Engineering topics
Publications and source records attributed to Dixon, K. L..
This report presents the environmental dose assessment methods and the estimated potential doses to the public from 2021 Savannah River Site (SRS) air and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios, such as the consumption of wildlife or goat milk.
Groundwater beneath the M-Area HWMF is contaminated with chlorinated ethenes including trichloroethylene (TCE) and tetrachloroethylene (PCE). SRS operates a network of recovery wells designed to hydraulically contain and capture the high concentration VOC plume in the Lost Lake Aquifer Zone (LLAZ) (Figure 1). The recovery wells are connected to the M-1 Air Stripper and the system is permitted by the South Carolina Department of Environmental Control (SCDHEC) to operate at a total flow of 610 gpm. RWM 8, which is one of ten operational recovery wells, has historically operated at a flow rate of approximately 40 gpm. RWM 8 was installed with four separate 10-ft screens that spanned the LLAZ with a continuous gravel pack spaced as shown in Figure 2. The three uppermost screens are located within the LLAZ whereas the deepest screen is located within the middle sand of the Crouch Branch Confining Unit (CBCU). Area Closure Projects (ACP) installed a permanent packer in May 2019 to isolate the lowest screen from the pump with the goal being to target the zone of highest concentration in the LLAZ. ACP expressed concern that a substantial portion of the flow from RWM 8 comes from the lower screen. With this screen isolated from service, flow from the well may be below the desired operational envelope for the well. The reconfiguration of RWM 8 presented an opportunity to re-evaluate the performance characteristics of the well. Following placement of the packer and relocation of the pump, the well was redeveloped. To assess the effects of eliminating the lower screen, a step-drawdown test was planned. The purpose of this test was to establish new baseline well performance properties including specific capacity, well efficiency, and well loss coefficients. Data from the step-drawdown testing was also used to estimate a maximum pumping rate for RWM 8 under the new configuration. The setup for the step-drawdown test facilitated a subsequent constant rate aquifer pumping test aimed at determining aquifer hydraulic properties. Properties estimated for the LLAZ included transmissivity and storativity. Following shutdown of RWM 8, recovery data were also collected and analyzed to estimate aquifer properties. This report discusses the hydrologic tests conducted following the reconfiguration of RWM 8. The information provided in this report may serve as input to subsequent updates to the groundwater flow and contaminant transport model for A/M Area.
Three short duration injection tests were conducted on wells at the humate test site. For each injection event, potable water was gravity drained into the well casing. Pressure response was monitored in the injection well and these data were used to estimate the injection capacity of each well. Injection capacity was calculated by dividing the average injection flow rate by the head increase observed in the injection well. Nearby injection wells were used as observation wells and data from these wells were used to estimate the local hydraulic conductivity. The results of this analysis show that it is hydraulically feasible to gravity inject water into the test wells. The estimated water injection capacity of each well as determined by injecting potable water is shown. It is important to note that these short duration tests utilized water and not the humate solution that will ultimately be injected into the aquifer. The results of these tests do not account for physical or chemical processes that may occur over longer time scales. Injection well performance typically declines over time due to water-chemistry issues, air entrainment, and aquifer clogging. Therefore, these results should be viewed as optimistic estimates of injection capacity. Data from the injection tests were analyzed to estimate local aquifer properties. Transmissivity values for all tests ranged from 0.62 to 1.07 ft 2 /min with an average value of 0.805 ft 2 /min. Hydraulic conductivity was calculated by dividing transmissivity by the aquifer thickness (53 ft). Hydraulic conductivity ranged from 16.7 to 29.2 ft/day with an average value of 21.9 ft/day. Storativity values ranged from 0.0001 to 0.001 with an average value of 0.0006.
The Robotic Refueling Mission 3 (RRM3) payload launched aboard a SpaceX rocket en route to the International Space Station on December 5th, 2018. The Goddard Space Flight Center designed payload carried approximately 50 liters of liquid methane onboard, with a mission to demonstrate long term storage and transfer of the cryogenic fluid in microgravity. Kennedy Space Center (KSC) was tasked to design, fabricate, test, and operate a system equipped to fill an RRM3 dewar with liquid methane prior to launch. Though KSC has a rich history of fueling rockets and payloads, no such operations had previously been accomplished using liquid methane. As such, all of the hardware and processes had to be developed from scratch. The completed ground system design, along with the verification and validation testing will be outlined in this paper. Several challenges that were met and overcome during procurement of the high purity methane are described. In addition, budget restrictions prohibited fueling operations from occurring in traditional processing facilities. The unique and creative solutions which were required to maintain payload cleanliness during cryogenic servicing are also detailed.
