Powered by Deep Web Technologies
Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ETR Tank Waste Treatment and Immobilization Plant - Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Full Document and Summary Versions are available for download Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - External Flowsheet Review Team (Technical) Report Summary - Flowsheet for the Hanford Waste Treatment Plant More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

2

HANFORD TANK CLEANUP UPDATE  

SciTech Connect

Access to Hanford's single-shell radioactive waste storage tank C-107 was significantly improved when workers completed the cut of a 55-inch diameter hole in the top of the tank. The core and its associated cutting equipment were removed from the tank and encased in a plastic sleeve to prevent any potential spread of contamination. The larger tank opening allows use of a new more efficient robotic arm to complete tank retrieval.

BERRIOCHOA MV

2011-04-07T23:59:59.000Z

3

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

- Tank Waste Treatment and Immobilization Plant - - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report This is a comprehensive review ofthe Hanford WTP estimate at completion - assessing the project scope, contract requirements, management execution plant, schedule, cost estimates, and risks. Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report More Documents & Publications TBH-0042 - In the Matter of Curtis Hall

4

Hanford Tank Waste Residuals  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Hanford Tank Waste Residuals DOE HLW Corporate Board November 6, 2008 Chris Kemp, DOE ORP Bill Hewitt, YAHSGS LLC Hanford Tanks & Tank Waste * Single-Shell Tanks (SSTs) - ~27 million gallons of waste* - 149 SSTs located in 12 SST Farms - Grouped into 7 Waste Management Areas (WMAs) for RCRA closure purposes: 200 West Area S/SX T TX/TY U 200 East Area A/AX B/BX/BY C * Double-Shell Tanks (DSTs) - ~26 million gallons of waste* - 28 DSTs located in 6 DST Farms (1 West/5 East) * 17 Misc Underground Storage Tanks (MUST) * 43 Inactive MUST (IMUST) 200 East Area A/AX B/BX/BY C * Volumes fluctuate as SST retrievals and 242-A Evaporator runs occur. Major Regulatory Drivers * Radioactive Tank Waste Materials - Atomic Energy Act - DOE M 435.1-1, Ch II, HLW - Other DOE Orders * Hazardous/Dangerous Tank Wastes - Hanford Federal Facility Agreement and Consent Order (TPA) - Retrieval/Closure under State's implementation

5

Hanford Waste Tank Plant PIA, Richland Operations Office | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Waste Tank Plant PIA, Richland Operations Office Hanford Waste Tank Plant PIA, Richland Operations Office Hanford Waste Tank Plant PIA, Richland Operations Office Hanford...

6

Hanford Site C Tank Farm Meeting Summary - May 2011 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

May 2011 Hanford Site C Tank Farm Meeting Summary - May 2011 Hanford Site C Tank Farm Meeting Summary More Documents & Publications Hanford Site C Tank Farm Meeting Summary -...

7

Hanford Site C Tank Farm Meeting Summary - September 2010 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

September 2010 Hanford Site C Tank Farm Meeting Summary - September 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

8

Hanford Site C Tank Farm Meeting Summary - September 2009 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

September 2009 Hanford Site C Tank Farm Meeting Summary - September 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

9

Hanford Site C Tank Farm Meeting Summary - February 2009 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

February 2009 Hanford Site C Tank Farm Meeting Summary - February 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank...

10

Hanford Site C Tank Farm Meeting Summary - September 2009 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Site C Tank Farm Meeting Summary - September 2009 Hanford Site C Tank Farm Meeting Summary - September 2009 Meeting Summary for Development of the Hanford Site C Tank Farm...

11

Hanford Site C Tank Farm Meeting Summary - May 2010 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0 Hanford Site C Tank Farm Meeting Summary - May 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

12

Hanford Site C Tank Farm Meeting Summary - July 2010 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

July 2010 Hanford Site C Tank Farm Meeting Summary - July 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm...

13

Hanford Site C Tank Farm Meeting Summary - May 2009 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

09 Hanford Site C Tank Farm Meeting Summary - May 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

14

Hanford Site C Tank Farm Meeting Summary - January 2010 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0 Hanford Site C Tank Farm Meeting Summary - January 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

15

Hanford Site C Tank Farm Meeting Summary - January 2011 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1 Hanford Site C Tank Farm Meeting Summary - January 2011 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm Meeting...

16

Hanford Site C Tank Farm Meeting Summary - October 2009 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

October 2009 Hanford Site C Tank Farm Meeting Summary - October 2009 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Hanford Site C Tank Farm...

17

Hanford Site C Tank Farm Meeting Summary - March 2010 | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

March 2010 Hanford Site C Tank Farm Meeting Summary - March 2010 Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment Meeting Summary for...

18

Hanford Tank Waste Treatment and Immobilization Plan Project...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Tank Waste Treatment and Immobilization Plan Project PIA, Richland Operations Office Hanford Tank Waste Treatment and Immobilization Plan Project PIA, Richland Operations...

19

Hanford Single-Shell Tank Integrity Program  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Operations Contract Hanford Single Hanford Single- -Shell Shell Hanford Single Hanford Single Shell Shell Tank Integrity Tank Integrity Program Program Herbert S Berman Herbert S Berman Herbert S. Berman Herbert S. Berman July 29, 2009 July 29, 2009 1 Page 1 Tank Operations Contract Introduction * The Hanford site's principle historic mission was plutonium production for the manufacture of nuclear weapons. * Between 1944 and 1988, the site operated nine graphite- moderated light-water production reactors to irradiate moderated, light-water, production reactors to irradiate fuel and produce plutonium. * Four large chemical separations plants were run to extract plutonium from the fuel, and a variety of laboratories, support facilities, and related infrastructure to support production

20

Enclosure 1 Additional Information on Hanford Tank Wastes  

E-Print Network (OSTI)

Enclosure 1 Additional Information on Hanford Tank Wastes Introduction The U. S. Nuclear Regulatory of Energy to the U. S. Environmental Protection Agency addressing the Hanford Tank and K Basin Wastes (CBFO stored in two tanks (designated as tanks 241-AW-103 and 241-AW-105) at the Hanford Site are not high

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

RETRIEVAL & TREATMENT OF HANFORD TANK WASTE  

SciTech Connect

The Hanford Tank Farms contain 53 million gal of radioactive waste accumulated during over 50 years of operations. The waste is stored in 177 single-shell and double-shell tanks in the Hanford 200 Areas. The single-shell tanks were put into operation from the early 1940s through the 1960s with wastes received from several generations of processing facilities for the recovery of plutonium and uranium, and from laboratories and other ancillary facilities. The overall hanford Tank Farm system represents one of the largest nuclear legacies in the world driving towards completion of retrieval and treatment in 2028 and the associated closure activity completion by 2035. Remote operations, significant radiation/contamination levels, limited access, and old facilities are just some of the challenges faced by retrieval and treatment systems. These systems also need to be able to successfully remove 99% or more of the waste, and support waste treatment, and tank closure. The Tank Farm retrieval program has ramped up dramatically in the past three years with design, fabrication, installation, testing, and operations ongoing on over 20 of the 149 single-shell tanks. A variety of technologies are currently being pursued to retrieve different waste types, applications, and to help establish a baseline for recovery/operational efficiencies. The paper/presentation describes the current status of retrieval system design, fabrication, installation, testing, readiness, and operations, including: (1) Saltcake removal progress in Tanks S-102, S-109, and S-112 using saltcake dissolution, modified sluicing, and high pressure water lancing techniques; (2) Sludge vacuum retrieval experience from Tanks C-201, C-202, C-203, and C-204; (3) Modified sluicing experience in Tank C-103; (4) Progress on design and installation of the mobile retrieval system for sludge in potentially leaking single-shell tanks, particularly Tank C-101; and (5) Ongoing installation of various systems in the next generation of tanks to be retrieved.

EACKER, J.A.; SPEARS, J.A.; STURGES, M.H.; MAUSS, B.M.

2006-01-20T23:59:59.000Z

22

Independent Oversight Review of Hanford Tank Farms Safety Basis...  

NLE Websites -- All DOE Office Websites (Extended Search)

Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades November 2011 Office of Safety and Emergency Management Evaluations Office of...

23

Independent Activity Report, Hanford Tank Farms - April 2013 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Farms - April 2013 Tank Farms - April 2013 Independent Activity Report, Hanford Tank Farms - April 2013 April 2013 Operational Awareness at the Hanford Tank Farms [HIAR-HANFORD-2013-04-15] The Office of Health, Safety and Security (HSS) Office of Safety and Emergency Management Evaluations (HS-45) Site Lead conducted an operational awareness visit to the Office of River Protection (ORP) to tour the Hanford Tank Farms, observe video inspection of single shell and double shell tanks, and observe Tank Farm project and staff meetings. Independent Activity Report, Hanford Tank Farms - April 2013 More Documents & Publications Independent Oversight Activity Report, Office of River Protection - May 2013 Independent Oversight Activity Report, Hanford Tank Farms - June 2013 Independent Activity Report, Office of River Protection Waste Treatment

24

Independent Oversight Activity Report, Hanford Tank Farms - June 2013 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Oversight Activity Report, Hanford Tank Farms - June Oversight Activity Report, Hanford Tank Farms - June 2013 Independent Oversight Activity Report, Hanford Tank Farms - June 2013 June 2013 Office of River Protection Assessment of Contractor Quality Assurance, Operational Awareness at the Hanford Tank Farms [HIAR NNSS-2012-12-03] The Office of Health, Safety and Security (HSS), Office of Safety and Emergency Management Evaluations (Independent Oversight) Site Lead conducted an operational awareness visit to the ORP Hanford Tank Farms, observed a Tank Farms morning meeting, toured the C Tank Farm, and observed a heavy (34,000 pound) lift. Independent Oversight Activity Report, Hanford Tank Farms - June 2013 More Documents & Publications Independent Activity Report, Office of River Protection Waste Treatment

25

Independent Oversight Review, Hanford Tank Farms - November 2011 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Review, Hanford Tank Farms - November 2011 Review, Hanford Tank Farms - November 2011 Independent Oversight Review, Hanford Tank Farms - November 2011 November 2011 Review of Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades The U.S. Department of Energy (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted an independent oversight review of the draft amendment to the Hanford Tank Farms safety basis for upgrading the double-shell tank (DST) primary tank ventilation (PTV) systems to safety-significant designation. The Tank Farms are Hazard Category 2 DOE nuclear facilities. The review was performed during the period July 25 - August 12, 2011 by the HSS Office of Enforcement and Oversight's Office of Safety and Emergency Management

26

Mineral formation during simulated leaks of Hanford waste tanks  

E-Print Network (OSTI)

Mineral formation during simulated leaks of Hanford waste tanks Youjun Deng a , James B. Harsh a at the US DOE Hanford Site, Washington, caus- ing mineral dissolution and re-precipitation upon contact mimicking tank leak conditions at the US DOE Hanford Site. In batch experiments, Si-rich solutions

Flury, Markus

27

EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review Environmental Management Advisory Board EM Tank Waste Subcommittee Report for SRS / Hanford Tank Waste Review Report Number TWS #003 EMAB EM-TWS SRS / Hanford Tank Waste June 23, 2011 This is the second report of the Environmental Management Tank Waste Subcommittee (EMTWS) of the Environmental Management Advisory Board (EMAB). The first report was submitted and accepted by the Assistant Secretary for Environmental Management (EM-1) in September 2010. The EM-TWS responded to three charges from EM-1 regarding the Waste Treatment and Immobilization Plant at Hanford (WTP) under construction in Richland, Washington. EM's responses were timely, and efforts have been

28

Rethinking the Hanford Tank Waste Program  

Science Conference Proceedings (OSTI)

The program to treat and dispose of the highly radioactive wastes stored in underground tanks at the U.S. Department of Energy's Hanford site has been studied. A strategy/management approach to achieve an acceptable (technically sound) end state for these wastes has been developed in this study. This approach is based on assessment of the actual risks and costs to the public, workers, and the environment associated with the wastes and storage tanks. Close attention should be given to the technical merits of available waste treatment and stabilization methodologies, and application of realistic risk reduction goals and methodologies to establish appropriate tank farm cleanup milestones. Increased research and development to reduce the mass of non-radioactive materials in the tanks requiring sophisticated treatment is highly desirable. The actual cleanup activities and milestones, while maintaining acceptable safety standards, could be more focused on a risk-to-benefit cost effectiveness, as agreed to by the involved stakeholders and in accordance with existing regulatory requirements. If existing safety standards can be maintained at significant cost savings under alternative plans but with a change in the Tri-Party Agreement (a regulatory requirement), those plans should be carried out. The proposed strategy would also take advantage of the lessons learned from the activities and efforts in the first phase of the two-phased cleanup of the Hanford waste tank farms.

Parker, F. L.; Clark, D. E.; Morcos, N.

2002-02-26T23:59:59.000Z

29

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

30

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

31

Hanford tanks initiative (HTI) work breakdown structure (WBS)dictionary  

Science Conference Proceedings (OSTI)

This dictionary lists the scope, deliverables, and interfaces for the various work elements of the Hanford Tanks Initiative. Cost detail is included for information only.

Mckinney, K.E.

1997-03-31T23:59:59.000Z

32

Parameters Impacting Crossflow Filter Performance of Hanford Tank ...  

Parameters Impacting Crossflow Filter Performance of Hanford Tank Waste Simulants Reid Peterson Justin Billings, Carolyn Burns, Richard Daniel, Phil Schonewill, Rick ...

33

Caustic Leaching of Hanford Tank S-110 Sludge  

SciTech Connect

This report describes the Hanford Tank S-110 sludge caustic leaching test conducted in FY 2001 at the Pacific Northwest National Laboratory. The data presented here can be used to develop the baseline and alternative flowsheets for pretreating Hanford tank sludge. The U.S. Department of Energy funded the work through the Efficient Separations and Processing Crosscutting Program (ESP; EM?50).

Lumetta, Gregg J.; Carson, Katharine J.; Darnell, Lori P.; Greenwood, Lawrence R.; Hoopes, Francis V.; Sell, Richard L.; Sinkov, Sergey I.; Soderquist, Chuck Z.; Urie, Michael W.; Wagner, John J.

2001-10-31T23:59:59.000Z

34

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1878, Rev. 0 1878, Rev. 0 Summary Notes from 5 - 7 May 2009 Office of River Protection Waste Management Area C Tank Farm Performance Assessment Input Meeting MP Connelly Washington River Protection Solutions LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800 EDT/EON: DRF UC: Cost Center: Charge Code: B&R Code: Total Pages: 15 Key Words: Waste Management Area C, Performance Assessment, tank closure, waste inventory Abstract: Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Waste Management Area C performance assessment TRADEMARK DISCLAIMER. 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

35

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Summary Notes from 24- 25 February 2009 Office of River Protection Waste Management Area C Performance Assessment Input Meeting Attendees: Representatives from Department of Energy-Office of River Protection (DOE-ORP), DOE Richland Operations Office (DOE-RL), DOE-Headquarters (DOE-HQ), the Washington State Department of Ecology (Ecology), and the U.S. Nuclear Regulatory Commission (NRC), met at the Ecology offices in Richland, Washington on 24 & 25 February 2009. EPA Region X staff participated on 25 February 2009 via teleconference. Discussion: DOE is pursuing closure of Waste Management Area C (WMA-C) located at the Hanford Site. At some point in the future, DOE and NRC will consult on waste determinations for these tank closures; additionally these tanks will be closed in coordination with EPA and

36

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3622, Rev. 0 3622, Rev. 0 Summary Notes from 1 - 3 September 2009 Office of River Protection Waste Management Area C Tank Farm Performance Assessment Input Meeting MP Connelly Washington River Protection Solutions LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV1 4800 EDT/ECN: DRF UC: Cost Center: Charge Code: B&R Code: Total Pages: 13 Key Words: Waste Management Area C, Performance Assessment, tank closure, waste inventory Abstract: Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Waste Management Area C performance assessment TRADEMARK DISCLAIMER. 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

37

EIS-0391: Hanford Tank Closure and Waste Management, Richland, Washington |  

NLE Websites -- All DOE Office Websites (Extended Search)

391: Hanford Tank Closure and Waste Management, Richland, 391: Hanford Tank Closure and Waste Management, Richland, Washington EIS-0391: Hanford Tank Closure and Waste Management, Richland, Washington Summary This EIS evaluates the environmental impacts for the following three key areas: (1) retrieval, treatment, and disposal of waste from 149 single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal of Hanford's waste and other DOE sites' low-level and mixed low-level radioactive waste. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 13, 2013 EIS-0391: Record of Decision Final Tank Closure and Waste Management Environmental Impact Statement for

38

EM Tank Waste Subcommittee Report for SRS and Hanford Tank Waste...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

incorporating chemistry. Such tools would allow the facile evaluation of the impacts of treatment and waste form alternatives on the overall disposition path for Hanford tank...

39

Hanford Determines Double-Shell Tank Leaked Waste From Inner Tank |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Determines Double-Shell Tank Leaked Waste From Inner Tank Determines Double-Shell Tank Leaked Waste From Inner Tank Hanford Determines Double-Shell Tank Leaked Waste From Inner Tank October 22, 2012 - 12:00pm Addthis Media Contacts Lori Gamache, ORP 509-372-9130 John Britton, WRPS 509-376-5561 RICHLAND - The Department of Energy's Office of River Protection (ORP), working with its Hanford tank operations contractor Washington River Protection Solutions, has determined that there is a slow leak of chemical and radioactive waste into the annulus space in Tank AY-102, the approximately 30-inch area between the inner primary tank and the outer tank that serves as the secondary containment for these types of tanks. This is the first time a double-shell tank (DST) leak from the primary tank into the annulus has been identified. There is no indication of waste in

40

Overview of Hanford Single Shell Tank (SST) Structural Integrity - 14023  

Science Conference Proceedings (OSTI)

To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project (SSTIP) in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford Single-Shell Tanks. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS. The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford Single-Shell Tanks has concluded that the tanks are structurally sound and meet current industry standards. Analysis of the remaining Hanford Single-Shell Tanks is scheduled for FY2014. Hanford Single-Shell Tanks are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than ? inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of the concrete tanks, looking for cracks and other surface conditions that may indicate signs of structural distress. The condition of the concrete and rebar of the Hanford Single-Shell Tanks is currently being tested and planned for additional activities in the near future. Concrete and rebar removed from the dome of a 65 year old tank was tested for mechanics properties and condition. Results indicated stronger than designed concrete with additional Petrographic examination and rebar completed. Material properties determined from previous efforts combined with current testing and construction document review will help to generate a database that will provide indication of Hanford Single-Shell Tank structural integrity.

Rast, Richard S.; Washenfelder, Dennis J.; Johnson, Jeremy M.

2013-11-14T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Independent Oversight Review, Hanford Tank Farms - December 2012 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

December 2012 December 2012 Independent Oversight Review, Hanford Tank Farms - December 2012 December 2012 Review of the Hanford Tank Farms Radiological Controls Activity-Level Implementation This report documents an independent review by the Office of Enforcement and Oversight (Independent Oversight) within the Office of Health, Safety and Security (HSS) of radiological protection program (RPP) activity-level implementation at the Hanford Tank Farms. The review was performed by the HSS Office of Safety and Emergency Management Evaluations. The purpose of this Independent Oversight targeted review effort is to evaluate the flowdown of occupational radiation protection requirements, as expressed in facility RPPs, to work planning, control, and execution processes, such as

42

Resolution of Hanford tanks organic complexant safety issue  

SciTech Connect

The Hanford Site tanks have been assessed for organic complexant reaction hazards. The results have shown that most tanks contain insufficient concentrations of TOC to support a propagating reaction. It has also been shown that those tanks where the TOC concentration approaches levels of concern, degradation of the organic complexants to less energetic compounds has occurred. The results of the investigations have been documented. The residual organic complexants in the Hanford Site waste tanks do not present a safety concern for long-term storage.

Kirch, N.W.

