed SIPS (Small In-Tank Erocessing System), that enables the intank processing and separation of high-level tank wastes into high-level waste (HLW) and lowlevel waste (LLW) streams that are suitable for vitrification, is described. Presently proposed pretreatment systems, such as enhanced sludge washing (ESW) and TRUEX, require that the high-level tank wastes be retrieved and pumped to a large, centralized processing facility, where the various waste components are separated into a relatively small, radioactively concentrated stream (HLW), and a relatively large, predominantly non-radioactive stream (LLW). In SIPS, a small process module, typically on the order of 1 meter in diameter and 4 meters in length, is insetted into a tank. During a period of approximately six months, it processes the solifliquid materials in the tank, separating them into liquid HLW and liquid LLW output streams that are pumped away in two small diameter (typically 3 cm 0.d.) pipes. The SIPS module would be serviced by six small diameter (-3 cm 0.d.) pipesthe two output pipes for the HLW and LLW streams mentioned above, a water input pipe, a nitric acid (-3 M) input pipe, and input/output pipes to hydraulically loadunload ion exchange beads. An illustrative SIPS processing cycle is described. During the first half of the cycle, solifliquid slurry from the tank is admitted to an internal compartment in the module (Compartment "B"), where the material is water washed.
DE84 010515 Mechanical tests following gamma Irradiation and creep tests during Irradiation have ... more DE84 010515 Mechanical tests following gamma Irradiation and creep tests during Irradiation have been conducted on high-density polyethylene (HOPE) to provide data to help assess the adequacy of this material for use 1n high integrity containers (HICs). Two types of HOPE, a highly cross-linked rotationally molded material and * non-cross-1 Inked blow molded material, were used in.these tests. Gamma-ray Irradiations were performed at several dose rates in envrionments of air, BarnweiV and Hanford backfill soils, and ion-exchange resins. The results of tensile and bend tests on these materials following Irradiation are presented along with results on creep during irradiation.
Strippable coating material considered for use in the TMI-2 reactor building decontamination has ... more Strippable coating material considered for use in the TMI-2 reactor building decontamination has been tested for Sr, Cs, and Co leachability, for radiation stability, and for resistance to biodegradation. It was also immersion tested in water, a water solution saturated with toluene and xylene, toluene, xylene, and liquid scintillation counting (LSC) cocktail. Leach testing, performed using a modified IAEA procedure, resulted in all of the Cs and Co activity and most of the Sr activity being released from the coating in just a few days. Immersion resulted in swelling of the coating in all of the liquids tested. Gamma irradiation of the coating did not produce any apparent physical changes in the coating to a dose of 1 x 10 8 rad, however, radiolytic gas generation of H2, CO, and CO2 was observed. Biodegradation testify was performed in soil samples from the Barnwell, South Carolina, and Hanford, Washington, low-level waste disposal sites. Progress of the biodegradations was monitored using the CO2 produced from microbial respiration. Biodegradation of xbQ coating occurs readily in both soils although somewhat faster in Hanford soil. These test results indicate that strippable coating radwaste of itself will not meet the requirements for stabilized Class B waste outlined in 10 CFR 61 (proposed) and the NRC Draft Branch Technical Position on Waste Form. *Work carried out under the auspices of the Nuclear Regulatory Commission,
The leachabllty of Cs and Sr from cement solidified ion exchange media claimed Co be representati... more The leachabllty of Cs and Sr from cement solidified ion exchange media claimed Co be representative of Che Epicor-II prefilterc (D-m't) ia presented. The Cs and Sr release 1B significantly lower than that typically observed for organic ion exchange resin/cement compositea. The effect of radiation up to a total dose of 10 7 Gy upon the leachabllity and mechanical integrity (aa measured by HCC-11) of Dmix/cement composites has been investigated. No deleterious effects were found.