An aquifer pumping test was conducted on the Lost Lake Aquifer Zone (LLAZ) at the recently installed recovery well RWM018 in accordance with the approved test plan (Dixon, 2018). The objective of the testing was to determine baseline well performance parameters and aquifer hydraulic conductivity. Well performance parameters determined included specific capacity, well efficiency, and head loss coefficients. The specific capacity of RWM018 was determined to be approximately 3.2 gpm/ft of drawdown. At baseline conditions (all active recovery wells operating except RWM018), RWM018 has approximately 26 ft of head above the well screen. This suggests that RWM018 can sustain a maximum pumping rate of 83 gpm with drawdown at the top of screen. Well efficiency was inversely related to pumping rate and decreased from 97% to 91% over a pumping range of approximately 20 to 55 gpm. These results suggest that RWM018 is an efficient well and does not require any further well development activities. The aquifer head loss coefficient was determined to be 2.1 ft/ft 3 /min and the well loss coefficient was determined to be 0.03 min 2 /ft 5 .
An aquifer pumping test was conducted on the Lost Lake Aquifer Zone (LLAZ) at the recently installed recovery well RWM018 in accordance with the approved test plan (Dixon, 2018). The objective of the testing was to determine baseline well performance parameters and aquifer hydraulic conductivity. Well performance parameters determine d included specific capacity, well efficiency, and head loss coefficients. The specific capacity of RWM018 was determined to be approximately 3.2 gpm/ft of drawdown. At baseline conditions (all active recovery wells operating except RWM018), RWM018 has approximately 26 ft of head above the well screen. This suggests that RWM018 can sustain a maximum pumping rate of 83 gpm with drawdown at the top of screen. Well efficiency was inversely related to pumping rate and decreased from 97% to 91% over a pumping range of approximately 20 to 55 gpm. These results suggest that RWM018 is an efficient well and does not require any further well development activities. The aquifer head loss coefficient was determined to be 2.1 ft/ft 3 /min and the well loss coefficient was determined to be 0.03 min 2 /ft 5 .
A total of eight short duration injection tests were conducted on wells at the M-Area Western Sector In-Situ Chemical Oxidation (ISCO) test site. For each injection event, approximately 200 gallons of water were gravity drained into the well casing. Pressure response was monitored in the injection well and these data were used to estimate the injection capacity of each well. Nearby injection wells were used as observation wells and data from these wells were used to estimate local hydraulic conductivity.
The Waste Treatment and Immobilization Plant (WTP) at Hanford is being constructed to treat 56 million gallons of radioactive waste currently stored in underground tanks at the Hanford site. Operation of the WTP will generate several solid secondary waste (SSW) streams including spent spherical resorcinol formaldehyde cation exchange resin (IXr). The current plan for safe disposal of IXr is solidification in cementitious material (CM) typically comprised of cement, fly ash and blast furnace slag. Three CM formulations were tested to stabilize IXr for long-term land disposal. Two IXr loading rates, 0.1 and 0.3 v/v IXr:grout were used with the three CM formulations to prepare simulated waste form monoliths for hydraulic property testing. Following curing, the monoliths were removed from molds and tested to determine saturated hydraulic conductivity (K{sub sat}) and water retention properties. K{sub sat} was measured using a standard flexible permeameter method ASTM D-5084-10. A constant vapor pressure (CVP) method was used to determine van Genuchten parameters for desorption moisture retention curves for each of the SSW grout formulations. For the CVP method, vacuum saturated, intact wafers approximately 1.25 cm thick were placed above a saturated salt solution inside a sealed container for equilibration. Each saturated salt solution has an associated vapor pressure related to relative humidity in the container. Visual examination and three-dimensional x-ray micro computed tomography (μCT) indicated that the IXr was uniformly distributed in the cured waste form. Saturated hydraulic conductivity was within the range previously reported by Flach et al. in a study of the hydraulic properties of 98 pastes and grouts. The solidification of IXr in CM resulted in a waste form with water retention properties similar to cementitious pastes. (authors)
This memorandum documents the recovery and evaluation of selected E-Area Corrosion coupons and updates the schedule for future recovery and evaluation efforts.