1998-05-14T23:59:59.000Z

43

Operational Awarness at Hanford Tank Farms, April 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-HANFORD-2013-04-15 Site: Hanford - Office of River Protection Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Operational Awareness at the Hanford Tank Farms Dates of Activity : 04/15-26/2013 Report Preparer: Robert E. Farrell Activity Description/Purpose: The Office of Health, Safety and Security (HSS) Office of Safety and Emergency Management Evaluations (HS-45) Site Lead conducted an operational awareness visit to the Office of River Protection (ORP) to tour the Hanford Tank Farms, observe video inspection of single shell and double shell tanks, and observe Tank Farm project and staff meetings. Result:

44

EA-0915: Waste Tank Safety Program Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE))

This EA evaluates the environmental impacts of the proposal to resolve waste tank safety issues at the Hanford Site near the City of Richland, Washington, and to reduce the risks associated with...

45

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT SEISMIC ANALYSIS OF HANFORD DOUBLE SHELL TANKS  

Science Conference Proceedings (OSTI)

M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratory (PNNL) to perform seismic analysis of the Hanford Site double-shell tanks (DSTs) in support of a project entitled ''Double-Shell Tank (DSV Integrity Project--DST Thermal and Seismic Analyses)''. The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST system at Hanford in support of Tri-Party Agreement Milestone M-48-14, The work described herein was performed in support of the seismic analysis of the DSTs. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). The work statement provided to M&D (PNNL 2003) required that the seismic analysis of the DSTs assess the impacts of potentially non-conservative assumptions in previous analyses and account for the additional soil mass due to the as-found soil density increase, the effects of material degradation, additional thermal profiles applied to the full structure including the soil-structure response with the footings, the non-rigid (low frequency) response of the tank roof, the asymmetric seismic-induced soil loading, the structural discontinuity between the concrete tank wall and the support footing and the sloshing of the tank waste. The seismic analysis considers the interaction of the tank with the surrounding soil and the effects of the primary tank contents. The DSTs and the surrounding soil are modeled as a system of finite elements. The depth and width of the soil incorporated into the analysis model are sufficient to obtain appropriately accurate analytical results. The analyses required to support the work statement differ from previous analysis of the DSTs in that the soil-structure interaction (SSI) model includes several (nonlinear) contact surfaces in the tank structure, and the contained waste must be modeled explicitly in order to capture the fluid-structure interaction behavior between the primary tank and contained waste.

MACKEY, T.C.

2006-03-17T23:59:59.000Z

46

Tank Waste Feed Delivery System Readiness at the Hanford Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Audit Report Audit Report Tank Waste Feed Delivery System Readiness at the Hanford Site OAS-L-12-09 August 2012 Department of Energy Washington, DC 20585 August 23, 2012 MEMORANDUM FOR THE MANAGER, OFFICE OF RIVER PROTECTION FROM: David Sedillo, Director Western Audits Division Office of Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Tank Waste Feed Delivery System Readiness at the Hanford Site" BACKGROUND The Department of Energy's largest cleanup task involves the treatment, immobilization and disposal of 56 million gallons of hazardous and highly radioactive waste at the Hanford Site, located in Southeastern Washington State. As part of this effort, the Department is constructing

47

Hanford Waste Tank Bump Accident and Consequence Analysis  

Science Conference Proceedings (OSTI)

This report provides a new evaluation of the Hanford tank bump accident analysis and consequences for incorporation into the Authorization Basis. The analysis scope is for the safe storage of waste in its current configuration in single-shell and double-shell tanks.

BRATZEL, D.R.

2000-06-20T23:59:59.000Z

48

DEPARTMENT OF ENERGY Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Site, Richland, Washington; Record of Decision (ROO). This Record of Decision has been prepared pursuant to the Council on Environme~tal Quality ~egulations for Implementing the Procedural Provisions of the National Environmental Pol icy Act (NEPAl (40 CFR Parts 1500-1508) and the Department of Energy NEPA Guidelines (52 FR 47662, December 15, 1987). It is based on DOE's "Environmental Impact Statement for the Oi sposal of Hanford Defense High-Level, Transuranic, and Tank Wastes'' (OOE/EIS-0113) and consideration of ~11 public and agency comments received on the Environmental Impact Statement (EIS). fJECISION The decision is to implement the ''Preferred Alternative'' as discussed in

49

Congressional, State Officials Tour Hanford's Test Site for Safe Tank  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Congressional, State Officials Tour Hanford's Test Site for Safe Congressional, State Officials Tour Hanford's Test Site for Safe Tank Waste Cleanup Congressional, State Officials Tour Hanford's Test Site for Safe Tank Waste Cleanup September 30, 2013 - 12:00pm Addthis Ben Harp, center, manager of Hanford’s Waste Treatment Plant Start-up and Commissioning Integration, discusses the advantages of ORP's Cold Test Facility to a group of congressional and state legislative staffers during a recent tour. Ben Harp, center, manager of Hanford's Waste Treatment Plant Start-up and Commissioning Integration, discusses the advantages of ORP's Cold Test Facility to a group of congressional and state legislative staffers during a recent tour. RICHLAND, Wash. - EM's Office of River Protection (ORP) recently hosted a group of congressional and state legislative staffers on a tour of the

50

OVERVIEW OF HANFORD SINGLE SHELL TANK (SST) STRUCTURAL INTEGRITY - 12123  

SciTech Connect

To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration. Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford SSTs. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford SSTs is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS{reg_sign} The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford SSTs has concluded that the tanks are structurally sound and meet current industry standards. Analyses of the remaining Hanford SSTs are scheduled for FY2013. Hanford SSTs are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than 1/4 inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of the concrete tank domes, looking for cracks and other surface conditions that may indicate signs of structural distress. The condition of the concrete and rebar of the Hanford SSTs is currently being tested and planned for additional activities in the near future. Concrete and rebar removed from the dome of a 65-year-old tank is being tested for mechanics properties and condition. Results indicated stronger than designed concrete with additional Petrographic examination and rebar testing ongoing. Material properties determined from previous efforts combined with current testing and construction document review will help to generate a database that will provide continuing indication of Hanford SST structural integrity.

RAST RS; RINKER MW; WASHENFELDER DJ; JOHNSON JB

2012-01-25T23:59:59.000Z

51

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

(the percentage of actual operating time). 1 Comprehensive Review of the Hanford Waste Treatment Plant Flowsheet and Throughput Specifically, the following questions were...

52

Hanford double shell tank corrosion monitoring instrument tree prototype  

Science Conference Proceedings (OSTI)

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks (DSTs and SSTs). The installation of a prototype corrosion monitoring instrument tree into DST 241-A-101 was completed in December 1995. The instrument tree has the ability to detect and discriminate between uniform corrosion, pitting, and stress corrosion cracking (SCC) through the use of electrochemical noise measurements and a unique stressed element, three-electrode probe. The tree itself is constructed of AISI 304L stainless steel (UNS S30403), with probes in the vapor space, vapor/liquid interface and liquid. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other US Department of Energy (DOE) sites. Keywords: Hanford, radioactive waste, high-level waste tanks, electrochemical noise, probes, double-shell tanks, single-shell tanks, corrosion.

Nelson, J.L.; Edgemon, G.L.; Ohl, P.C.

1995-11-01T23:59:59.000Z

53

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SEISMIC ANALYSIS OF HANFORD DOUBLE SHELL TANKS  

Science Conference Proceedings (OSTI)

M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratories (PNNL) to perform seismic analysis of the Hanford Site Double-Shell Tanks (DSTs) in support of a project entitled Double-Shell Tank (DST) Integrity Project - DST Thermal and Seismic Analyses. The original scope of the project was to complete an up-to-date comprehensive analysis of record of the DST System at Hanford in support of Tri-Party Agreement Milestone M-48-14. The work described herein was performed in support of the seismic analysis of the DSTs. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). Although Milestone M-48-14 has been met, Revision I is being issued to address external review comments with emphasis on changes in the modeling of anchor bolts connecting the concrete dome and the steel primary tank. The work statement provided to M&D (PNNL 2003) required that a nonlinear soil structure interaction (SSI) analysis be performed on the DSTs. The analysis is required to include the effects of sliding interfaces and fluid sloshing (fluid-structure interaction). SSI analysis has traditionally been treated by frequency domain computer codes such as SHAKE (Schnabel, et al. 1972) and SASSI (Lysmer et al. 1999a). Such frequency domain programs are limited to the analysis of linear systems. Because of the contact surfaces, the response of the DSTs to a seismic event is inherently nonlinear and consequently outside the range of applicability of the linear frequency domain programs. That is, the nonlinear response of the DSTs to seismic excitation requires the use of a time domain code. The capabilities and limitations of the commercial time domain codes ANSYS{reg_sign} and MSC Dytran{reg_sign} for performing seismic SSI analysis of the DSTs and the methodology required to perform the detailed seismic analysis of the DSTs has been addressed in Rinker et al (2006a). On the basis of the results reported in Rinker et al. (2006a), it is concluded that time-domain SSI analysis using ANSYS{reg_sign} is justified for predicting the global response of the DSTs. The most significant difference between the current revision (Revision 1) of this report and the original issue (Revision 0) is the treatment of the anchor bolts that tie the steel dome of the primary tank to the concrete tank dome.

MACKEY TC; RINKER MW; CARPENTER BG; HENDRIX C; ABATT FG

2009-01-15T23:59:59.000Z

54

Record of Decision Issued for the Hanford Tank Closure and Waste...  

NLE Websites -- All DOE Office Websites (Extended Search)

Record of Decision Issued for the Hanford Tank Closure and Waste Management EIS Record of Decision Issued for the Hanford Tank Closure and Waste Management EIS December 13, 2013 -...

55

ORNL measurements at Hanford Waste Tank TX-118  

Science Conference Proceedings (OSTI)

A program of measurements and calculations to develop a method of measuring the fissionable material content of the large waste storage tanks at the Hanford, Washington, site is described in this report. These tanks contain radioactive waste from the processing of irradiated fuel elements from the plutonium-producing nuclear reactors at the Hanford site. Time correlation and noise analysis techniques, similar to those developed for and used in the Nuclear Weapons Identification System at the Y-12 Plant in Oak Ridge, Tennessee, will be used at the Hanford site. Both ``passive`` techniques to detect the neutrons emitted spontaneously from the waste in the tank and ``active`` techniques using AmBe and {sup 252}Cf neutron sources to induce fissions will be used. This work is divided into three major tasks: (1) development of high-sensitivity neutron detectors that can selectively count only neutrons in the high {gamma} radiation fields in the tanks, (2) Monte Carlo neutron transport calculations using both the KENO and MCNP codes to plan and analyze the measurements, and (3) the measurement of time-correlated neutrons by time and frequency analysis to distinguish spontaneous fission from sources inside the tanks. This report describes the development of the detector and its testing in radiation fields at the Radiation Calibration Facility at Oak Ridge National Laboratory and in tank TX-118 at the 200 W area at Westinghouse Hanford Company.

Koehler, P.E.; Mihalczo, J.T.

1995-02-01T23:59:59.000Z

56

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Systems Working Session (7) ChangeRelease Summary of meeting between DOE-ORP and Hanford Site regulatorsstakeholders regarding Description: Waste Management Area C...

57

Independent Oversight Review, Hanford Tank Farms - April 2013 | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

April 2013 April 2013 Independent Oversight Review, Hanford Tank Farms - April 2013 April 2013 Review of Management of Safety Systems at the Hanford Tank Farms The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent review of the management of safety class or safety significant structures, systems and components (hereinafter referred to as safety systems) at the Hanford Site Tank Farms. The review was performed by the HSS Office of Safety and Emergency Management Evaluations. The purpose of this Independent Oversight targeted assessment effort is to evaluate processes for monitoring, maintaining, and operating safety systems to ensure their continued reliable capability to perform the

58

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT BUCKLING EVALUATION METHODS & RESULTS FOR THE PRIMARY TANKS  

SciTech Connect

This report documents a detailed buckling evaluation of the primary tanks in the Hanford double shell waste tanks. The analysis is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raise by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review (in April and May 2001) of work being performed on the double-shell tank farms, and the operation of the aging waste facility (AWF) primary tank ventilation system.

MACKEY, T.C.

2006-03-17T23:59:59.000Z

59

Mitigation of the most hazardous tank at the Hanford Site  

DOE Green Energy (OSTI)

Various tanks at the Hanford Site have been declared to be unresolved safety problems. This means that the tank has the potential to be beyond the limits covered by the current safety documentation. Tank 241-SY-101 poses the greatest hazard. The waste stored in this tank has periodically released hydrogen gas which exceeds the lower flammable limits. A mixer pump was installed in this tank to stir the waste. Stirring the waste would allow the hydrogen to be released slowly in a controlled manner and mitigate the hazard associated with this tank. The testing of this mixer pump is reported in this document. The mixer pump has been successful in controlling the hydrogen concentration in the tank dome to below the flammable limit which has mitigated the hazardous gas releases.

Reynolds, D.A.

1994-09-01T23:59:59.000Z

60

Industrial mixing techniques for Hanford double-shell tanks  

Science Conference Proceedings (OSTI)

Jet mixer pumps are currently the baseline technology for sludge mobilization and mixing in one-million gallon double-shell tanks at the Hanford and Savannah River Sites. Improvements to the baseline jet mixer pump technology are sought because jet mixer pumps have moving parts that may fail or require maintenance. Moreover, jet mixers are relatively expensive, they heat the waste, and, in some cases, may not mobilize enough of the sludge. This report documents a thorough literature search for commercially available applicable mixing technologies that could be used for double-shell tank sludge mobilization and mixing. Textbooks, research articles, conference proceedings, mixing experts, and the Thomas Register were consulted to identify applicable technologies. While there are many commercial methods that could be used to mobilize sludge or mix the contents of a one-million gallon tank, few will work given the geometrical constraints (e.g., the mixer must fit through a 1.07-m-diameter riser) or the tank waste properties (e.g., the sludge has such a high yield stress that it generally does not flow under its own weight). Pulsed fluid jets and submersible Flygt mixers have already been identified at Hanford and Savannah River Sites for double-shell tank mixing applications. While these mixing technologies may not be applicable for double-shell tanks that have a thick sludge layer at the bottom (since too many of these mixers would need to be installed to mobilize most of the sludge), they may have applications in tanks that do not have a settled solids layer. Retrieval projects at Hanford and other U.S. Department of Energy sites are currently evaluating the effectiveness of these mixing techniques for tank waste applications. The literature search did not reveal any previously unknown technologies that should be considered for sludge mobilization and mixing in one-million gallon double-shell tanks.

Daymo, E.A.

1997-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Engineering task plan HTI [Hanford Tank Initiative] cone penetrometer  

SciTech Connect

The Hanford Cone Penetrometer Platform (CPP) will be used to insert instrumented and soil sampling probes into the soil adjacent to Tank AX-104 to assist in characterizing the waste plume. The scope, deliverables, roles and responsibilities, safety, and environmental considerations are presented in the task plan.

Krieg, S.A.

1998-03-19T23:59:59.000Z

62

Hanford waste tanks - light at the end of the tunnel  

DOE Green Energy (OSTI)

The U.S. Department of Energy (DOE) faced several problems in its Hanford Site tank farms in the early nineties. It had 177 waste tanks, ranging in size from 55,000 to 1,100,000 gallons, which contained more than 55 million gallons of liquid and solid high-level radioactive waste (HLW) from a variety of processes. Unfortunately, waste transfer records were incomplete. Chemical reactions going on in the tanks were not totally understood. Every tank had high concentrations of powerful oxidizers in the form of nitrates and nitrites, and some tanks had relatively high concentrations of potential fuels that could react explosively with oxidizers. A few of these tanks periodically released large quantities of hydrogen and nitrous oxide, a mixture that was potentially more explosive than hydrogen and air. Both the nitrate/fuel and hydrogen/nitrous oxide reactions had the potential to rupture a tank exposing workers and the general public to unacceptably large quantities of radioactive material. One tank (241-C-106) was generating so much heat that water had to be added regularly to avoid thermal damage to the tank's concrete exterior shell. The tanks contained more than 250 million Curies of radioactivity. Some of that radioactivity was in the form of fissile plutonium, which represented a potential criticality problem. As awareness of the potential hazards grew, the public and various regulatory agencies brought increasing pressure on DOE to quantify the hazards and mitigate any that were found to be outside accepted risk guidelines. In 1990, then Representative, now Senator Ron Wyden (D-Oregon), introduced an amendment to Public Law 101-510, Section 3137, that required DOE to identify Hanford tanks that might have a serious potential for release of high-level waste.

POPPITI, J.A.

1999-09-29T23:59:59.000Z

63

HANFORD WASTE TANK BUMP ACCIDENT & CONSEQUENCE ANALYSIS  

DOE Green Energy (OSTI)

Postulated physical scenarios leading to tank bumps were examined. A combination of a substantial supernatant layer depth, supernatant temperatures close to saturation, and high sludge temperatures are required for a tank bump to occur. Scenarios postulated at various times for sludge layers lacking substantial supernatant, such as superheat within the layer and fumarole formation leading to a bump were ruled out.

MEACHAM, J.E.

2005-02-22T23:59:59.000Z

64

The Hanford site tank waste remediation system technical strategy  

SciTech Connect

The US Department of Energy`s Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of radioactive tank the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m{sup 3} (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have accumulated in 177 tanks. In addition, significant amounts of {sup 90}S and {sup 137}Cs were removed from the tank waste, converted to salts, doubly encapsulated in metal containers, and stored in water basins. A Tank Waste Remediation System Program was established by the US DOE Energy in 1991 to safely manage and immobilize these wastes for permanent disposal of the high-level waste fraction in a geologic repository. The technical strategy to manage and dispose of these wastes has been revised and successfully negotiated with the regulatory agencies.

Wodrich, D.D.

1994-04-01T23:59:59.000Z

65

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington  

Science Conference Proceedings (OSTI)

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Not Available

1994-07-01T23:59:59.000Z

66

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory ofthis waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most ofthe leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

67

CHANGING THE SAFETY CULTURE IN HANFORD TANK FARMS  

SciTech Connect

In 2000 the Hanford Tank Farms had one of the worst safety records in the Department of Energy Complex. By the end of FY08 the safety performance of the workforce had turned completely around, resulting in one of the best safety records in the DOE complex for operations of its kind. This paper describes the variety of programs and changes that were put in place to accomplish such a dramatic turn-around. The U.S. Department of Energy's 586-square-mile Hanford Site in Washington State was established during World War II as part of the Manhattan Project to develop nuclear materials to end the war. For the next several decades it continued to produce plutonium for the nation's defense, leaving behind vast quantities of radioactive and chemical waste. Much of this waste, 53,000,000 gallons, remains stored in 149 aging single-shell tanks and 28 newer double-shell tanks. One of the primary objectives at Hanford is to safely manage this waste until it can be prepared for disposal, but this has not always been easy. These giant underground tanks, many of which date back to the beginning of the Manhattan Project, range in size from 55,000 gallons up to 1.1 million gallons, and are buried beneath 10 feet of soil near the center of the site. Up to 67 of the older single-shell tanks have leaked as much as one million gallons into the surrounding soil. Liquids from the single-shell tanks were removed by 2003 but solids remain in the form of saltcake, sludges and a hardened heel at the bottom of some tanks. The Department of Energy's Office of River Protection was established to safely manage this waste until it could be prepared for disposal. For most of the last seven years the focus has been on safely retrieving waste from the 149 aging single-shell and moving it to the newer double-shell tanks. Removing waste from the tanks is a difficult and complex task. The tanks were made to put waste in, not take it out. Because of the toxic nature of the waste, both chemically as well as radiologically, all retrieval operations must be performed using remote-controlled equipment which has to be installed in each tank, then removed when retrieval is completed. This process involves a variety of potentially hazardous construction activities including crane and rigging, excavation, electrical and piping work. It also requires strong attention to safety to avoid injuries to personnel and contamination of the environment.