An inventory has been compiled of the isotopes of half-life >5 years buried in eight o... more An inventory has been compiled of the isotopes of half-life >5 years buried in eight of the trenches at the Sheffield low-level waste burial site. This was accomplished through a search of the Sheffield radioactive shipment records (RSRs). Pertinent information from some 3200 fuel cycle RSRs and 1700 non-fuel cycle RSRs has been stored in a computerized data base and
Transactions of the American Nuclear Society
As a result of the U.S. weapons production program, there are now hundreds of large tanks contain... more As a result of the U.S. weapons production program, there are now hundreds of large tanks containing highly radioactive wastes. Safe disposal of these wastes requires their processing and separations into a small volume of highly radioactive waste (HLW) and a much larger volume of low-level waste (LLW). The HLW waste would then be vitrified and transported to a geologic repository. To date, the principal approach proposed for the separation envisions a large, centralized process facility. The small in-tank processing system (SIPS) is a proposed new, small modular concept for the in-tank processing and separation of wastes into HLW and LLW output streams suitable for vitrification. Instead of pumping the retrieved tank wastes as a solid/liquid slurry over long distances to a centralized process facility, SIPS would employ a small process module, typically â¼1 m in diameter and 4 m long, which would be inserted into the tank. Over a period of â 6 months, the module would process the s...
MRS Proceedings, 1993
Particle bed reactors (PBRs) have the potential for providing compact power sources for both spac... more Particle bed reactors (PBRs) have the potential for providing compact power sources for both space power and propulsion applications. The reactors operate in the temperature range of 2000 to 3000 K and, for propulsion systems, utilize hydrogen as a coolant. Given these overall operating conditions, the need exists to develop and verify the performance of various reactor components, particularly those which must operate at the more extreme conditions of temperature and hydrogen flow rate. These components must undergo multiple thermal cycles between cryogenic and exit temperatures. In addition, some of the components are subject to a thermal gradient of thousands of degrees Kelvin over a few centimeters.A number of approaches directed towards meeting these needs have been developed. These include both monolithic ceramics (e.g. boron nitride) as well as coated composites consisting of refractory carbides (ZrC, NbC and TaC) on carbon-based substrates. Full and partial scale components ...
As a part of the component development process for the particle bed reactor (PBR), it is necessar... more As a part of the component development process for the particle bed reactor (PBR), it is necessary to develop coatings which will be time and temperature stable at extremely high temperatures in flowing hydrogen. These coatings must protect the underlying carbon structure from attack by the hydrogen coolant. Degradation which causes small changes in the reactor component, e.g. hole diameter in the hot frit, can have a profound effect on operation. The ability of a component to withstand repeated temperature cycles is also a coating development issue. Coatings which crack or spall under these conditions would be unacceptable. While refractory carbides appear to be the coating material of choice for carbon substrates being used in PBR components, the method of applying these coatings can have a large effect on their performance. Two deposition processes for these refractory carbides, chemical vapor deposition (CVD) and chemical vapor reaction (CVR) have been evaluated. Screening tests for these coatings consisted of testing of coated 2-D and 3-D weave carbon-carbon in flowing hot hydrogen at one atmosphere. Carbon loss from these samples was measured as a function of time. Exposure temperatures up to 3000 K were used and samples were exposed in a cyclical fashion, cooling to room temperature between exposures. The results of these measurements are presented along with an evaluation of the relative merits of CVR and CVD coatings for this application.
This report was prepared as an account of work sponsored by an agency of the United States Govern... more This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressor implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. NOTICE PORlleHS gF ?HIS REPORT ARE ILLEGIBLE.' It has bssil reprQduced from the best awailable copy ta permit the broadest posstbk availnb!l?ty, DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government.
Spectrochimica Acta Part A: Molecular Spectroscopy, 1977
ABSTRACT
The Journal of Chemical Physics, 1977
The difference between the atomic force constant for oxygen in ice I and liquid water, and that i... more The difference between the atomic force constant for oxygen in ice I and liquid water, and that in the vapor phase is determined from an analysis of H2 16O/H2 18O isotope fractionation factors. It is shown that the force constants in liquid water depend explicitly upon the hydrogen-bond distribution in the liquid phase, and upon fusion the average number of hydrogen bonds per H2O decreases from 4 to 3. This result and the number of hydrogen bonds in water above the ice point are compared with the numbers obtained from molecular dynamics calculations and the cluster and lattice–gas theories of liquid water.
The Journal of Chemical Physics, 1979
ABSTRACT