A database of the population within 50 miles of the Savannah River Site (SRS) is needed to estimate radiation doses to a collective group of individuals. The offsite population data was last updated with the 2000 census data (Simpkins 2002; Koffman 2001) and has been once again updated with the 2010 census data. The data acquisition process for the 2010 census data was the same as for the 2000 census data. Koffman (2001) provides complete details of the process and is provided in Appendix A.
Dose-release factors (DRFs) were calculated for potential atmospheric releases of several radionuclides from the E-Area Low-Level Waste Facility (ELLWF). The ELLWF receives solid low-level radioactive waste from across the Savannah River Site (SRS) and offsite for disposal. These factors represent the maximum dose a receptor would receive if standing at either 100 m or 11,410 m (Site Boundary) from the edge of an ELLWF disposal unit which are points of assessment (POA) for Department of Energy (DOE) Order 435.1 performance assessments (PA). The DRFs were calculated for 1 Ci of the specified radionuclide being released from the ground surface to the atmosphere (mrem per curie released). The calculation conservatively represented the ELLWF as a point source, and conservatively assumed the receptor was positioned at the center of the contaminant plume and continuously exposed for a period of one year. These DRFs can be refined to take into consideration disposal unit size, proximity and timing of peak dose to establish less conservative radionuclide specific disposal limits. DRFs were calculated for H-3 and C-14 in Revision 0 of this report. H-3 as HTO and C-14 as CO 2 were identified as volatile radionuclides of potential concern in earlier radionuclide screening studies. In Revision 1, DRFs were calculated for eight additional radionuclides identified by an updated screening analysis as potentially important volatile radionuclides. These include Ar-37, Ar-39, Ar-42, Hg-194, Hg- 203, Kr-81, Kr-85, and Xe-127.
The Hanford Site Effluent Treatment Facility (ETF) currently treats aqueous waste streams generated during site cleanup activities. When the Hanford Tank Waste Treatment and Immobilization Plant (WTP) begins operations, including Direct Feed Low Activity Waste (DFLAW) vitrification, a liquid secondary waste (LSW) stream from the WTP will need to be treated. The volume of effluent for treatment at the ETF will increase significantly. The powdered salt waste form produced by the ETF will be replaced by a stabilized solidified waste form for disposal in Hanford’s Integrated Disposal Facility (IDF). Washington River Protection Solutions is implementing a Secondary Liquid Waste Immobilization Technology Development Plan to address the technology needs for a waste form and solidification process to treat the increased volume of waste planned for disposal at the IDF. Waste form testing to support this plan is composed of work in the near term to provide data as input to a performance assessment (PA) for Hanford’s IDF. In 2015, three Hanford Liquid Secondary Waste simulants were developed based on existing and projected waste streams. Using these waste simulants, fourteen mixes of Hanford Liquid Secondary Waste were prepared and tested varying the waste simulant, the water-to-dry materials ratio, and the dry materials blend composition.1 In FY16, testing was performed using a simulant of the EMF process condensate blended with the caustic scrubber—from the Low Activity Waste (LAW) melter—, processed through the ETF. The initial EMF-16 simulant will be based on modeling efforts performed to determine the mass balance of the ETF for the DFLAW.2 The compressive strength of all of the mixes exceeded the target of 3.4 MPa (500 psi) to meet the requirements identified as potential IDF Waste Acceptance Criteria in Table 1 of the Secondary Liquid Waste Immobilization Technology Development Plan.3 The hydraulic properties of the waste forms tested (hydraulic conductivity and water characteristic curves) were comparable to the properties measured on the Savannah River Site (SRS) Saltstone waste form. Future testing should include efforts to first; 1) determine the rate and amount of ammonia released during each unit operation of the treatment process to determine if additional ammonia management is required, then; 2) reduce the ammonia content of the ETF concentrated brine prior to solidification, making the waste more amenable to grouting, or 3) manage the release of ammonia during production and ongoing release during storage of the waste form, or 4) develop a lower pH process/waste form thereby precluding ammonia release.
This memorandum documents the update and verification of the HELP model which is used to provide infiltration estimates for facility closure caps.