BERRIOCHOA MV; ALCALA LJ

2009-01-06T23:59:59.000Z

68

CHANGING THE SAFETY CULTURE IN HANFORD TANK FARMS  

SciTech Connect

In 2000 the Hanford Tank Farms had one of the worst safety records in the Department of Energy Complex. By the end of FY08 the safety performance of the workforce had turned completely around, resulting in one of the best safety records in the DOE complex for operations of its kind. This paper describes the variety of programs and changes that were put in place to accomplish such a dramatic turn-around. The U.S. Department of Energy's 586-square-mile Hanford Site in Washington State was established during World War II as part of the Manhattan Project to develop nuclear materials to end the war. For the next several decades it continued to produce plutonium for the nation's defense, leaving behind vast quantities of radioactive and chemical waste. Much of this waste, 53,000,000 gallons, remains stored in 149 aging single-shell tanks and 28 newer double-shell tanks. One of the primary objectives at Hanford is to safely manage this waste until it can be prepared for disposal, but this has not always been easy. These giant underground tanks, many of which date back to the beginning of the Manhattan Project, range in size from 55,000 gallons up to 1.1 million gallons, and are buried beneath 10 feet of soil near the center of the site. Up to 67 of the older single-shell tanks have leaked as much as one million gallons into the surrounding soil. Liquids from the single-shell tanks were removed by 2003 but solids remain in the form of saltcake, sludges and a hardened heel at the bottom of some tanks. The Department of Energy's Office of River Protection was established to safely manage this waste until it could be prepared for disposal. For most of the last seven years the focus has been on safely retrieving waste from the 149 aging single-shell and moving it to the newer double-shell tanks. Removing waste from the tanks is a difficult and complex task. The tanks were made to put waste in, not take it out. Because of the toxic nature of the waste, both chemically as well as radiologically, all retrieval operations must be performed using remote-controlled equipment which has to be installed in each tank, then removed when retrieval is completed. This process involves a variety of potentially hazardous construction activities including crane and rigging, excavation, electrical and piping work. It also requires strong attention to safety to avoid injuries to personnel and contamination of the environment.

BERRIOCHOA MV; ALCALA LJ

2009-01-06T23:59:59.000Z

69

Tank Waste Retrieval Lessons Learned at the Hanford Site  

SciTech Connect

One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the U. S. Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60 percent of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste to the surrounding soil. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring this waste to the DST system. Retrieval of SST salt-cake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. Regulatory requirements for SST waste retrieval and tank farm closure are established in the Hanford Federal Facility Agreement and Consent Order (HFFACO), better known as the Tri- Party Agreement, or TPA. The HFFACO was signed by the DOE, the State of Washington Department of Ecology (Ecology), and U.S. Environmental Protection Agency (EPA) and requires retrieval of as much waste as technically possible, with waste residues not to exceed 360 ft{sup 3} in 530,000 gallon or larger tanks; 30 ft{sup 3} in 55,000 gallon or smaller tanks; or the limit of waste retrieval technology, whichever is less. If residual waste volume requirements cannot be achieved, then HFFACO Appendix H provisions can be invoked to request Ecology and EPA approval of an exception to the waste retrieval criteria for a specific tank. Tank waste retrieval has been conducted at the Hanford Site over the last few decades using a method referred to as Past Practice Hydraulic Sluicing. Past Practice Hydraulic Sluicing employs large volumes of DST supernatant and water to dislodge, dissolve, mobilize, and retrieve tank waste. Concern over the leak integrity of SSTs resulted in the need for tank waste retrieval methods capable of using smaller volumes of liquid in a more controlled manner. Retrieval of SST waste in accordance with HFFACO requirements was initiated at the Hanford Site in April 2003. New and innovative tank waste retrieval methods that minimize and control the use of liquids are being implemented for the first time. These tank waste retrieval methods replace Past Practice Hydraulic Sluicing and employ modified sluicing, vacuum retrieval, and in-tank vehicle techniques. Waste retrieval has been completed in seven Hanford Site SSTs (C-106, C-103, C-201, C-202, C-203, C-204, and S-112) in accordance with HFFACO requirements. Three additional tanks are currently in the process of being retrieved (C-108, C-109 and S-102) Preparation for retrieval of two additional SSTs (C-104 and C-110) is ongoing with retrieval operations forecasted to start in calendar year 2008. Tank C-106 was retrieved to a residual waste volume of 470 ft{sup 3} using oxalic acid dissolution and modified sluicing. An Appendix H exception request for Tank C-106 is undergoing review. Tank C-103 was retrieved to a residual volume of 351 ft{sup 3} using a modified sluicing technology. This approach was successful at reaching the TPA limits for this tank of less than 360 ft{sup 3}and the limits of the technology. Tanks C-201, C-202, C-203, and C-204 are smaller (55,000 gallon) tanks and waste removal was completed in accordance with HFFACO requirements using a vacuum retrieval system. Residual waste volumes in each of these four tanks were less than 25 ft{sup 3}. Tank S-112 retrieval was completed February 28, 2007, meeting the TPA Limits of less than

Dodd, R.A. [CH2M HILL Hanford Group, Inc., Richland, Washington (United States)

2008-07-01T23:59:59.000Z

70

Washing and caustic leaching of Hanford Tank C-106 sludge  

Science Conference Proceedings (OSTI)

This report describes the results of a laboratory-scale washing and caustic leaching test performed on sludge from Hanford Tank C-106. The purpose of this test was to determine the behavior of important sludge components when subjected to washing with dilute or concentrated sodium hydroxide solutions. The results of this laboratory-scale test were used to support the design of a bench-scale washing and leaching process used to prepare several hundred grams of high-level waste solids for vitrification tests to be done by private contractors. The laboratory-scale test was conducted at Pacific Northwest Laboratory in FY 1996 as part of the Hanford privatization effort. The work was funded by the US Department of Energy through the Tank Waste Remediation System (TWRS; EM-30).

Lumetta, G.J.; Wagner, M.J.; Hoopes, F.V.; Steele, R.T.

1996-10-01T23:59:59.000Z

71

TANK WASTE RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE  

SciTech Connect

One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the US Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60% of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring the waste to the DST system since 1997 as part of the interim stabilization program. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. This paper presents lessons learned from retrieval of tank waste at the Hanford Site and discusses how this information is used to optimize retrieval system efficiency, improve overall cost effectiveness of retrieval operations, and ensure that HFFACO requirements are met.

DODD, R.A.

2006-01-17T23:59:59.000Z

72

Retrieval technology development for Hanford double-shell tanks  

SciTech Connect

This paper describes the combined analytical, computational, and experimental program developed for identifying operating strategies for mobilization and retrieval of radioactive waste stored in double-shell tanks at Hanford. Sludge mobilization, slurry uniformity, and slurry retrieval investigations will produce guidelines for mixer pump and retrieval pump operation based on the physical properties of the waste and the geometric properties of the system (number of operating pumps and pump design and placement).

Bamberger, J.A.; Wise, B.M.; Miller, W.C.

1992-05-01T23:59:59.000Z

73

Hanford tank residual waste contaminant source terms and release models  

Science Conference Proceedings (OSTI)

Residual waste is expected to be left in 177 underground storage tanks after closure at the U.S. Department of Energys Hanford Site in Washington State (USA). In the long term, the residual wastes represent a potential source of contamination to the subsurface environment. Residual materials that cannot be completely removed during the tank closure process are being studied to identify and characterize the solid phases and estimate the release of contaminants from these solids to water that might enter the closed tanks in the future. As of the end of 2009, residual waste from five tanks has been evaluated. Residual wastes from adjacent tanks C-202 and C-203 have high U concentrations of 24 and 59 wt%, respectively, while residual wastes from nearby tanks C-103 and C-106 have low U concentrations of 0.4 and 0.03 wt%, respectively. Aluminum concentrations are high (8.2 to 29.1 wt%) in some tanks (C-103, C-106, and S-112) and relatively low (Technetium leachability is not as strongly dependent on the concentration of Tc in the waste, and it appears to be slightly more leachable by the Ca(OH)2-saturated solution than by the CaCO3-saturated solution. In general, Tc is much less leachable (<10 wt% of the available mass in the waste) than previously predicted. This may be due to the coprecipitation of trace concentrations of Tc in relatively insoluble phases such as Fe oxide/hydroxide solids.

Deutsch, William J.; Cantrell, Kirk J.; Krupka, Kenneth M.; Lindberg, Michael J.; Serne, R. Jeffrey

2011-08-23T23:59:59.000Z

74

Approach for tank safety characterization of Hanford site waste  

Science Conference Proceedings (OSTI)

The overall approach and associated technical basis for characterizing Hanford Site waste to help identify and resolve Waste Tank Safety Program safety issues has been summarized. The safety issues include flammable gas, noxious vapors, organic solvents, condensed-phase exothermic reactions (ferrocyanide and organic complexants), criticality, high heat, and safety screening. For the safety issues involving chemical reactions (i.e., flammable gas, organic solvents, ferrocyanide, and organic complexants), the approach to safety characterization is based on the fact that rapid exothermic reactions cannot occur if either fuel, oxidizer, or temperature (initiators) is not sufficient or controlled. The approach to characterization has been influenced by the progress made since mid-1993: (1) completion of safety analyses on ferrocyanide, criticality, organic solvent in tank 241-C-103, and sludge dryout. (2) successful mitigation of tank 241-SY-101; (3) demonstration of waste aging in laboratory experiments and from waste sampling, and (4) increased understanding of the information that can be obtained from headspace sampling. Headspace vapor sampling is being used to confirm that flammable gas does not accumulate in the single-shell tanks, and to determine whether organic solvents are present. The headspaces of tanks that may contain significant quantities of flammable gas will be monitored continuously using standard hydrogen monitors. For the noxious vapors safety issue, characterization will consist of headspace vapor sampling of most of the Hanford Site waste tanks. Sampling specifically for criticality is not required to confirm interim safe storage; however, analyses for fissile material will be conducted as waste samples are obtained for other reasons. High-heat tanks will be identified through temperature monitoring coupled with thermal analyses.

Meacham, J.E.; Babad, H.; Cash, R.J.; Dukelow, G.T.; Eberlein, S.J.; Hamilton, D.W.; Johnson, G.D.; Osborne, J.W.; Payne, M.A.; Sherwood, D.J. [and others

1995-03-01T23:59:59.000Z

75

Hanford Tank Farm interim storage phase probabilistic risk assessment outline  

Science Conference Proceedings (OSTI)

This report is the second in a series examining the risks for the high level waste (HLW) storage facilities at the Hanford Site. The first phase of the HTF PSA effort addressed risks from Tank 101-SY, only. Tank 101-SY was selected as the initial focus of the PSA because of its propensity to periodically release (burp) a mixture of flammable and toxic gases. This report expands the evaluation of Tank 101-SY to all 177 storage tanks. The 177 tanks are arranged into 18 farms and contain the HLW accumulated over 50 years of weapons material production work. A centerpiece of the remediation activity is the effort toward developing a permanent method for disposing of the HLW tank`s highly radioactive contents. One approach to risk based prioritization is to perform a PSA for the whole HLW tank farm complex to identify the highest risk tanks so that remediation planners and managers will have a more rational basis for allocating limited funds to the more critical areas. Section 3 presents the qualitative identification of generic initiators that could threaten to produce releases from one or more tanks. In section 4 a detailed accident sequence model is developed for each initiating event group. Section 5 defines the release categories to which the scenarios are assigned in the accident sequence model and presents analyses of the airborne and liquid source terms resulting from different release scenarios. The conditional consequences measured by worker or public exposure to radionuclides or hazardous chemicals and economic costs of cleanup and repair are analyzed in section 6. The results from all the previous sections are integrated to produce unconditional risk curves in frequency of exceedance format.

Not Available

1994-05-19T23:59:59.000Z

76

Retrieval of the Tenth Single-Shell Tank Complete at Hanford: Third  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Retrieval of the Tenth Single-Shell Tank Complete at Hanford: Third Retrieval of the Tenth Single-Shell Tank Complete at Hanford: Third Single-Shell Tank Emptied at Hanford's C Farm This Year Retrieval of the Tenth Single-Shell Tank Complete at Hanford: Third Single-Shell Tank Emptied at Hanford's C Farm This Year September 17, 2012 - 12:00pm Addthis Media Contacts Lori Gamache, ORP 509-372-9130 Rob Roxburgh, WRPS 509-376-5188 RICHLAND - Washington River Protection Solutions (WRPS) has advised the U.S. Department of Energy (DOE) that they have completed retrieval of radioactive and chemical waste from the third single-shell tank (SST) this year. WRPS is the tank operations contractor for the DOE Office of River Protection (ORP). An engineering evaluation in the field shows the waste volume in C-109 is below the regulatory requirement of 360 cubic feet of waste remaining in

77

Retrieval of the Tenth Single-Shell Tank Complete at Hanford: Third  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the Tenth Single-Shell Tank Complete at Hanford: Third the Tenth Single-Shell Tank Complete at Hanford: Third Single-Shell Tank Emptied at Hanford's C Farm This Year Retrieval of the Tenth Single-Shell Tank Complete at Hanford: Third Single-Shell Tank Emptied at Hanford's C Farm This Year September 17, 2012 - 12:00pm Addthis Media Contacts Lori Gamache, ORP 509-372-9130 Rob Roxburgh, WRPS 509-376-5188 RICHLAND - Washington River Protection Solutions (WRPS) has advised the U.S. Department of Energy (DOE) that they have completed retrieval of radioactive and chemical waste from the third single-shell tank (SST) this year. WRPS is the tank operations contractor for the DOE Office of River Protection (ORP). An engineering evaluation in the field shows the waste volume in C-109 is below the regulatory requirement of 360 cubic feet of waste remaining in

78

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4941 (2) Revision Number: 0 (3) Effective Date: 02/25/2010 4941 (2) Revision Number: 0 (3) Effective Date: 02/25/2010 (4) Document Type: ElDigital Image [] Hard copy (a) Number of pages (including the DIRF) or 20 SPDF Video number of digital images (5) Release Type New El Cancel I E Page Change El Complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Working Session on Soils Inventory (7) Change/Release Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on soil inventory. (8) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, N/NA and Component N/NA (SSC) and Building (b) System Designator: (d) Equipment ID Number (EIN): Number: N/A N/A (10) Impacted (a) Document Type (b) Document Number (c) Document Revision

79

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOCUMENT RELEASE FORM DOCUMENT RELEASE FORM ! I (1) Document Number: RPP-47375 . NUMber· 0 I (3) Effective Date: 08/11/2010 i (4) Document Type: o Digital Image o Hard copy (a) Number of pages (including the DRF) or 21 I ~PDF o Video I number of digital images (5) Release Type ~ New o Cancel o Page Change o Complete Revision i (6) Document Title: Meeting Minutes for the WMA C PA Engineered Systems #2 Working Session - Steel Corrosion; i ConcretelGrout Degradation I(7) Change/Release ..- - . Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on Engineered Systems #2 - Steel Corrosion; Concrete/Grout Degradation I(8) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number:

80

Hanford Site C Tank Farm Meeting Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

51 35 51 35 (2) Revision Number: 0 (3) Effective Date: 03/03/2010 (4) Document Typo: [I Digital Image ElHard copy (a) Number of pages (including the DRF) or 18 JE PDF Vie number of digital Images (5) Release Type Z New 1: Cancel 1E: Page Change Complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Engineering System #1 Working Session (7) ChangelReleese Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on Engineering System #1. (5) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, and Component N/NA (SSC) and Building (b) System Designator: (d) Equipment ID Number (EIN):. Number: (10) Impacted (a) Document Type (b) Document Number (c) Document Revision

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Advances in Geochemical Testing of Key Contaminants in Residual Hanford Tank Waste  

Science Conference Proceedings (OSTI)

This report describes the advances that have been made over the past two years in testing and characterizing waste material in Hanford tanks.

Deutsch, William J.; Krupka, Kenneth M.; Cantrell, Kirk J.; Brown, Christopher F.; Lindberg, Michael J.; Schaef, Herbert T.; Heald, Steve M.; Arey, Bruce W.; Kukkadapu, Ravi K.

2005-11-04T23:59:59.000Z

82

Low temperature hydrothermal destruction of organics in Hanford tank wastes  

SciTech Connect

The objective of this work is to evaluate and develop a low temperature hydrothermal process (HTP) for the destruction of organics that are present wastes temporarily stored in underground tanks at the Hanford Site. Organic compounds contribute to tank waste safety issues, such as hydrogen generation. Some organic compounds act as complexants, promoting the solubility of radioactive constituents such as {sup 90}Sr and {sup 241}Am, which is undesirable for waste pretreatment processing. HTP is thermal-chemical autogenous processing method that is typically operated between 250{degrees}C and 375{degrees}C and approximately 200 atm. Testing with simulated tank waste, containing a variety of organics has been performed. The distribution of strontium, cesium and bulk metals between the supernatant and solid phases as a function of the total organic content of the waste simulant will be presented. Test results using simulant will be compared with similar tests conducted using actual radioactive waste.

Orth, R.J.; Elmore, M.R.; Zacher, A.H.; Neuenschwander, G.G.; Schmidt, A.J.; Jones, E.O.; Hart, T.R.; Poshusta, J.C.

1994-08-01T23:59:59.000Z

83

Hanford Tank Farms Waste Certification Flow Loop Test Plan  

Science Conference Proceedings (OSTI)

A future requirement of Hanford Tank Farm operations will involve transfer of wastes from double shell tanks to the Waste Treatment Plant. As the U.S. Department of Energy contractor for Tank Farm Operations, Washington River Protection Solutions anticipates the need to certify that waste transfers comply with contractual requirements. This test plan describes the approach for evaluating several instruments that have potential to detect the onset of flow stratification and critical suspension velocity. The testing will be conducted in an existing pipe loop in Pacific Northwest National Laboratorys facility that is being modified to accommodate the testing of instruments over a range of simulated waste properties and flow conditions. The testing phases, test matrix and types of simulants needed and the range of testing conditions required to evaluate the instruments are described

Bamberger, Judith A.; Meyer, Perry A.; Scott, Paul A.; Adkins, Harold E.; Wells, Beric E.; Blanchard, Jeremy; Denslow, Kayte M.; Greenwood, Margaret S.; Morgen, Gerald P.; Burns, Carolyn A.; Bontha, Jagannadha R.

2010-01-01T23:59:59.000Z

84

Forms of Al in Hanford Tank Waste  

NLE Websites -- All DOE Office Websites (Extended Search)

Actual Waste Testing Actual Waste Testing Lanée Snow Sandra Fiskum Rick Shimskey Reid Peterson 4/9/09 2 Tested > 75% of sludge waste types Sludge Sources Bi-Phosphate waste Redox Purex Cladding TBP FeCN sludge Redox Cladding Zirc Cladding Purex waste Misc NA 4/9/09 3 Tested > 75% of saltcake waste types Saltcake fractions Bi-phosphate saltcake S A B R NA Tested 8 groups of tank waste types Group ID Type Al Cr PO 4 3- Oxalate Sulfate Fluoride 1 Bi Phosphate sludge 3% 3% 21% 2% 6% 12% 2 Bi Phosphate saltcake (BY, T) 18% 25% 36% 36% 43% 36% 3 PUREX Cladding Waste sludge 12% 1% 3% 1% 1% 3% 4 REDOX Cladding Waste sludge 8% 1% 0% 0% 0% 2% 5 REDOX sludge 26% 8% 1% 3% 1% 2% 6 S - Saltcake (S) 11% 38% 12% 24% 14% 3% 7 TBP Waste sludge 1% 1% 8% 0% 2% 1% 8 FeCN sludge 2% 1% 4% 1% 1% 1% *Percentages reflect % of total inventory of species in the tank farm. *Discussion will focus on those that make up the largest fraction of the Al

85

Worker Protection from Chemical Vapors: Hanford Tank Farms  

Science Conference Proceedings (OSTI)

Chemical vapor emissions from underground hazardous waste storage tanks on the Hanford site in eastern Washington State are a potential concern because workers enter the tank farms on a regular basis for waste retrievals, equipment maintenance, and surveillance. Tank farm contractors are in the process of retrieving all remaining waste from aging single-shell tanks, some of which date to World War II, and transferring it to newer double-shell tanks. During the waste retrieval process, tank farm workers are potentially exposed to fugitive chemical vapors that can escape from tank head-spaces and other emission points. The tanks are known to hold more than 1,500 different species of chemicals, in addition to radionuclides. Exposure assessments have fully characterized the hazards from chemical vapors in half of the tank farms. Extensive sampling and analysis has been done to characterize the chemical properties of hazardous waste and to evaluate potential health hazards of vapors at the ground surface, where workers perform maintenance and waste transfer activities. Worker concerns, risk communication, and exposure assessment are discussed, including evaluation of the potential hazards of complex mixtures of chemical vapors. Concentrations of vapors above occupational exposure limits (OEL) were detected only at exhaust stacks and passive breather filter outlets. Beyond five feet from the sources, vapors disperse rapidly. No vapors have been measured above 50% of their OELs more than five feet from the source. Vapor controls are focused on limited hazard zones around sources. Further evaluations of vapors include analysis of routes of exposure and thorough analysis of nuisance odors. (authors)

Anderson, T.J. [CH2M HILL Hanford Group, Inc. / Environmental Health, Richland, WA (United States)

2007-07-01T23:59:59.000Z

86

Thermodynamic Modeling of Hanford Waste Tank 241-AN-107  

Science Conference Proceedings (OSTI)

The high level waste storage double-shell tanks at the Hanford site are highly basic. The high basicity is a key factor in controlling the chemical behavior of different components of the waste and in influencing the corrosion rate of the carbon steel primary tanks. However, the introduction of atmospheric CO2 can act to reduce the pH of the tank wastes over time and possibly alter the corrosion rate of the carbon steel tanks. In order to at least partially address this issue for waste tank 241-AN-107, thermodynamic modeling calculations were performed to predict the changes in pH and carbonate concentration that could occur as CO2 is absorbed from the atmosphere. The calculations extended to complete equilibrium with the partial pressure of CO2 in the atmosphere (i.e. pCO2 = 10-3.5 atm). Simulations were performed for both the upper segments of tank 241-AN-107, which have been influenced by the introduction of high concentrations of NaOH to the supernatant, and for the lower segments where the salt cake/interstitial liquid have not been substantially altered by the introduction of base concentration.

Felmy, Andrew R.

2005-09-07T23:59:59.000Z

87

Development of Occupational Exposure Limits for the Hanford Tank Farms  

SciTech Connect

Production of plutonium for the United States nuclear weapons program from the 1940s to the 1980s generated 53 million gallons of radioactive chemical waste, which is storedin 177 underground tanks at the Hanford Site in southeastern W 18 ashington State. Recent 19 attempts to begin the retrieval and treatment of these wastes require moving the waste to 20 more modern tanks results in potential exposure of the workers to unfamiliar odors 21 emanating from headspace in the tanks. Given the unknown risks involved, workers 22 were placed on supplied air respiratory protection. CH2M HILL, the managers of the 23 Hanford Site Tank Farms, asked an Independent Toxicology Panel (ITP) to assist them in issues relating to an Industrial Hygiene and risk assessment problem. The ITP was called upon to help determine the risk of exposure to vapors from the tanks, and in general develop a strategy for solution of the problem. This paper presents the methods used to determine the chemicals of potential concern (COPC) and the resultant development of screening values and Acceptable Occupational Exposure Limits (AOELs) for these COPCs. A total of 1,826 chemicals were inventoried and evaluated. Over 1,500 chemicals were identified in the waste tanks headspaces and more than 600 of these were assigned screening values; 72 of these compounds were recommended for AOEL development. Included in this list of 72 were 57 COPCs identified by the ITP and of these 47 were subsequently assigned AOELs. An exhaustive exposure assessment strategy was developed by the CH2M HILL industrial hygiene department to evaluate these COPCs.

Still, Kenneth; Gardner, Donald; Snyder, Robert; Anderson, Thomas; Honeyman, James; Timchalk, Charles

2010-04-01T23:59:59.000Z

88

DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Announces Preference for Disposal of Hanford Transuranic Tank Announces Preference for Disposal of Hanford Transuranic Tank Waste at WIPP DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at WIPP March 6, 2013 - 12:00pm Addthis WASHINGTON, D.C. - Today the U.S. Department of Energy (DOE) announced its preferred alternative to retrieve, treat, package, characterize and certify certain Hanford tank waste for disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, if such waste is properly classified in the future as defense-related mixed transuranic tank waste (mixed TRU waste). This preferred alternative, which may cover up to approximately 3.1 million gallons of tank waste contained in up to 20 tanks, will provide DOE with an option to deal with recent information about possible tank leaks and to

89

Retrieval of Hanford Single Shell Nuclear Waste Tanks using Technologies Foreign and Domestic  

SciTech Connect

The Hanford Site is accelerating its SST retrieval mission. One aspect of this acceleration is the identification of new baseline retrieval technologies that can be applied to all tank conditions for salt & sludge wastes in both sound & leaking tanks.

EACKER, J.A.; GIBBONS, P.W.

2003-01-01T23:59:59.000Z

90

Process chemistry for the pretreatment of Hanford tank wastes  

SciTech Connect

Current guidelines for disposing radioactive wastes stored in underground tanks at the US Department of Energy`s Hanford Site call for the vitrification of high-level waste in borosilicate glass and disposal of the glass canisters in a deep geologic repository. Low-level waste is to be cast in grout and disposed of on site in shallow burial vaults. Because of the high cost of vitrification and geologic disposal, methods are currently being developed to minimize the volume of high-level waste requiring disposal. Two approaches are being considered for pretreating radioactive tank sludges: (1) leaching of selected components from the sludge and (2) acid dissolution of the sludge followed by separation of key radionuclides. The leaching approach offers the advantage of simplicity, but the acid dissolution/radionuclide extraction approach has the potential to produce the least number of glass canisters. Four critical components (Cr, P, S, and Al) were leached from an actual Hanford tank waste-Plutonium Finishing Plant sludge. The Al, P, and S were removed from the sludge by digestion of the sludge with 0.1 M NaOH at 100{degrees}C. The Cr was leached by treating the sludge with alkaline KMnO{sub 4} at 100{degrees}C. Removing these four components from the sludge will dramatically lower the number of glass canisters required to dispose of this waste. The transuranic extraction (TRUEX) solvent extraction process has been demonstrated at a bench scale using an actual Hanford tank waste. The process, which involves extraction of the transuranic elements with octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO), separated 99.9% of the transuranic elements from the bulk components of the waste. Several problems associated with the TRUEX processing of this waste have been addressed and solved.

Lumetta, G.J.; Swanson, J.L. [Pacific Northwest Lab., Richland, WA (United States); Barker, S.A. [Westinghouse Hanford Co., Richland, WA (United States)

1992-08-01T23:59:59.000Z

91

Meeting Summaries for Development of the Hanford Site C Tank Farm  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Meeting Summaries for Development of the Hanford Site C Tank Farm Meeting Summaries for Development of the Hanford Site C Tank Farm Performance Assessment Meeting Summaries for Development of the Hanford Site C Tank Farm Performance Assessment The Meeting Summaries for Development of the Hanford Site C Tank Farm Performance Assessment cover informal discussions between representatives of the U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), the U.S. Nuclear Regulatory Commission (NRC), and the Washington State Department of Ecology (Ecology) and involvement with Tribal Nations, State of Oregon, and the Hanford Advisory Board to support DOE's preparation of a new performance assessment (PA) for the Hanford Site C Tank Farm (CTF). These discussions will include the underlying assumptions, input parameters, and modeling approaches to be taken in

92

Removing Phosphate from Hanford High-Phosphate Tank Wastes: FY 2010 Results  

SciTech Connect

The U.S. Department of Energy (DOE) is responsible for environmental remediation at the Hanford Site in Washington State, a former nuclear weapons production site. Retrieving, processing, immobilizing, and disposing of the 2.2 105 m3 of radioactive wastes stored in the Hanford underground storage tanks dominates the overall environmental remediation effort at Hanford. The cornerstone of the tank waste remediation effort is the Hanford Tank Waste Treatment and Immobilization Plant (WTP). As currently designed, the capability of the WTP to treat and immobilize the Hanford tank wastes in the expected lifetime of the plant is questionable. For this reason, DOE has been pursuing supplemental treatment options for selected wastes. If implemented, these supplemental treatments will route certain waste components to processing and disposition pathways outside of WTP and thus will accelerate the overall Hanford tank waste remediation mission.

Lumetta, Gregg J.; Braley, Jenifer C.; Edwards, Matthew K.; Qafoku, Odeta; Felmy, Andrew R.; Carter, Jennifer C.; MacFarlan, Paul J.

2010-09-22T23:59:59.000Z

93

High Level Waste Feed Certification in Hanford Double Shell Tanks  

SciTech Connect

The ability to effectively mix, sample, certify, and deliver consistent batches of High Level Waste (HLW) feed from the Hanford Double Shell Tanks (DST) to the Waste Treatment and Immobilization Plant (WTP) presents a significant mission risk with potential to impact mission length and the quantity of HLW glass produced. DOEs River Protection Project (RPP) mission modeling and WTP facility modeling assume that individual 3785 cubic meter (1 million gallon) HLW feed tanks are homogenously mixed, representatively sampled, and consistently delivered to the WTP. It has been demonstrated that homogenous mixing of HLW sludge in Hanford DSTs is not likely achievable with the baseline design thereby causing representative sampling and consistent feed delivery to be more difficult. Inconsistent feed to the WTP could cause additional batch to batch operational adjustments that reduces operating efficiency and has the potential to increase the overall mission length. The Hanford mixing and sampling demonstration program will identify DST mixing performance capability, will evaluate representative sampling techniques, and will estimate feed batch consistency. An evaluation of demonstration program results will identify potential mission improvement considerations that will help ensure successful mission completion. This paper will discuss the history, progress, and future activities that will define and mitigate the mission risk.

Thien, Micheal G.; Wells, Beric E.; Adamson, Duane J.

2010-03-01T23:59:59.000Z

94

Hanford double shell tank corrosion monitoring instrument trees  

Science Conference Proceedings (OSTI)

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks - (DSTs and SSTS). Westinghouse Hanford Company is considering installation of a prototype corrosion monitoring instrument tree in at least one DST in the summer of 1995. The instrument tree will have the ability to detect and discriminate between uniform corrosion, stress corrosion cracking (SCC), and pitting. Additional instrument trees will follow in later years. Proof-of-technology testing is currently underway for the use of commercially available electric field pattern (EFP) analysis and electrochemical noise (EN) corrosion monitoring equipment. Creative use and combinations of other existing technologies is also being considered. Successful demonstration of these technologies will be followed by the development of a Hanford specific instrument tree. The first instrument tree will incorporate one of these technologies. Subsequent trees may include both technologies, as well as a more standard assembly of corrosion coupons. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other U.S. Department of Energy (DOE) sites.

Nelson, J.L.

1995-03-01T23:59:59.000Z

95

Vadose zone characterization project at the Hanford Tank Farms: U Tank Farm Report  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy Grand Junction Office (DOE-GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the gamma-ray-emitting radionuclides that are distributed in the vadose zone sediments beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources when possible, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information regarding vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. This information is presently limited to detection of gamma-emitting radionuclides from both natural and man-made sources. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank in a tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the U Tank Farm. Logging operations used high-purity germanium detection systems to acquire laboratory-quality assays of the gamma-emitting radionuclides in the sediments around and below the tanks. These assays were acquired in 59 boreholes that surround the U Tank Farm tanks. Logging of all boreholes was completed in December 1995, and the last Tank Summary Data Report for the U Tank Farm was issued in September 1996.

NONE

1997-05-01T23:59:59.000Z

96

Hanford immobilized low-activity tank waste performance assessment  

Science Conference Proceedings (OSTI)

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis to set requirements on the waste form and the facility design that will protect the long-term public health and safety and protect the environment.

Mann, F.M.

1998-03-26T23:59:59.000Z

97

SLUDGE RETRIEVAL FROM HANFORD K WEST BASIN SETTLER TANKS  

SciTech Connect

In 2010, an innovative, remotely operated retrieval system was deployed to successfully retrieve over 99.7% of the radioactive sludge from ten submerged tanks in Hanford's K-West Basin. As part of K-West Basin cleanup, the accumulated sludge needed to be removed from the 0.5 meter diameter by 5 meter long settler tanks and transferred approximately 45 meters to an underwater container for sampling and waste treatment. The abrasive, dense, non-homogeneous sludge was the product of the washing process of corroded nuclear fuel. It consists of small (less than 600 micron) particles of uranium metal, uranium oxide, and various other constituents, potentially agglomerated or cohesive after 10 years of storage. The Settler Tank Retrieval System (STRS) was developed to access, mobilize and pump out the sludge from each tank using a standardized process of retrieval head insertion, periodic high pressure water spray, retraction, and continuous pumping of the sludge. Blind operations were guided by monitoring flow rate, radiation levels in the sludge stream, and solids concentration. The technology developed and employed in the STRS can potentially be adapted to similar problematic waste tanks or pipes that must be remotely accessed to achieve mobilization and retrieval of the sludge within.

ERPENBECK EG; LESHIKAR GA

2011-01-13T23:59:59.000Z

98

Hanford Single-Shell Tank Leak Causes and Locations - 241-B Farm  

SciTech Connect

This document identifies 241-B Tank Farm (B Farm) leak cause and locations for the 100 series leaking tank (241-B-107) identified in RPP-RPT-49089, Hanford B-Farm Leak Inventory Assessments Report. This document satisfies the B Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L. [Washington River Protection Systems, Richland, WA (United States); Harlow, Donald G. [Washington River Protection Systems, Richland, WA (United States)

2013-07-11T23:59:59.000Z

99

The Remotely Operated Nondestructive Examination System for Examining the Knuckle Region of Hanfords Double Shell Waste Tanks  

Science Conference Proceedings (OSTI)

The Pacific Northwest National Laboratory has developed a technology to address the examination requirements associated with the knuckle region of Hanfords double shell waste tanks. This examination poses a significant technical challenge because the area that requires examination is in a confined space

S. L. Crawford; A. F. Pardini

2005-01-01T23:59:59.000Z

100

Expert Panel Recommendations for Hanford Double-Shell Tank Life Extension  

Science Conference Proceedings (OSTI)

Expert workshops were held in Richland in May 2001 to review the Hanford Double-Shell Tank Integrity Project and make recommendations to extend the life of Hanford's double-shell waste tanks. The workshop scope was limited to corrosion of the primary tank liner, and the main areas for review were waste chemistry control, tank inspection, and corrosion monitoring. Participants were corrosion experts from Hanford, Savannah River Site, Brookhaven National Laboratory, Pacific Northwest National Laboratory, and several consultants. This report describes the current state of the three areas of the program, the final recommendations of the workshop, and the rationale for their selection.

Stewart, Charles W.; Bush, Spencer H.; Berman, Herbert S.; Czajkowski, Carl J.; Divine, James R.; Posakony, Gerald J.; Johnson, A. B.; Elmore, Monte R.; Reynolds, D. A.; Anantatmula, Ramamohan P.; Sindelar, Robert L.; Zapp, Philip E.

2001-06-29T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Hanford Site Tank Waste Remediation System. Waste management 1993 symposium papers and viewgraphs  

Science Conference Proceedings (OSTI)

The US Department of Energy`s (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives.

Not Available

1993-05-01T23:59:59.000Z

102

Vadose zone characterization project at the Hanford Tank Farms: BY Tank Farm report  

SciTech Connect

The US Department of Energy Grand Junction Office (GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the contamination distributed in the vadoze zone sediment beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information about the vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the BY Tank Farm.

Kos, S.E.

1997-02-01T23:59:59.000Z

103

Historical Tank Content Estimate for the Northwest Quandrant of the Hanford 200 East Area  

Science Conference Proceedings (OSTI)

Historical Tank Content Estimate of the Northeast Quadrant provides historical evaluations on a tank by tank basis of the radioactive mixed wastes stored in the underground single-shell tanks of the Hanford 200 East area. This report summaries historical information such at waste history, temperature, tank integrity, inventory estimates and tank level history on a tank by tank basis. Tank Farm aerial photos and in-tank photos of each tank are provided. A brief description of instrumentation methods used for waste tank surveillance, along with the components of the data management effort, such as waste status and Transaction Record Summary, Tank Layering Model, Defined Waste Types, and Inventory Estimates to generate these tank content estimates are also given in this report.

Brevick, C.H.; Gaddis, L.A.; Pickett, W.W.

1994-06-01T23:59:59.000Z

104

Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes  

SciTech Connect

Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and {sup 90}Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste.

Lumetta, G.J.; Wagner, M.J.; Colton, N.G.; Jones, E.O.

1993-06-01T23:59:59.000Z

105

Safety criteria for organic watch list tanks at the Hanford Site  

SciTech Connect

This document reviews the hazards associated with the storage of organic complexant salts in Hanford Site high-level waste single- shell tanks. The results of this analysis were used to categorize tank wastes as safe, unconditionally safe, or unsafe. Sufficient data were available to categorize 67 tanks; 63 tanks were categorized as safe, and four tanks were categorized as conditionally safe. No tanks were categorized as unsafe. The remaining 82 SSTs lack sufficient data to be categorized.Historic tank data and an analysis of variance model were used to prioritize the remaining tanks for characterization.

Meacham, J.E., Westinghouse Hanford

1996-08-01T23:59:59.000Z

106

Hanford Tank Farms Vadose Zone, Addendum to the TX Tank Farm Report  

Science Conference Proceedings (OSTI)

This addendum to the TX Tank Farm Report (GJO-97-13-TAR, GJO-HAN-11) published in September 1997 incorporates the results of high-rate and repeat logging activities along with shape factor analysis of the logging data. A high-rate logging system was developed and deployed in the TX Tank Farm to measure cesium-137 concentration levels in high gamma flux zones where the spectral gamma logging system was unable to collect usable data because of high dead times and detector saturation. This report presents additional data and revised visualizations of subsurface contaminant distribution in the TX Tank Farm at the DOE Hanford Site in the state of Washington.

Spatz, R.

2000-08-01T23:59:59.000Z

107

Estimating retained gas volumes in the Hanford tanks using waste level measurements  

SciTech Connect

The Hanford site is home to 177 large, underground nuclear waste storage tanks. Safety and environmental concerns surround these tanks and their contents. One such concern is the propensity for the waste in these tanks to generate and trap flammable gases. This report focuses on understanding and improving the quality of retained gas volume estimates derived from tank waste level measurements. While direct measurements of gas volume are available for a small number of the Hanford tanks, the increasingly wide availability of tank waste level measurements provides an opportunity for less expensive (than direct gas volume measurement) assessment of gas hazard for the Hanford tanks. Retained gas in the tank waste is inferred from level measurements -- either long-term increase in the tank waste level, or fluctuations in tank waste level with atmospheric pressure changes. This report concentrates on the latter phenomena. As atmospheric pressure increases, the pressure on the gas in the tank waste increases, resulting in a level decrease (as long as the tank waste is {open_quotes}soft{close_quotes} enough). Tanks with waste levels exhibiting fluctuations inversely correlated with atmospheric pressure fluctuations were catalogued in an earlier study. Additionally, models incorporating ideal-gas law behavior and waste material properties have been proposed. These models explicitly relate the retained gas volume in the tank with the magnitude of the waste level fluctuations, dL/dP. This report describes how these models compare with the tank waste level measurements.

Whitney, P.D.; Chen, G.; Gauglitz, P.A.; Meyer, P.A.; Miller, N.E.

1997-09-01T23:59:59.000Z

108

Agreement on New Commitments for Hanford Tank Waste Cleanup Sent to Federal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Agreement on New Commitments for Hanford Tank Waste Cleanup Sent to Agreement on New Commitments for Hanford Tank Waste Cleanup Sent to Federal Judge Agreement on New Commitments for Hanford Tank Waste Cleanup Sent to Federal Judge October 6, 2010 - 12:00am Addthis RICHLAND, Wash. - The U.S. Department of Energy and Washington State Department of Ecology (Ecology) jointly filed a motion today in U.S. District Court asking the court to approve and enter a judicial consent decree that imposes a new, enforceable, and achievable schedule for cleaning up waste from Hanford's underground tanks. The settlement also includes new milestones in the Tri-Party Agreement (TPA), an administrative order between DOE, Ecology, and the U.S. Environmental Protection Agency, which governs cleanup at DOE's Hanford Site. "Today's agreement represents an important milestone in the ongoing cleanup

109

Structural integrity and potential failure modes of hanford high-level waste tanks  

Science Conference Proceedings (OSTI)

Structural Integrity of the Hanford High-Level Waste Tanks were evaluated based on the existing Design and Analysis Documents. All tank structures were found adequate for the normal operating and seismic loads. Potential failure modes of the tanks were assessed by engineering interpretation and extrapolation of the existing engineering documents.

Han, F.C.

1996-09-30T23:59:59.000Z

110

Engineering Task Plan for the Ultrasonic Inspection of Hanford Double Shell Tanks (DST) FY2000  

SciTech Connect

This document facilitates the ultrasonic examination of Hanford double-shell tanks. Included are a plan for engineering activities (individual responsibilities), plan for performance demonstration testing, and a plan for field activities (tank inspection). Also included are a Statement of Work for contractor performance of the work and a protocol to be followed should tank flaws that exceed the acceptance criteria be discovered.

JENSEN, C.E.

2000-01-10T23:59:59.000Z

111

Steady State Flammable Gas Release Rate Calculation and Lower Flammability Level Evaluation for Hanford Tank Waste  

DOE Green Energy (OSTI)

This work is to assess the steady-state flammability level at normal and off-normal ventilation conditions in the tank dome space for 177 double-shell and single-shell tanks at Hanford. Hydrogen generation rate was calculated for 177 tanks using rate equation model developed recently.

HU, T.A.

2000-04-27T23:59:59.000Z

112

Workers Complete Retrieval of 11th Single-Shell Tank at EM's Hanford Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Workers Complete Retrieval of 11th Single-Shell Tank at EM's Workers Complete Retrieval of 11th Single-Shell Tank at EM's Hanford Site Workers Complete Retrieval of 11th Single-Shell Tank at EM's Hanford Site November 26, 2013 - 12:00pm Addthis A composite image comprised of dozens of photos taken inside C-110 provides a rare panoramic view of the tank interior. Portions of the tank floor and the FoldTrack waste-retrieval system are clearly visible. A composite image comprised of dozens of photos taken inside C-110 provides a rare panoramic view of the tank interior. Portions of the tank floor and the FoldTrack waste-retrieval system are clearly visible. Operators use multiple technologies to remove waste from underground storage tank RICHLAND, Wash. - EM's Office of River Protection and its tank farm contractor, Washington River Protection Solutions (WRPS), recently

113

Independent Oversight Review of Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades, November 2011  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Tank Farms Safety Basis Amendment for Double-Shell Tank Ventilation System Upgrades November 2011 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope and Approach .............................................................................................................................. 2

114

Hanford Single-Shell Tank Leak Causes and Locations - 241-BY and 241-TY Farm  

SciTech Connect

This document identifies 241-BY Tank Farm (BY Farm) and 241-TY Tank Farm (TY Farm) leak causes and locations for the 100 series leaking tanks (241-BY-103, 241-TY-103, 241-TY-104, 241-TY-105, and 241-TY-106) identified in RPP-RPT-43704, Hanford BY Farm Leak Assessments Report, and in RPP-RPT-42296, Hanford TY Farm Leak Assessments Report. This document satisfies the BY and TY Farm portion of the target (T04) in Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2013-11-19T23:59:59.000Z

115

Statistical Methods and Tools for Hanford Staged Feed Tank Sampling  

SciTech Connect

This report summarizes work conducted by Pacific Northwest National Laboratory to technically evaluate the current approach to staged feed sampling of high-level waste (HLW) sludge to meet waste acceptance criteria (WAC) for transfer from tank farms to the Hanford Waste Treatment and Immobilization Plant (WTP). The current sampling and analysis approach is detailed in the document titled Initial Data Quality Objectives for WTP Feed Acceptance Criteria, 24590-WTP-RPT-MGT-11-014, Revision 0 (Arakali et al. 2011). The goal of this current work is to evaluate and provide recommendations to support a defensible, technical and statistical basis for the staged feed sampling approach that meets WAC data quality objectives (DQOs).

Fountain, Matthew S.; Brigantic, Robert T.; Peterson, Reid A.

2013-10-01T23:59:59.000Z

116

Retrieval of Tenth Single-shell Tank Complete at Hanford's Office of River  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Retrieval of Tenth Single-shell Tank Complete at Hanford's Office Retrieval of Tenth Single-shell Tank Complete at Hanford's Office of River Protection Retrieval of Tenth Single-shell Tank Complete at Hanford's Office of River Protection December 27, 2012 - 12:00pm Addthis EM’s Office of River Protection has successfully removed waste from a tenth storage tank at the Hanford site. Located in C Farm, C-109 is one of 16 underground tanks ranging in capacity from 55,000 to 530,000 gallons. EM's Office of River Protection has successfully removed waste from a tenth storage tank at the Hanford site. Located in C Farm, C-109 is one of 16 underground tanks ranging in capacity from 55,000 to 530,000 gallons. Standing near a pipe providing access to the tank below, workers initiate a water soak aimed at loosening hard-to-remove-waste from the bottom of the underground tank known as C-109.

117

Evaporation of a Large Decontaminated Hanford Tank Sample  

SciTech Connect

A radioactive sample (approximately 15 L) from Hanford tank 241-AN-102 was concentrated via evaporation at reduced pressure and temperature, to support flowsheet development and regulatory approval for the Hanford River Protection Project Waste Treatment Plant (RPP-WTP). The received sample (Envelope C) had been pretreated at the Savannah River Technology Center (SRTC) for removal of strontium and transuranic ions by precipitation and removal of cesium and technetium via ion exchange. The resulting pretreated Low Activity Waste (LAW) stream was the feed material for this evaporation test. The goals of this evaporation were to: (1) provide operating data -- including foaming and scaling tendencies -- for scale-up purposes, (2) obtain liquid and off-gas samples during steady-state operation for regulatory analysis, (3) conduct a ''final boildown'' after the steady-state operation to determine the solubility endpoint of the solution and the major precipitants, and (4) provide concentrated feed for a melter vitrification study to produce several kilograms of immobilized LAW glass product.

Crawford, C.L.

2001-03-22T23:59:59.000Z

118

Inhibited Release of Mobile Contaminants from Hanford Tank Residual Waste  

SciTech Connect

Investigations of contaminant release from Hanford Site tank residual waste have indicated that in some cases certain contaminants of interest (Tc and Cr) exhibit inhibited release. The percentage of Tc that dissolved from residual waste from tanks 241-C-103, 241-C-106, 241-C-202, and 241-C-203 ranged from approximately 6% to 10%. The percent leachable Cr from residual waste from tanks C-103, C 202, and C-203 ranged from approximately 1.1% to 44%. Solid phase characterization results indicate that the recalcitrant forms of these contaminants are associated with iron oxides. X-ray absorption near edge structure analysis of Tc and Cr in residual waste indicates that these contaminants occur in Fe oxide particles as their lower, less soluble oxidation states [Tc(IV) and Cr(III)]. The form of these contaminants is likely as oxides or hydroxides incorporated within the structure of the Fe oxide. Leaching behavior of U from tank residual waste was studied using deionized water, and CaCO3 and Ca(OH)2 saturated solutions as leachants. The release behavior of U from tank residual waste is complex. Initial U concentrations in water and CaCO3 leachants are high due to residual amounts of the highly soluble U mineral cejkaite. As leaching and dilution occur NaUO2PO4 {center_dot} xH2O, Na2U2O7(am) and schoepite (or a similar phase) become the solubility controlling phases for U. In the case of the Ca(OH)2 leachant, U release from tank residual waste is dramatically reduced. Thermodynamic modeling indicates that the solubility of CaUO4(c) controls release of U from residual waste in the Ca(OH)2 leachants. It is assumed the solubility controlling phase is actually a hydrated version of CaUO4 with a variable water content ranging from CaUO4 to CaUO4 {center_dot} (H2O). The critically reviewed value for CaUO4(c) (log KSP0 = 15.94) produced good agreement with our experimental data for the Ca(OH)2 leachates.

Cantrell, Kirk J.; Heald, Steve M.; Arey, Bruce W.; Lindberg, Michael J.

2011-03-03T23:59:59.000Z

119

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT BUCKLING EVALUATION METHODS & RESULTS FOR THE PRIMARY TANKS  

Science Conference Proceedings (OSTI)

This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste facility (AWF) primary tank ventilation system. The current buckling review focuses on the following tasks: (1) Evaluate the potential for progressive I-bolt failure and the appropriateness of the safety factors that were used for evaluating local and global buckling. The analysis will specifically answer the following questions: (a) Can the EH-22 scenario develop if the vacuum is limited to -6.6-inch water gage (w.g.) by a relief valve? (b) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario can develop? (c) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario cannot develop? (2) Develop influence functions to estimate the axial stresses in the primary tanks for all reasonable combinations of tank loads, based on detailed finite element analysis. The analysis must account for the variation in design details and operating conditions between the different DSTs. The analysis must also address the imperfection sensitivity of the primary tank to buckling. (3) Perform a detailed buckling analysis to determine the maximum allowable differential pressure for each of the DST primary tanks at the current specified limits on waste temperature, height, and specific gravity. Based on the I-bolt loads analysis and the small deformations that are predicted at the unfactored limits on vacuum and axial loads, it is very unlikely that the EH-22 scenario (i.e., progressive I-bolt failure leading to global buckling of the tank under increased vacuum) could occur.

MACKEY TC; JOHNSON KI; DEIBLER JE; PILLI SP; RINKER MW; KARRI NK

2007-02-14T23:59:59.000Z

120

EM Tank Waste Subcommittee Report for SRS and Hanford Tank Waste Review  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

One System Plan. ........................................................................................................ 88 v PREFACE This is the second report of the Environmental Management Tank Waste Subcommittee (EM- TWS) of the Environmental Management Advisory Board (EMAB). The first report was submitted and accepted by the Assistant Secretary for Environmental Management (EM-1) in September 2010. The EM-TWS responded to three charges from EM-1 regarding the Waste Treatment and Immobilization Plant at Hanford (WTP) under construction in Richland, Washington. EM's responses were timely, and efforts have been put in place to address the recommendations that EMAB made. This report addresses eight charges given to the EM-TWS earlier this fiscal year. The current

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

ALTERATION OF KAOLINITE TO CANCRINITE AND SODALITE BY SIMULATED HANFORD TANK WASTE AND ITS IMPACT ON CESIUM RETENTION  

E-Print Network (OSTI)

ALTERATION OF KAOLINITE TO CANCRINITE AND SODALITE BY SIMULATED HANFORD TANK WASTE AND ITS IMPACT Department of Energy's Hanford site in Washington State (USA) causing hundreds of thousands of gallons--Cancrinite, Cation Exchange, Cesium Sorption, Feldspathoid , Hanford Waste Tanks, Kaolinite, Mineral Stability

Flury, Markus

122

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

Science Conference Proceedings (OSTI)

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

123

Hanford Site waste tank farm facilities design reconstitution program plan  

SciTech Connect

Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980`s has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan.

Vollert, F.R.

1994-09-06T23:59:59.000Z

124

Criticality safety analysis of Hanford Waste Tank 241-101-SY  

SciTech Connect

As part of a safety assessment for proposed pump mixing operations to mitigate episodic gas releases in Tank 241-101-SY at the Hanford Site, Richland, Washington, a criticality safety analysis was made using the Sn transport code ONEDANT. The tank contains approximately one million gallons of waste and an estimated 910 G of plutonium. the criticality analysis considers reconfiguration and underestimation of plutonium content. The results indicate that Tank SY-101 does not present a criticality hazard. These methods are also used in criticality analyses of other Hanford tanks.

Perry, R.T.; Sapir, J.L.; Krohn, B.J.

1993-12-31T23:59:59.000Z

125

Hanford Tank Initiative (HTI) & Acquire Commercial Technology for Retrieval Report & Database  

SciTech Connect

The data base is an annotated bibliography of technology evaluations and demonstrations conducted in previous years by the Hanford Tank Initiative (HTI) and the Acquire Commercial Technology for Retrieval (ACTR) programs.

SEDERBURG, J. P

2000-08-31T23:59:59.000Z

126

Review of technologies for the pretreatment of retrieved single-shell tank waste at Hanford  

SciTech Connect

The purpose of the study reported here was to identify and evaluate innovative processes that could be used to pretreat mixed waste retrieved from the 149 single-shell tanks (SSTs) on the US Department of Energy`s (DOE) Hanford site. The information was collected as part of the Single Shell Tank Waste Treatment project at Pacific Northwest Laboratory (PNL). The project is being conducted for Westinghouse Hanford Company under their SST Disposal Program.

Gerber, M.A.

1992-08-01T23:59:59.000Z

127

Review of technologies for the pretreatment of retrieved single-shell tank waste at Hanford  

SciTech Connect

The purpose of the study reported here was to identify and evaluate innovative processes that could be used to pretreat mixed waste retrieved from the 149 single-shell tanks (SSTs) on the US Department of Energy's (DOE) Hanford site. The information was collected as part of the Single Shell Tank Waste Treatment project at Pacific Northwest Laboratory (PNL). The project is being conducted for Westinghouse Hanford Company under their SST Disposal Program.

Gerber, M.A.

1992-08-01T23:59:59.000Z

128

Hanford Single-Shell Tank Leak Causes and Locations - 241-A Farm  

Science Conference Proceedings (OSTI)

This document identifies 241-A Tank Farm (A Farm) leak causes and locations for the 100 series leaking tanks (241-A-104 and 241-A-105) identified in RPP-ENV-37956, Hanford A and AX Farm Leak Assessment Report. This document satisfies the A Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2013-09-10T23:59:59.000Z

129

Hanford Single-Shell Tank Leak Causes and Locations - 241-C Farm  

SciTech Connect

This document identifies 241-C Tank Farm (C Farm) leak causes and locations for the 100 series leaking tanks (241-C-101 and 241-C-105) identified in RPP-RPT-33418, Rev. 2, Hanford C-Farm Leak Inventory Assessments Report. This document satisfies the C Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2013-07-30T23:59:59.000Z

130

Hanford Single-Shell Tank Leak Causes and Locations - 241-U Farm  

SciTech Connect

This document identifies 241-U Tank Farm (U Farm) leak causes and locations for the 100 series leaking tanks (241-U-104, 241-U-110, and 241-U-112) identified in RPP-RPT-50097, Rev. 0, Hanford 241-U Farm Leak Inventory Assessment Report. This document satisfies the U-Farm portion of the target (T04) in the Hanford Federal Facility Agreement and Consent Order milestone M-045-91F.

Girardot, Crystal L.; Harlow, Donald G.

2013-12-02T23:59:59.000Z

131

Screening for organic solvents in Hanford waste tanks using organic vapor concentrations  

SciTech Connect

The potential ignition of organic liquids stored in the Hanford Site high-level radioactive waste tanks has been identified as a safety issue because expanding gases could potentially affect tank dome integrity. Organic liquid waste has been found in some of the waste tanks, but most are thought to contain only trace amounts. Due to the inhomogeneity of the waste, direct sampling of the tank waste to locate organic liquids may not conclusively demonstrate that a given tank is free of risk. However, organic vapors present above the organic liquid waste can be detected with a high degree of confidence and can be used to identify problem tanks. This report presents the results of a screening test that has been applied to 82 passively ventilated high-level radioactive waste tanks at the Hanford Site to identify those that might contain a significant amount of organic liquid waste. It includes seven tanks not addressed in the previous version of this report, Screening for Organic Solvents in Hanford Waste Tanks Using Total Non-Methane Organic Compound Vapor Concentrations. The screening test is based on a simple model of the tank headspace that estimates the effective surface area of semivolatile organic liquid waste in a tank. Analyses indicate that damage to the tank dome is credible only if the organic liquid burn rate is above a threshold value, and this can occur only if the surface area of organic liquid in a tank is above a corresponding threshold value of about one square meter. Thirteen tanks were identified as potentially containing at least that amount of semivolatile organic liquid based on conservative estimates. Most of the tanks identified as containing potentially significant quantities of organic liquid waste are in the 241-BY and 241-C tank farms, which agrees qualitatively with the fact that these tank farms received the majority of the PUREX process organic wash waste and waste organic liquids.

Huckaby, J.L.; Sklarew, D.S.

1997-09-01T23:59:59.000Z

132

Hanford tank clean up: A guide to understanding the technical issues  

Science Conference Proceedings (OSTI)

One of the most difficult technical challenges in cleaning up the US Department of Energy`s (DOE) Hanford Site in southeast Washington State will be to process the radioactive and chemically complex waste found in the Site`s 177 underground storage tanks. Solid, liquid, and sludge-like wastes are contained in 149 single- and 28 double-shelled steel tanks. These wastes contain about one half of the curies of radioactivity and mass of hazardous chemicals found on the Hanford Site. Therefore, Hanford cleanup means tank cleanup. Safely removing the waste from the tanks, separating radioactive elements from inert chemicals, and creating a final waste form for disposal will require the use of our nation`s best available technology coupled with scientific advances, and an extraordinary commitment by all involved. The purpose of this guide is to inform the reader about critical issues facing tank cleanup. It is written as an information resource for the general reader as well as the technically trained person wanting to gain a basic understanding about the waste in Hanford`s tanks -- how the waste was created, what is in the waste, how it is stored, and what are the key technical issues facing tank cleanup. Access to information is key to better understanding the issues and more knowledgeably participating in cleanup decisions. This guide provides such information without promoting a given cleanup approach or technology use.

Gephart, R.E.; Lundgren, R.E.

1995-12-31T23:59:59.000Z

133

Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] 1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes DOE/EIS-0212 VOLUME 1 OF 2 VOLUME 1 FINAL ENVIRONMENTAL IMPACT STATEMENT SAFE INTERIM STORAGE OF HANFORD TANK WASTES Hanford Site Richland, Washington October, 1995 WASHINGTON STATE DEPARTMENT OF ECOLOGY NUCLEAR WASTE PROGRAM LACEY, WASHINGTON 98503 U.S. DEPARTMENT OF ENERGY RICHLAND OPERATIONS OFFICE

134

Simulation of Hanford Tank 241-C-106 Waste Release into Tank 241-Y-102  

SciTech Connect

Waste stored in Hdord single-shell Tank 241-C-106 will be sluiced with a supernatant liquid from doubIe-shell Tank 241 -AY- 102 (AY-1 02) at the U.S. Department of Energy's Har@ord Site in Eastern Washington. The resulting slurry, containing up to 30 wtYo solids, will then be transferred to Tank AY-102. During the sluicing process, it is important to know the mass of the solids being transferred into AY- 102. One of the primary instruments used to measure solids transfer is an E+ densitometer located near the periphery of the tank at riser 15S. This study was undert.dcen to assess how well a densitometer measurement could represent the total mass of soiids transferred if a uniform lateral distribution was assumed. The study evaluated the C-1 06 slurry mixing and accumulation in Tank AY- 102 for the following five cases: Case 1: 3 wt'%0 slurry in 6.4-m AY-102 waste Case 2: 3 w-t% slurry in 4.3-m AY-102 waste Case 3: 30 wtYo slurry in 6.4-m AY-102 waste Case 4: 30 wt% slurry in 4.3-m AY-102 waste Case 5: 30 wt% slurry in 5. O-m AY-102 waste. The tirne-dependent, three-dimensional, TEMPEST computer code was used to simulate solid deposition and accumulation during the injection of the C-106 slurry into AY-102 through four injection nozzles. The TEMPEST computer code was applied previously to other Hanford tanks, AP-102, SY-102, AZ-101, SY-101, AY-102, and C-106, to model tank waste mixing with rotating pump jets, gas rollover events, waste transfer from one tank to another, and pump-out retrieval of the sluiced waste. The model results indicate that the solid depth accumulated at the densitometer is within 5% of the average depth accumulation. Thus the reading of the densitometer is expected to represent the total mass of the transferred solids reasonably well.

KP Recknagle; Y Onishi

1999-05-19T23:59:59.000Z

135

Screening for organic solvents in Hanford waste tanks using total non- methane organic compound vapor concentrations  

SciTech Connect

The potential ignition of organic liquids stored in the Hanford high-level radioactive waste tanks is a safety issue because expanding gases could affect tank dome integrity. This report presents results of a screening test that was applied to 75 passively ventilated waste tanks at Hanford to determine those that might contain a significant amount of organic liquid waste. The screening test is based on a simple model of tank headspace, headspace organic vapor concentrations, and certain tank physical parameters. Analyses indicate that damage to the tank dome is credible only if the organic liquid burn rate is above a threshold value, and this can occur only if the surface area of organic liquid in a tank is above a corresponding threshold value of about one square meter. Twelve tanks were identified as potentially containing at least that amount of semivolatile organic liquid based on conservative estimates. Tank head space organic vapor concentrations and physical parameters required by the screening test have been compiled and are presented for each of the tanks studied. Estimates of the ventilation rates of the waste tanks were revised to reflect recent information obtained from hydrogen monitoring data. A simple analysis of the uncertainty in the test results suggests that the largest current uncertainty in the estimation of organic liquid surface area is that associated with knowledge of the tank ventilation rate. The uncertainty analysis is applied to determine 95% confidence limits for the estimated organic waste surface area in each tank.

Huckaby, J.L.; Glissmeyer, J.A.; Sklarew, D.S.

1997-02-01T23:59:59.000Z

136

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT SUMMARY OF COMBINED THERMAL & OPERATING LOADS  

Science Conference Proceedings (OSTI)

This report summarizes the results of the Double-Shell Tank Thermal and Operating Loads Analysis (TOLA) combined with the Seismic Analysis. This combined analysis provides a thorough, defensible, and documented analysis that will become a part of the overall analysis of record for the Hanford double-shell tanks (DSTs).

MACKEY, T.C.

2006-03-17T23:59:59.000Z

137

Estimation of Hanford SX tank waste compositions from historically derived inventories  

Science Conference Proceedings (OSTI)

Migration of radionuclides under the SX-tank farm at the Hanford nuclear waste complex involves interaction of sediments with concentrated NaOH-NaNO3-NaNO2 solutions that leaked from the tanks. This study uses a reaction path calculation ... Keywords: Gibbs free energy minimization, Pitzer equations, kinetic, rate limiter, reaction path

Peter C. Lichtner; Andrew R. Felmy

2003-04-01T23:59:59.000Z

138

AN ENHANCED HAZARD ANALYSIS PROCESS FOR THE HANFORD TANK FARMS  

SciTech Connect

CH2M HILL Hanford Group, Inc., has expanded the scope and increased the formality of process hazards analyses performed on new or modified Tank Farm facilities, designs, and processes. The CH2M HILL process hazard analysis emphasis has been altered to reflect its use as a fundamental part of the engineering and change control process instead of simply being a nuclear safety analysis tool. The scope has been expanded to include identification of accidents/events that impact the environment, or require emergency response, in addition to those with significant impact to the facility worker, the offsite, and the 100-meter receptor. Also, there is now an expectation that controls will be identified to address all types of consequences. To ensure that the process has an appropriate level of rigor and formality, a new engineering standard for process hazards analysis was created. This paper discusses the role of process hazards analysis as an information source for not only nuclear safety, but also for the worker-safety management programs, emergency management, environmental programs. This paper also discusses the role of process hazards analysis in the change control process, including identifying when and how it should be applied to changes in design or process.

SHULTZ MV

2008-05-15T23:59:59.000Z

139

Effects of simulant Hanford tank waste on plastic packaging components  

Science Conference Proceedings (OSTI)

In this paper, the authors describe a chemical compatibility testing program for packaging components which might be used to transport mixed wastes. They mention the results of the screening phase of this program and then present the results of the second phase of this experimental program. This effort involved the comprehensive testing of five plastic liner materials in the aqueous mixed waste simulant. The testing protocol involved exposing the respective materials to {approximately} 140, 290, 570, and 3,670 krads of gamma radiation followed by 7, 14, 28, 180 day exposures to the waste simulant at 18, 50, and 60 C. From the data analysis performed to date in this study, they have identified the fluorocarbon Kel-F{trademark} as having the greatest chemical compatibility after being exposed to gamma radiation followed by exposure to the Hanford Tank simulant mixed waste. The most striking observation from this study was the poor performance of Teflon under these conditions. The data obtained from this testing program will be available to packaging designers for the development of mixed waste packagings. The implications of the testing results on the selection of appropriate materials as packaging components are discussed.

Nigrey, P.J.; Dickens, T.G.

1996-07-01T23:59:59.000Z

140

RCRA Assessment Plan for Single-Shell Tank Waste Management Area A-AX at the Hanford Site  

Science Conference Proceedings (OSTI)

This document describes a groundwater assessment plan for the single-shell tank systems in Waste Management Area A-AX at the Hanford Site.

Narbutovskih, Susan M.; Chou, Charissa J.

2006-03-03T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Summary of Group Development and Testing for Single Shell Tank Closure at Hanford  

Science Conference Proceedings (OSTI)

This report is a summary of the bench-scale and large scale experimental studies performed by Savannah River National Laboratory for CH2M HILL to develop grout design mixes for possible use in producing fill materials as a part of Tank Closure of the Single-Shell Tanks at Hanford. The grout development data provided in this report demonstrates that these design mixes will produce fill materials that are ready for use in Hanford single shell tank closure. The purpose of this report is to assess the ability of the proposed grout specifications to meet the current requirements for successful single shell tank closure which will include the contracting of services for construction and operation of a grout batch plant. The research and field experience gained by SRNL in the closure of Tanks 17F and 20F at the Savannah River Site was leveraged into the grout development efforts for Hanford. It is concluded that the three Hanford grout design mixes provide fill materials that meet the current requirements for successful placement. This conclusion is based on the completion of recommended testing using Hanford area materials by the operators of the grout batch plant. This report summarizes the regulatory drivers and the requirements for grout mixes as tank fill material. It is these requirements for both fresh and cured grout properties that drove the development of the grout formulations for the stabilization, structural and capping layers.

Harbour, John, R.

2005-04-28T23:59:59.000Z

142

Operational Awarness at Hanford Tank Farms, April 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

HSS Independent Activity Report - Rev. 0 Report Number: HIAR-HANFORD-2013-04-15 Site: Hanford - Office of River Protection Subject: Office of Enforcement and Oversight's Office of...

143

Hanford Double-Shell Tank Extent-of-Condition Construction Review - 14174  

SciTech Connect

During routine visual inspections of Hanford double-shell waste tank 241-AY-102 (AY-102), anomalies were identified on the annulus floor which resulted in further evaluations. Following a formal leak assessment in October 2012, Washington River Protection Solutions, LLC (WRPS) determined that the primary tank of AY-102 was leaking. The formal leak assessment, documented in RPP-ASMT-53793,Tank 241-AY-102 Leak Assessment Report, identified first-of-a-kind construction difficulties and trial-and-error repairs as major contributing factors to tank failure. To determine if improvements in double-shell tank (DST) construction occurred after construction of tank AY-102, a detailed review and evaluation of historical construction records were performed for the first three DST tank farms constructed, which included tanks 241-AY-101, 241-AZ-101, 241-AZ-102, 241-SY-101, 241-SY-102, and 241-SY-103. The review for these six tanks involved research and review of dozens of boxes of historical project documentation. These reviews form a basis to better understand the current condition of the three oldest Hanford DST farms. They provide a basis for changes to the current tank inspection program and also provide valuable insight into future tank use decisions. If new tanks are constructed in the future, these reviews provide valuable ?lessons-learned? information about expected difficulties as well as construction practices and techniques that are likely to be successful.

Venetz, Theodore J.; Johnson, Jeremy M.; Gunter, Jason R.; Barnes, Travis J.; Washenfelder, Dennis J.; Boomer, Kayle D.

2013-11-14T23:59:59.000Z

144

Predicting flammable gas mixtures in Hanford double-contained receiver tanks  

DOE Green Energy (OSTI)

This study presents a methodology to estimate the maximum concentrations of flammable gases (ammonia, hydrogen, and methane) which could exist in the vapor space of a double-contained receiver tank (DCRT). DCRTs are temporary storage tanks which receive highly radioactive liquid wastes from salt well pumping of Hanford single-shell tanks (SST). The methodology of this study could be used in other applications involving the storage and transfer of radioactive liquid wastes which generate or contain various dissolved flammable gases.

Hedengren, D.C.

1998-05-13T23:59:59.000Z

145

Hanford Tank 241-C-106: Residual Waste Contaminant Release Model and Supporting Data  

Science Conference Proceedings (OSTI)

CH2M HILL is producing risk/performance assessments to support the closure of single-shell tanks at the DOE's Hanford Site. As part of this effort, staff at PNNL were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. This report provides the information developed by PNNL.

Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

2005-06-03T23:59:59.000Z

146

Assessment of chemical vulnerabilities in the Hanford high-level waste tanks  

SciTech Connect

The purpose of this report is to summarize results of relevant data (tank farm and laboratory) and analysis related to potential chemical vulnerabilities of the Hanford Site waste tanks. Potential chemical safety vulnerabilities examined include spontaneous runaway reactions, condensed phase waste combustibility, and tank headspace flammability. The major conclusions of the report are the following: Spontaneous runaway reactions are not credible; condensed phase combustion is not likely; and periodic releases of flammable gas can be mitigated by interim stabilization.

Meacham, J.E. [and others

1996-02-15T23:59:59.000Z

147

Soil structural analysis tools and properties for Hanford site waste tank evaluation  

Science Conference Proceedings (OSTI)

As Hanford Site contractors address future structural demands on nuclear waste tanks, built as early as 1943, it is necessary to address their current safety margins and ensure safe margins are maintained. Although the current civil engineering practice guidelines for soil modeling are suitable as preliminary design tools, future demands potentially result in loads and modifications to the tanks that are outside the original design basis and current code based structural capabilities. For example, waste removal may include cutting a large hole in a tank. This report addresses both spring modeling of site soils and finite-element modeling of soils. Additionally seismic dynamic modeling of Hanford Site soils is also included. Of new and special interest is Section 2.2 that Professor Robert D. Holtz of the University of Washington wrote on plane strain soil testing versus triaxial testing with Hanford Site application to large buried waste tanks.

Moore, C.J.; Holtz, R.D.; Wagenblast, G.R.; Weiner, E.D.; Marlow, R.S.

1995-09-01T23:59:59.000Z

148

Independent Oversight Review of Hanford Tank Farms Safety Basis...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to create tank vacuum exceeding their analyzed capabilities, which could result in structural failures. The vacuum relief valves and other tank vacuum 3 protection devices are...

149

Data quality objectives process applied to characterization of Hanford tanks containing ferrocyanide  

Science Conference Proceedings (OSTI)

Since 1944, underground storage tanks located at the Hanford Site in Richland, Washington, have stored approximately 277,000 m{sup 3} (60 Mgal) of highly radioactive and non-radioactive wastes. Recently, a number of safety issues have arisen concerning these tanks, with regard to worker and public health. The US Department of Energy (DOE) has made the resolution of these safety concerns its number one priority at the Hanford Site. The safety program of the Tank Waste Remediation System (TWRS) was developed to provide an integrated approach to resolution of these waste tank safety issues and safety concerns. The Characterization Program within TWRS is responsible for characterizing the wastes contained in the tanks. To ensure that characterization activities provide data that will be adequate to resolve safety concerns, the Data Quality Objectives (DQO) process is being implemented.

Pulsipher, B.A.; Anderson, C.M.; Buck, J.W. [Pacific Northwest Lab., Richland, WA (United States); Cash, R.J.; Dukelow, G.T.; Meacham, J.E. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

150

Analysis of organic carbon and moisture in Hanford single-shell tank waste  

SciTech Connect

This report documents a revised analysis performed by Pacific Northwest Laboratory involving the organic carbon laboratory measurement data for Hanford single-shell tanks (SSTs) obtained from a review of the laboratory analytical data. This activity has as its objective to provide a best-estimate, including confidence levels, of total organic carbon (TOC) and moisture in each of the 149 SSTs at Hanford. The TOC and moisture information presented in this report is useful as part of the criteria to identify SSTs for additional measurements, or monitoring for the Organic Safety Program. In April 1994, an initial study of the organic carbon in Hanford single-shell tanks was completed at PNL. That study reflected the estimates of TOC based on tank characterizations datasets that were available at the time. Also in that study, estimation of dry basis TOC was based on generalized assumptions pertaining to the moisture of the tank wastes. The new information pertaining to tank moisture and TOC data that has become available from the current study influences the best estimates of TOC in each of the SSTs. This investigation of tank TOC and moisture has resulted in improved estimates based on waste phase: saltcake, sludge, or liquid. This report details the assumptions and methodologies used to develop the estimates of TOC and moisture in each of the 149 SSTs at Hanford.

Toth, J.J.; Heasler, P.G.; Lerchen, M.E.; Hill, J.G.; Whitney, P.D.

1995-05-01T23:59:59.000Z

151

Hanford ETR - Tank Waste Treatment and Immobilization Plant - Hanford Tank Waste Treatment and Immobilization Plant Technical Review - Estimate at Completion (Cost) Report  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Comprehensive Review of the Hanford Tank Waste Treatment and Immobilization Plant Estimate at Completion Assessment Conducted by an Independent Team of External Experts March 2006 Comprehensive Review of the Hanford Waste Treatment Plant Estimate at Completion Page i of vi Executive Summary Following an August 2005 corporate commitment to the Secretary of Energy, Bechtel National, Inc. chartered a team of industry experts to review the technical, cost, and schedule aspects of the Waste Treatment and Immobilization Plant (WTP) project. This summary reflects the observations and recommendations of the EAC Review Team (ERT), comprised of six senior industry consultants, six retired Bechtel employees, one current Bechtel employee, three employees of Bechtel's competitors, and

152

Hanford Tank Waste What is in it? Where is it going?  

Science Conference Proceedings (OSTI)

The Waste Treatment Plant currently under construction for treatment of High Level Waste at the Hanford Site will process High Level Waste (HLW) to reduce the quantity of HLW material that must be immobilized. Recently, an extensive testing program was undertaken to characterize the composition of some of the major sources of HLW in the Hanford tank farm system. This effort has led to an increased understanding of the chemical form and the underlying dissolution chemistry for much of the waste.

Peterson, Reid A.; Fiskum, Sandra K.; Snow, Lanee A.; Edwards, Matthew K.; Shimskey, Rick W.

2010-11-30T23:59:59.000Z

153

Changes in the pore network structure of Hanford sediment after reaction1 with caustic tank wastes2  

E-Print Network (OSTI)

Changes in the pore network structure of Hanford sediment after reaction1 with caustic tank wastes2@princeton.edu9 10 11 Abstract12 At the former nuclear weapons production site in Hanford, WA, caustic radioactive due to these geochemical reactions. The reacted Hanford sediment column had been18 imaged in 3D using

New York at Stoney Brook, State University of

154

Structural analysis of Hanford`s single-shell 241-C-106 tank: A first step toward waste-tank remediation  

SciTech Connect

The buried single-shell waste tank 241-C-106, located at the US Department of Energy`s Hanford Site, has been a repository for various liquid radioactive waste materials since its construction in 1943. A first step toward waste tank remediation is demonstrating that remediation activities can be performed safely. Determination of the current structural capacity of this high-heat tank is an important element in this assessment. A structural finite-element model of tank 241-C-106 has been developed to assess the tank`s structural integrity with respect to in situ conditions and additional remediation surface loads. To predict structural integrity realistically, the model appropriately addresses two complex issues: (1) surrounding soil-tank interaction associated with thermal expansion cycling and surcharge load distribution and (2) concrete-property degradation and creep resulting from exposure to high temperatures generated by the waste. This paper describes the development of the 241-C-106 structural model, analysis methodology, and tank-specific structural acceptance criteria.

Harris, J.P.; Julyk, L.J.; Marlow, R.S.; Moore, C.J. [Westinghouse Hanford Co., Richland, WA (United States); Day, J.P.; Dyrness, A.D.; Jagadish, P.; Shulman, J.S. [Advent Engineering Services, Inc., San Ramon, CA (United States)

1993-10-01T23:59:59.000Z

155

Hanford Tanks 241-AY-102 and 241-BX-101: Sludge Composition and Contaminant Release Data  

SciTech Connect

This report describes the results of testing sludge samples from Hanford tanks 241-AY-102 (AY-102) and 241-BX-101 (BX-101). These tests were conducted to characterize the sludge and assess the water leachability of contaminants from the solids. This work is being conducted to support the tank closure risk assessments being performed by CH2M HILL Hanford Group, Inc. for the U.S. Department of Energy. This is the first report of testing of BX-101 sludge and the second report of testing of AY-102. Lindberg and Deutsch (2003) described the first phase of testing on AY-102 material.

Krupka, Kenneth M.; Deutsch, William J.; Lindberg, Michael J.; Cantrell, Kirk J.; Hess, Nancy J.; Schaef, Herbert T.; Arey, Bruce W.

2004-05-01T23:59:59.000Z

156

Selection of Pretreatment Processes for Removal of Radionuclides from Hanford Tank Waste  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy's (DOE's), Office of River Protection (ORP) located at Hanford Washington has established a contract (1) to design, construct, and commission a new Waste Treatment and Immobilization Plant (WTP) that will treat and immobilize the Hanford tank wastes for ultimate disposal. The WTP is comprised of four major elements, pretreatment, LAW immobilization, HLW immobilization, and balance of plant facilities. This paper describes the technologies selected for pretreatment of the LAW and HLW tank wastes, how these technologies were selected, and identifies the major technology testing activities being conducted to finalize the design of the WTP.

Carreon, R.; Mauss, B. M.; Johnson, M. E.; Holton, L. K.; Wright, G. T.; Peterson, R. A.; Rueter, K. J.

2002-02-26T23:59:59.000Z

157

EIS-0391: Hanford Tank Closure and Waste Management, Richland...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal...

158

Washing and caustic leaching of Hanford tank sludge: Results of FY 1997 studies  

Science Conference Proceedings (OSTI)

The current plan for remediating the Hanford tank farms consists of waste retrieval, pretreatment, treatment (immobilization), and disposal. The tank wastes will be partitioned into high-level and low-level fractions. The HLW will be immobilized in a borosilicate glass matrix; the resulting glass canisters will then be disposed of in a geologic repository. Because of the expected high cost of HLW vitrification and geologic disposal, pretreatment processes will be implemented to reduce the volume of immobilized high-level waste (IHLW). Caustic leaching (sometimes referred to as enhanced sludge washing or ESW) represents the baseline method for pretreating Hanford tank sludges. Caustic leaching is expected to remove a large fraction of the Al, which is present in large quantities in Hanford tank sludges. A significant portion of the P is also expected to be removed from the sludge by metathesis of water-insoluble metal phosphates to insoluble hydroxides and soluble Na{sub 3}PO{sub 4}. Similar metathesis reactions can occur for insoluble sulfate salts, allowing the removal of sulfate from the HLW stream. This report describes the sludge washing and caustic leaching tests performed at the Pacific Northwest National Laboratory in FY 1996. The sludges used in this study were taken from Hanford tanks AN-104, BY-108, S-101, and S-111.

Lumetta, G.J.; Burgeson, I.E.; Wagner, M.J.; Liu, J.; Chen, Y.L.

1997-08-01T23:59:59.000Z

159

Criticality Safety Evaluation of Hanford Tank Farms Facility  

SciTech Connect

Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

WEISS, E.V.

2000-12-15T23:59:59.000Z

160

Discovery of the First Leaking Double-Shell Tank - Hanford Tank 241-AY-102  

SciTech Connect

A routine video inspection of the annulus region of double-shell tank 241-A Y-102 in August of 2012 indicated the presence material in the annulus space between the primary and secondary liners. A comparison was made to previous inspections perfom1ed in 2006 and 2007. which indicated that a change had occurred. The material was observed at two locations on the floor of the annulus and one location at the top of the annulus region where the primary and secondary top knuckles meet (RPP-ASMT-53793). Subsequent inspections were performed. leading to additional material observed on the floor of the annulus space in a region that had not previously been inspected (WRPS-PER-2012-1363). The annulus Continuous Air Monitor (CAM) was still operational and was not indicating elevated radiation levels in the annulus region. When the camera from the inspections was recovered. it also did not indicate increased radiation above minimum contamination levels (WRPS-PER-2012-1363). A formal leak assessment team was established August 10, 2012 to review tank 241-AY-102 construction and operating histories and to determine whether the material observed in the annulus had resulted from a leak in the primary tank. The team consisted of individuals from Engineering. Base Operations.and Environmental Protection. As this was a first-of-its-kind task. a method for obtaining a sample of the material in the annulus was needed. The consistency of the material was unknown.and the location of a majority of the material was not conducive to using the sampling devices that were currently available at Hanford. A subcontractor was tasked with the development fabrication.and testing of a sampling device that would be able to obtain multiple samples from the material on the annulus floor. as well as the material originating from a refractory air-slot near the floor of the annulus space. This sampler would need to be able to collect and dispense the material it collected into a sample jar retrieval device for transportation of the material to the 222-S laboratory on the Hanford site for analysis. The subcontractor agency fabricated a remote underground sampler by modifying off-the-shelf robotics and parts. Limited testing of the sampler was conducted using a mock-up of the tank annulus and one simulated material type -a salt block. The mock-up testing indicated that the sampler would be able to maneuver within the confined space and that the device worked with full functionality. A total of six weeks had passed from initiation to implementation of the new sampler in the 241-AY-102 tank annulus. Initial sample material was obtained from the annulus floor using the Off-Riser Sampler System that has been used at Hanford tor years to obtain material from the primary tanks. This could be used at the location near Riser 83 since the material was collected directly from the annulus floor and not from a location on the wall or behind a pipe, as was needed from the two locations near Riser 90. After obtaining a small sample of the material on the annulus floor.this sampler sustained terminal damage due to conduit pipes it had to transverse in order to collect and recover material from this location. Several issues were also encountered during deployment of the new sampler into the annulus near Riser 90. These included: Difficulty fitting the sampler down the 12-inch riser into the annulus due to a small tolerance in the size ofthe sampler Failure of sampler components and functions during deployment including the camera. pneumatics.and bearing seals Delays in the field due to supporting equipment issues including cables. cameras. and scaffolding Low recovery of sample material obtained for analysis The complications that occurred during deployment and use of the new sampler during the sampling event ultimately resulted in lower recovery of material from these locations in the annulus than was obtained using the Off-Riser Sampler System and limited the analyses that could be performed for determining the origin of the material. Following completion of th

Harrington, Stephanie J.; Sams, Terry L.

2013-08-15T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Criteria for temperature monitoring in ferrocyanide waste tanks at the Hanford Site  

Science Conference Proceedings (OSTI)

This report is relevant to the twenty underground waste storage tanks at the Hanford Site that have been identified as potentially containing a significant amount of ferrocyanide compounds. Tanks believed to contain > 1,000 gram moles of ferrocyanide have been classified as Watch List tanks. This report addresses temperature monitoring criteria for the Ferrocyanide Watch List tanks. These criteria must comply with governing regulations to ensure that safe continued storage of the tank wastes is not jeopardized. Temperature monitoring is defined in this report as the routine as the routine continuous measurement of a waste tank temperature with an output that is tied to an actively interrogated information collection system that includes an automated warning of temperature increases beyond the established limits.

Fowler, K.D.; Dukelow, G.T.

1994-09-01T23:59:59.000Z

162

Hanford high level waste (HLW) tank mixer pump safe operating envelope reliability assessment  

DOE Green Energy (OSTI)

The US Department of Energy and its contractor, Westinghouse Corp., are responsible for the management and safe storage of waste accumulated from processing defense reactor irradiated fuels for plutonium recovery at the Hanford Site. These wastes, which consist of liquids and precipitated solids, are stored in underground storage tanks pending final disposition. Currently, 23 waste tanks have been placed on a safety watch list because of their potential for generating, storing, and periodically releasing various quantities of hydrogen and other gases. Tank 101-SY in the Hanford SY Tank Farm has been found to release hydrogen concentrations greater than the lower flammable limit (LFL) during periodic gas release events. In the unlikely event that an ignition source is present during a hydrogen release, a hydrogen burn could occur with a potential to release nuclear waste materials. To mitigate the periodic gas releases occurring from Tank 101-SY, a large mixer pump currently is being installed in the tank to promote a sustained release of hydrogen gas to the tank dome space. An extensive safety analysis (SA) effort was undertaken and documented to ensure the safe operation of the mixer pump after it is installed in Tank 101-SY.1 The SA identified a need for detailed operating, alarm, and abort limits to ensure that analyzed safety limits were not exceeded during pump operations.

Fischer, S.R. [Los Alamos National Lab., NM (United States); Clark, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States)

1993-10-01T23:59:59.000Z

163

Chemical Characterization of an Envelope A Sample from Hanford Tank 241-AN-103  

Science Conference Proceedings (OSTI)

A whole tank composite sample from Hanford waste tank 241-AN-103 was received at the Savannah River Technology Center (SRTC) and chemically characterized. Prior to characterization the sample was diluted to {approximately}5 M sodium concentration. The filtered supernatant liquid, the total dried solids of the diluted sample, and the washed insoluble solids obtained from filtration of the diluted sample were analyzed. A mass balance calculation of the three fractions of the sample analyzed indicate the analytical results appear relatively self-consistent for major components of the sample. However, some inconsistency was observed between results where more than one method of determination was employed and for species present in low concentrations. A direct comparison to previous analyses of material from tank 241-AN-103 was not possible due to unavailability of data for diluted samples of tank 241-AN-103 whole tank composites. However, the analytical data for other types of samples from 241-AN-103 we re mathematically diluted and compare reasonably with the current results. Although the segments of the core samples used to prepare the sample received at SRTC were combined in an attempt to produce a whole tank composite, determination of how well the results of the current analysis represent the actual composition of the Hanford waste tank 241-AN-103 remains problematic due to the small sample size and the large size of the non-homogenized waste tank.

Hay, M.S.

2000-08-23T23:59:59.000Z

164

Review of Management of Safety Systems at the Hanford Tank Farms, April 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

Independent Oversight Review of Independent Oversight Review of Management of Safety Systems at the Hanford Tank Farms May 2011 February 2013 April 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

165

PSA results for Hanford high level waste Tank 101-SY  

DOE Green Energy (OSTI)

Los Alamos National Laboratory has performed a comprehensive probabilistic safety assessment (PSA) that includes consideration of external events for the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases (``burps``) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is underway in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. This PSA for Tank 101-SY, which did not consider the pump experiment or future tank-remediation activities, involved three distinct tasks. First, the accident sequence analysis identified and quantified those potential accidents whose consequences result in tank material release. Second, characteristics and release paths for the airborne and liquid radioactive source terms were determined. Finally, the consequences, primarily onsite and offsite potential health effects resulting from radionuclide release, were estimated, and overall risk curves were constructed. An overview of each of these tasks and a summary of the overall results of the analysis are presented in the following sections.

MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W. [Los Alamos National Lab., NM (United States); Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J. [PLG, Inc., Newport Beach, CA (United States)

1993-10-01T23:59:59.000Z

166

Review of the Hanford Tank Farms Radiological Controls Activity...  

NLE Websites -- All DOE Office Websites (Extended Search)

tank pump and slurry distributer, as well as excavation and installation of associated instrumentation. Independent Oversight also interviewed a selection of key personnel...

167

New methods for determination of interstitial liquid levels in Hanford waste tanks  

Science Conference Proceedings (OSTI)

The key to the leak detection program for many tanks at Hanford is the method used to evaluate the apparent interstitial liquid interface (ILL) within the pore space of the solid waste medium (either crystalline or sludge). Three new approaches were introduced in the summer of 1993 (count rate, derivative, and sigmoid), all of which significantly improved the accuracy and repeatability of interstitial liquid level values from neutron survey data. This paper summarizes the three new methods and details a case study in which, as a direct result of this improved analysis, a tank that had been declared an ``assumed leaker`` was reclassified as ``sound`` for the first time in Hanford`s 50 year history.

Barnes, D.A.; Raymond, R.E. [Westinghouse Hanford Co., Richland, WA (United States); Whitney, P.D. [Pacific Northwest Lab., Richland, WA (United States)

1995-01-01T23:59:59.000Z

168

DEWATERING TREATMENT SCALE-UP TESTING RESULTS OF HANFORD TANK WASTES  

SciTech Connect

This report documents CH2M HILL Hanford Group Inc. (CH2M HILL) 2007 dryer testing results in Richland, WA at the AMEC Nuclear Ltd., GeoMelt Division (AMEC) Horn Rapids Test Site. It provides a discussion of scope and results to qualify the dryer system as a viable unit-operation in the continuing evaluation of the bulk vitrification process. A 10,000 liter (L) dryer/mixer was tested for supplemental treatment of Hanford tank low-activity wastes, drying and mixing a simulated non-radioactive salt solution with glass forming minerals. Testing validated the full scale equipment for producing dried product similar to smaller scale tests, and qualified the dryer system for a subsequent integrated dryer/vitrification test using the same simulant and glass formers. The dryer system is planned for installation at the Hanford tank farms to dry/mix radioactive waste for final treatment evaluation of the supplemental bulk vitrification process.

TEDESCHI AR

2008-01-23T23:59:59.000Z

169

Overview of the Flammability of Gases Generated in Hanford Waste Tanks  

SciTech Connect

This report presents an overview of what is known about the flammability of the gases generated and retained in Hanford waste tanks in terms of the gas composition, the flammability and detonability limits of the gas constituents, and the availability of ignition sources. The intrinsic flammability (or nonflammability) of waste gas mixtures is one major determinant of whether a flammable region develops in the tank headspace; other factors are the rate, surface area, volume of the release, and the tank ventilation rate, which are not covered in this report.

LA Mahoney; JL Huckaby; SA Bryan; GD Johnson

2000-07-21T23:59:59.000Z

170

Historical tank content estimate for the southeast quadrant of the Hanford 200 Areas  

SciTech Connect

This document provides historical evaluations of the radioactive and mixed waste stored in the Hanford site underground double-shell tanks. A Historical Tank Content Estimate has been developed by reviewing the process histories, waste transfer data, and available physical and chemical characterization data from various Department of Energy and Department of Defense contractors. The historical data will supplement information that is currently being gathered from core sampling. Historical waste transfer and level data, tank physical information, temperature data, and sampling data have been compiled for this report and supporting documents.

NONE

1995-06-01T23:59:59.000Z

171

Physical mechanisms contributing to the episodic gas release from Hanford tank 241-SY-101  

DOE Green Energy (OSTI)

Volume growth of contents in a waste storage tank at Hanford is accompanied by episodic releases of gas and a rise in the level of tank contents. A theory is presented to describe how the gas is retained in the waste and how it is released. The theory postulates that somewhat cohesive gobs of sludge rise from the lower regions of the tank and buoyancy overcomes the cohesive strength of the slurry; this quantitatively explains several of the measured phenomena and qualitatively explains other observations.

Allemann, R.T.

1992-04-01T23:59:59.000Z

172

Hanford Tank 241-C-106: Impact of Cement Reactions on Release of Contaminants from Residual Waste  

Science Conference Proceedings (OSTI)

The CH2M HILL Hanford Group, Inc. (CH2M HILL) is producing risk/performance assessments to support the closure of single-shell tanks at the U.S. Department of Energy's Hanford Site. As part of this effort, staff at Pacific Northwest National Laboratory were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. Initial work to produce release models was conducted on residual tank sludge using pure water as the leaching agent. The results were reported in an earlier report. The decision has now been made to close the tanks after waste retrieval with a cementitious grout to minimize infiltration and maintain the physical integrity of the tanks. This report describes testing of the residual waste with a leaching solution that simulates the composition of water passing through the grout and contacting the residual waste at the bottom of the tank.

Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

2006-09-01T23:59:59.000Z

173

Contaminant Release Data Package for Residual Waste in Single-Shell Hanford Tanks  

Science Conference Proceedings (OSTI)

The Hanford Federal Facility Agreement and Consent Order requires that a Resource Conservation and Recovery Act (RCRA) Facility Investigation report be submitted to the Washington State Department of Ecology. The RCRA Facility Investigation report will provide a detailed description of the state of knowledge needed for tank farm performance assessments. This data package provides detailed technical information about contaminant release from closed single-shell tanks necessary to support the RCRA Facility Investigation report. It was prepared by Pacific Northwest National Laboratory (PNNL) for CH2M HILL Hanford Group, Inc., which is tasked by the U.S. Department of Energy (DOE) with tank closure. This data package is a compilation of contaminant release rate data for residual waste in the four Hanford single-shell tanks (SSTs) that have been tested (C-103, C-106, C-202, and C-203). The report describes the geochemical properties of the primary contaminants of interest from the perspective of long-term risk to groundwater (uranium, technetium-99, iodine-129, chromium, transuranics, and nitrate), the occurrence of these contaminants in the residual waste, release mechanisms from the solid waste to water infiltrating the tanks in the future, and the laboratory tests conducted to measure release rates.

Deutsch, William J.; Cantrell, Kirk J.; Krupka, Kenneth M.

2007-12-01T23:59:59.000Z

174

Data reconcilation study of Tank 241-AN-105 at the Hanford Site  

Science Conference Proceedings (OSTI)

The Project Hanford Management Contractor gave the Los Alamos National Laboratory Nuclear Systems Design and Analysis Group (TSA-10) the task of performing data reconciliation studies on flammable-gas watchlist tanks at the Hanford Site. This task is being performed in support of the flammable-gas programs at the Hanford Site and for closure of the flammable-gas unreviewed safety question. In our data reconciliation studies, we examine all available data from a global point of view. Our goal is to find an explanation, or conceptual model, of the tank behavior that is consistent with all available data. Our primary tool in this study of Tank 241-AN-105 is the maximum likelihood method of data reconciliation, which we have applied successfully to other tanks in the past. This method helps us (1) determine whether a model is consistent with the data, and (2) obtain quantitative estimates that are consistent with the data. A release of a flammable quantity of hydrogen in Tank 241-AN-105 is possible but unlikely at the current time. Any changes to the waste that could cause large releases would be accompanied by a measurable increase in the surface level of the waste. We also theorize that a significant increase in the waste temperature may signal a qualitative change in the behavior of the waste and an increase in the flammability hazard.

Kubic, W.L. Jr.; Pillay, G.

1998-12-31T23:59:59.000Z

175

HANFORD TANK FARM RESOURCE CONVERVATION & RECOVERY ACT (RCRA) CORRECTIVE ACTION PROGRAM  

SciTech Connect

As a consequence of producing special nuclear material for the nation's defense, large amounts of extremely hazardous radioactive waste was created at the US Department of Energy's (DOE) Hanford Site in south central Washington State. A little over 50 million gallons of this waste is now stored in 177 large, underground tanks on Hanford's Central Plateau in tank farms regulated under the Atomic Energy Act and the Resource, Conservation, and Recovery Act (RCRA). Over 60 tanks and associated infrastructure have released or are presumed to have released waste in the vadose zone. In 1998, DOE's Office of River Protection established the Hanford Tank Farm RCRA Corrective Action Program (RCAP) to: (1) characterize the distribution and extent of the existing vadose zone contamination; (2) determine how the contamination will move in the future; (3) estimate the impacts of this contamination on groundwater and other media; (4) develop and implement mitigative measures; and (5) develop corrective measures to be implemented as part of the final closure of the tank farm facilities. Since its creation, RCAP has made major advances in each of these areas, which will be discussed in this paper.

KRISTOFZSKI, J.G.

2007-01-15T23:59:59.000Z

176

Testing of organic waste surrogate materials in support of the Hanford organic tank program. Final report  

SciTech Connect

To address safety issues regarding effective waste management efforts of underground organic waste storage tanks at the Hanford Site, the Bureau of Mines conducted a series of tests, at the request of the Westinghouse Hanford company. In this battery of tests, the thermal and explosive characteristics of surrogate materials, chosen by Hanford, were determined. The surrogate materials were mixtures of inorganic and organic sodium salts, representing fuels and oxidants. The oxidants were sodium nitrate and sodium nitrite. The fuels were sodium salts of oxalate, citrate and ethylenediamine tetraacetic acid (EDTA). Polyethylene powder was also used as a fuel with the oxidant(s). Sodium aluminate was used as a diluent. In addition, a sample of FeCN, supplied by Hanford was also investigated.

Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Miron, Y. [Bureau of Mines (United States)

1994-01-01T23:59:59.000Z

177

Engineering study of 50 miscellaneous inactive underground radioactive waste tanks located at the Hanford Site, Washington  

SciTech Connect

This engineering study addresses 50 inactive underground radioactive waste tanks. The tanks were formerly used for the following functions associated with plutonium and uranium separations and waste management activities in the 200 East and 200 West Areas of the Hanford Site: settling solids prior to disposal of supernatant in cribs and a reverse well; neutralizing acidic process wastes prior to crib disposal; receipt and processing of single-shell tank (SST) waste for uranium recovery operations; catch tanks to collect water that intruded into diversion boxes and transfer pipeline encasements and any leakage that occurred during waste transfer operations; and waste handling and process experimentation. Most of these tanks have not been in use for many years. Several projects have, been planned and implemented since the 1970`s and through 1985 to remove waste and interim isolate or interim stabilize many of the tanks. Some tanks have been filled with grout within the past several years. Responsibility for final closure and/or remediation of these tanks is currently assigned to several programs including Tank Waste Remediation Systems (TWRS), Environmental Restoration and Remedial Action (ERRA), and Decommissioning and Resource Conservation and Recovery Act (RCRA) Closure (D&RCP). Some are under facility landlord responsibility for maintenance and surveillance (i.e. Plutonium Uranium Extraction [PUREX]). However, most of the tanks are not currently included in any active monitoring or surveillance program.

Freeman-Pollard, J.R.

1994-03-02T23:59:59.000Z

178

Hanford Tank Waste to WIPP - Maximizing the Value of our National Repository Asset - 14230  

Science Conference Proceedings (OSTI)

Preplanning scope for the Hanford tank transuranic (TRU) waste project was authorized in 2013 by the Department of Energy (DOE) Office of River Protection (ORP) after a project standby period of eight years. Significant changes in DOE orders, Hanford contracts, and requirements at the Waste Isolation Pilot Plant (WIPP) have occurred during this time period, in addition to newly implemented regulatory permitting, re-evaluated waste management strategies, and new commercial applications. Preplanning has identified the following key approaches for reactivating the project: qualification of tank inventory designations and completion of all environmental regulatory permitting; identifying program options to accelerate retrieval of key leaking tank T-111; planning fully compliant implementation of DOE Order 413.3B, and DOE Standard 1189 for potential on-site treatment; and re-evaluation of commercial retrieval and treatment technologies for better strategic bundling of permanent waste disposal options.

Tedeschi, Allan R.; Wheeler, Martin

2013-11-11T23:59:59.000Z

179

Proposed Occupational Exposure Limits for Non-Carcinogenic Hanford Waste Tank Vapor Chemicals  

SciTech Connect

A large number of volatile chemicals have been identified in the headspaces of tanks used to store mixed chemical and radioactive waste at the U.S. Department of Energy (DOE) Hanford Site, and there is concern that vapor releases from the tanks may be hazardous to workers. Contractually established occupational exposure limits (OELs) established by the Occupational Safety and Health Administration (OSHA) and American Conference of Governmental Industrial Hygienists (ACGIH) do not exist for all chemicals of interest. To address the need for worker exposure guidelines for those chemicals that lack OSHA or ACGIH OELs, a procedure for assigning Acceptable Occupational Exposure Limits (AOELs) for Hanford Site tank farm workers has been developed and applied to a selected group of 57 headspace chemicals.

Poet, Torka S.; Timchalk, Chuck

2006-03-24T23:59:59.000Z

180

Comparison of Sludge Digestion Methods for High Organic Hanford Tank 241-C-204  

SciTech Connect

This report presents the results of an investigation into methods for digesting sludge in tank 241-C-204 at the Hanford Site in south-central Washington State. The objective of this study was to compare the recovery of uranium, neptunium, and plutonium using three digestion methods: EPA Method 3052, EPA Method 3050B, and alkaline fusion. Results show that EPA Method 3052, microwave assisted acid digestion, is the most efficient digestion method with higher recoveries for both uranium and plutonium. This may also be the case for neptunium; however, the analytical results are uncertain for this element. The microwave digestion method also has the added benefits of being quicker and producing less waste, which lowers the overall cost per sample. Further testing with samples from other tanks will confirm that microwave assisted digestion is a viable method of digesting Hanford tank sludges (including those with a high organic content) for chemical analysis.

Lindberg, Michael J.; Deutsch, William J.

2006-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue  

Science Conference Proceedings (OSTI)

This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

1997-12-01T23:59:59.000Z

182

Status report for inactive miscellaneous underground storage tanks at Hanford Site 200 Areas  

DOE Green Energy (OSTI)

The purpose of this status report is to summarize updated data and information from the FY 1994 strategy plan that is associated with inactive miscellaneous underground storage tanks (IMUSTs). Assumptions and processes to assess potential risks and operational concerns are documented in this report. Safety issue priorities are ranked based on a number of considerations. Sixty-three IMUSTs have been Identified and placed on the official IMUST list. All the tanks are associated with past Hanford Site operations. Of the 63 tanks., 19 are catch tanks, 20 are vault tanks, 3 are neutralization tanks, 8 are settling tanks, 2 are solvent makeup tanks used to store hexone, 2 are flush tanks, 3 are decontamination tanks, 1 is a diverter station, 1 is a receiver tank, 1 is an experimental tank, and 3 are waste handling tanks. It is important to proactively deal with the risks Imposed by these 63 tanks, and at the same time not jeopardize the existing commitments and schedules for mitigating and resolving identified safety issues related to the 177 SSTs and DSTS. Access controls and signs have been placed on all but the three official IMUSTs added most recently. An accelerated effort to identify authorization documents and perform unreviewed safety question (USQ) screening has been completed. According to a set of criteria consistent with the safety screening data quality objective (DQO) process, 6 IMUSTs are ranked high related to the hydrogen generation potential safety Issue, 1 is ranked high related to the ferrocyanide potential safety issue, 6 are ranked high related to the flammability potential safety issue, and 25 are ranked high related to the vapor emissions potential safety issue.

Powers, T.B.

1995-10-01T23:59:59.000Z

183

Cost benefit of caustic recycle for tank waste remediation at the Hanford and Savannah River Sites  

SciTech Connect

The potential cost savings due to the use of caustic recycle used in conjunction with remediation of radioactive underground storage tank waste, is shown in a figure for the Hanford and Savannah River sites. Two cost savings estimates for each case have been made for Hanford, and one cost savings estimate for each case have been made for Hanford, and one cost savings estimate for each case has been made for the Savannah River site. This is due to the Hanford site remediation effort being less mature than that of Savannah River; and consequently, a range of cost savings being more appropriate for Hanford. This range of cost savings (rather than a ingle value) for each case at Hanford is due to cost uncertainties related to the LAW immobilization operation. Caustic recycle Case-1 has been defined as the sodium required to meet al identified caustic needs for the entire Site. Case-2 has been defined as the maximum sodium which can be separated from the low activity waste without precipitation of Al(OH){sub 3}. It has been determined that the potential cost savings at Hanford ranges from $194 M to $215 M for Case-1, and $293 M to $324 M for Case-2. The potential cost savings at Savannah River are $186 M for Case-1 and $281 M for Case-2. A discussion of the uncertainty associated with these cost savings estimates can be found in the Discussion and Conclusions section.

DeMuth, S. [Los Alamos National Lab., NM (United States). Technology and Safety Assessment Div.; Kurath, D. [Pacific Northwest National Lab., Richland, WA (United States)

1998-07-30T23:59:59.000Z

184

AUTOMATED LEAK DETECTION OF BURIED TANKS USING GEOPHYSICAL METHODS AT THE HANFORD NUCLEAR SITE  

SciTech Connect

At the Hanford Nuclear Site in Washington State, the Department of Energy oversees the containment, treatment, and retrieval of liquid high-level radioactive waste. Much of the waste is stored in single-shelled tanks (SSTs) built between 1943 and 1964. Currently, the waste is being retrieved from the SSTs and transferred into newer double-shelled tanks (DSTs) for temporary storage before final treatment. Monitoring the tanks during the retrieval process is critical to identifying leaks. An electrically-based geophysics monitoring program for leak detection and monitoring (LDM) has been successfully deployed on several SSTs at the Hanford site since 2004. The monitoring program takes advantage of changes in contact resistance that will occur when conductive tank liquid leaks into the soil. During monitoring, electrical current is transmitted on a number of different electrode types (e.g., steel cased wells and surface electrodes) while voltages are measured on all other electrodes, including the tanks. Data acquisition hardware and software allow for continuous real-time monitoring of the received voltages and the leak assessment is conducted through a time-series data analysis. The specific hardware and software combination creates a highly sensitive method of leak detection, complementing existing drywell logging as a means to detect and quantify leaks. Working in an industrial environment such as the Hanford site presents many challenges for electrical monitoring: cathodic protection, grounded electrical infrastructure, lightning strikes, diurnal and seasonal temperature trends, and precipitation, all of which create a complex environment for leak detection. In this discussion we present examples of challenges and solutions to working in the tank farms of the Hanford site.

CALENDINE S; SCHOFIELD JS; LEVITT MT; FINK JB; RUCKER DF

2011-03-30T23:59:59.000Z

185

Hanford Tanks 241-C-202 and 241-C-203 Residual Waste Contaminant Release Models and Supporting Data  

SciTech Connect

As directed by Congress, the U. S. Department of Energy (DOE) established the Office of River Protection in 1998 to manage DOE's largest, most complex environmental cleanup project retrieval of radioactive waste from Hanford tanks for treatment and eventual disposal. Sixty percent by volume of the nation's high-level radioactive waste is stored at Hanford in aging deteriorating tanks. If not cleaned up, this waste is a threat to the Columbia River and the Pacific Northwest. CH2M Hill Hanford Group, Inc., is the Office of River Protection's prime contractor responsible for the storage, retrieval, and disposal of Hanford's tank waste. As part of this effort, CH2M HILL Hanford Group, Inc. contracted with Pacific Northwest National Laboratory (PNNL) to develop release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for DOE.

Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Mattigod, Shas V.; Schaef, Herbert T.; Arey, Bruce W.

2007-09-13T23:59:59.000Z

186

Analysis of NaOH releases for Hanford tank farms  

Science Conference Proceedings (OSTI)

The information contained in the canceled document is now located in the document: Consequence Analysis of a NaOH Solution Spray Release During Addition to Waste Tank, WHC-SD-WM-CN-065.

Ryan, G.W., Westinghouse Hanford

1996-09-12T23:59:59.000Z

187

Structural Analysis on Hanford Single Shell Waste Tanks  

Thermal Profile for Type II Tanks 10. Thermal and Operating Loads Analysis ... Ultimate Load Evaluation at 2010 in-situ Conditions Year 64 @ 155 oF (1947 2010)

188

Pore Water Extraction Test Near 241-SX Tank Farm at the Hanford Site, Washington, USA - 14168  

SciTech Connect

A proof-of-principle test is underway near the Hanford Site 241-SX Tank Farm. The test will evaluate a potential remediation technology that will use tank farm-deployable equipment to remove contaminated pore water from vadose zone soils. The test system was designed and built to address the constraints of working within a tank farm. Due to radioactive soil contamination and limitations in drilling near tanks, small-diameter direct push drilling techniques applicable to tank farms are being utilized for well placement. To address space and weight limitations in working around tanks and obstacles within tank farms, the aboveground portions of the test system have been constructed to allow deployment flexibility. The test system utilizes low vacuum over a sealed well screen to establish flow into an extraction well. Extracted pore water is collected in a well sump,and then pumped to the surface using a small-diameter bladder pump.If pore water extraction using this system can be successfully demonstrated, it may be possible to target local contamination in the vadose zone around underground storage tanks. It is anticipated that the results of this proof-of-principle test will support future decision making regarding interim and final actions for soil contamination within the tank farms.

Eberlein, Susan J.; Parker, Danny L.; Tabor, Cynthia L.; Holm, Melissa J.

2013-11-11T23:59:59.000Z

189

Progress in resolving Hanford Site high-level waste tank safety issues  

DOE Green Energy (OSTI)

Interim storage of alkaline, high-level radioactive waste, from two generations of spent fuel reprocessing and waste management activities, has resulted in the accumulation of 238 million liters of waste in Hanford Site single and double-shell tanks. Before the 1990`s, the stored waste was believed to be: (1) chemically unreactive under its existing storage conditions and plausible accident scenarios; and (2) chemically stable. This paradigm was proven incorrect when detailed evaluation of tank contents and behavior revealed a number of safety issues and that the waste was generating flammable and noxious gases. In 1990, the Waste Tank Safety Program was formed to focus on identifying safety issues and resolving the ferrocyanide, flammable gas, organic, high heat, noxious vapor, and criticality issues. The tanks of concern were placed on Watch Lists by safety issue. This paper summarizes recent progress toward resolving Hanford Site high-level radioactive waste tank safety issues, including modeling, and analyses, laboratory experiments, monitoring upgrades, mitigation equipment, and developing a strategy to screen tanks for safety issues.

Babad, H.; Eberlein, S.J.; Johnson, G.D.; Meacham, J.E.; Osborne, J.W.; Payne, M.A.; Turner, D.A.

1995-02-01T23:59:59.000Z

190

OVERVIEW OF ENHANCED HANFORD SINGLE-SHELL TANK (SST) INTEGRITY PROJECT - 12128  

SciTech Connect

To improve the understanding of the single-shell tanks integrity, Washington River Protection Solutions, LLC, the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank (SST) Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The change package identified two phases of work for SST integrity. The initial phase has been focused on efforts to envelope the integrity of the tanks. The initial phase was divided into two primary areas of investigation: structural integrity and leak integrity. If necessary based on the outcome from the initial work, a second phase would be focused on further definition of the integrity of the concrete and liners. Combined these two phases are designed to support the formal integrity assessment of the Hanford SSTs in 2018 by Independent Qualified Registered Engineer. The work to further define the DOE's understanding of the structural integrity SSTs involves preparing a modern Analysis of Record using a finite element analysis program. Structural analyses of the SSTs have been conducted since 1957, but these analyses used analog calculation, less rigorous models, or focused on individual structures. As such, an integrated understanding of all of the SSTs has not been developed to modern expectations. In support of this effort, other milestones will address the visual inspection of the tank concrete and the collection of concrete core samples from the tanks for analysis of current mechanics properties. The work on the liner leak integrity has examined the leaks from 23 tanks with liner failures. Individual leak assessments are being developed for each tank to identify the leak cause and location. Also a common cause study is being performed to take the data from individual tanks to look for trends in the failure. Supporting this work is an assessment of the leak rate from tanks at both Hanford and the Savannah River Site and a new method to locate leak sites in tank liner using ionic conductivity. A separate activity is being conducted to examine the propensity for corrosion in select single shell tanks with aggressive waste layers. The work for these two main efforts will provide the basis for the phase two planning. If the margins identified aren't sufficient to ensure the integrity through the life of the mission, phase two would focus on activities to further enhance the understanding of tank integrity. Also coincident with any phase-two work would be the integrity analysis for the tanks, which would be complete in 2018. With delays in the completion of waste treatment facilities at Hanford, greater reliance on safe, continued storage of waste in the single shell tanks is increased in importance. The goal of integrity assessment would provide basis to continue SST activities till the end of the treatment mission.

VENETZ TJ; BOOMER KD; WASHENFELDER DJ; JOHNSON JB

2012-01-25T23:59:59.000Z

191

Estimate of the Distribution of Solids Within Mixed Hanford Double-Shell Tank AZ-101: Implications for AY-102  

SciTech Connect

This paper describes the current level of understanding of the suspension of solids in Hanford double-shell waste tanks while being mixed with the baseline configuration of two 300-horsepower mixer pumps. A mixer pump test conducted in Tank AZ-101 during fiscal year 2000 provided the basis for this understanding. Information gaps must be filled to demonstrate the capability of the baseline feed delivery system to effectively mix, sample, and deliver double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) for vitrification.

Wells, Beric E.; Ressler, Jennifer J.

2009-04-29T23:59:59.000Z

192

Hanford Tank Safety Project: Minutes of the Tank Waste Science Panel meeting, February 7--8, 1991  

DOE Green Energy (OSTI)

The Tank Waste Science Panel met February 7--8, 1991, to review the latest data from the analyses of the October 24, 1990, gas release from Tank 241-SY-101 (101-SY) at Hanford; discuss the results of work being performed in support of the Hanford Tank Safety Project; and be briefed on the ferrocyanide issues included in the expanded scope of the Science Panel. The shapes of the gas release curves from the past three events are similar and correlate well with changes in waste level, but the correlation between the released volume of gas and the waste height is not as good. An analysis of the kinetics of gas generation from waste height measurements in Tank 101-SY suggests that the reaction giving rise to the gases in the tank is independent of the gas pressure and independent of the physical processes that give rise to the episodic release of the gases. Tank waste height data were also used to suggest that a floating crust formed early in the history of the tank and that the current crust is being made thicker in the eastern sector of the tank by repeated upheaval of waste slurry onto the surface. The correlation between the N{sub 2}O and N{sub 2} generated in the October release appears to be 1:1, suggesting a single mechanistic pathway. Analysis of other gas generation ratios, however, suggests that H{sub 2} and N{sub 2}O are evolved together, whereas N{sub 2} is from the air. If similar ratios are observed in planned radiolysis experiments are Argonne National Laboratory, radiolysis would appear to be generating most of the gases in Tank 101-SY. Data from analysis of synthetic waste crust using a dynamic x-ray diffractometer suggest that, in air, organics are being oxidized and liberating CO{sub 2} and NO{sub x}. Experiments at Savannah River Laboratory indicate that irradiation of solutions containing NO{sub 3} and organics can produce N{sub 2}O.

Strachan, D.M. (comp.)

1991-06-01T23:59:59.000Z

193

STEADY STATE FLAMMABLE GAS RELEASE RATE CALCULATION AND LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE  

Science Conference Proceedings (OSTI)

This report assesses the steady state flammability level under off normal ventilation conditions in the tank headspace for 28 double-shell tanks (DST) and 149 single shell-tanks (SST) at the Hanford Site. Flammability was calculated using estimated gas release rates, Le Chatelier's rule, and lower flammability limits of fuels in an air mixture. This revision updates the hydrogen generation rate input data for all 177 tanks using waste composition information from the Best Basis Inventory Detail Report (data effective as of August 4,2008). Assuming only barometric breathing, the shortest time to reach 25% of the lower flammability limit is 11 days for DSTs (i.e., tank 241-AZ-10l) and 36 days for SSTs (i.e., tank 241-B-203). Assuming zero ventilation, the shortest time to reach 25% of the lower flammability limit is 10 days for DSTs (i.e., tank 241-AZ-101) and 34 days for SSTs (i.e., tank 241-B-203).

MEACHAM JE

2009-10-26T23:59:59.000Z

194

Organic Tank Safety Project: development of a method to measure the equilibrium water content of Hanford organic tank wastes and demonstration of method on actual waste  

Science Conference Proceedings (OSTI)

Some of Hanford`s underground waste storage tanks contain Organic- bearing high level wastes that are high priority safety issues because of potentially hazardous chemical reactions of organics with inorganic oxidants in these wastes such as nitrates and nitrites. To ensure continued safe storage of these wastes, Westinghouse Hanford Company has placed affected tanks on the Organic Watch List and manages them under special rules. Because water content has been identified as the most efficient agent for preventing a propagating reaction and is an integral part of the criteria developed to ensure continued safe storage of Hanford`s organic-bearing radioactive tank wastes, as part of the Organic Tank Safety Program the Pacific Northwest National Laboratory developed and demonstrated a simple and easily implemented procedure to determine the equilibrium water content of these potentially reactive wastes exposed to the range of water vapor pressures that might be experienced during the wastes` future storage. This work focused on the equilibrium water content and did not investigate the various factors such as @ ventilation, tank surface area, and waste porosity that control the rate that the waste would come into equilibrium, with either the average Hanford water partial pressure 5.5 torr or other possible water partial pressures.

Scheele, R.D.; Bredt, P.R.; Sell, R.L.

1996-09-01T23:59:59.000Z

195

Analysis of Induced Gas Releases During Retrieval of Hanford Double-Shell Tank Waste  

DOE Green Energy (OSTI)

Checklist for Technical Peer Review for PNNL-13782 Rev. 1 as requested to ensure that software used to support the DSA is compliant with software QA requirements. Radioactive waste is scheduled to be retrieved from Hanford double-shell tanks AN-103, AN-104, AN-105 and AW-101 and transferred to the vitrification plant beginning in about 2009. Retrieval may involve decanting the supernatant liquid and/or mixing the waste with jet pumps. In these four tanks, which contain relatively large volumes of retained gas, both operations are expected to induce buoyant displacement gas releases that can potentially raise the tank headspace hydrogen concentration to a level very near the lower flammability limit. This report describes the theory and detailed physical models for both the supernatant decant and jet mixing processes and presents the results from applying the models to these operations in the four tanks. The technical bases for input parameter distributions are elucidated.

Wells, Beric E.

2003-02-19T23:59:59.000Z

196

Analysis of Induced Gas Released During Retrieval of Hanford Double-Shell Tank Waste  

DOE Green Energy (OSTI)

Radioactive waste is scheduled to be retrieved from Hanford double-shell tanks AN-103, AN-104, AN-105 and AW-101 to the vitrification plant beginning about 2009. Retrieval may involve decanting the supernatant liquid and/or mixing the waste with jet pumps. In these four tanks, which contain relatively large volumes of retained gas, both of these operations are expected to induce buoyant displacement gas releases that can potentially raise the tank headspace hydrogen concentration to very near the lower flammability limit. This report describes the theory and detailed physical models for both the supernate decant and jet mixing processes and presents the results from applying the models to these operations in the four tanks. The technical bases for input parameter distributions are elucidated.

Wells, Beric E. (BATTELLE (PACIFIC NW LAB)); Cuta, Judith M. (BATTELLE (PACIFIC NW LAB)); Hartley, Stacey A. (BATTELLE (PACIFIC NW LAB)); Mahoney, Lenna A. (BATTELLE (PACIFIC NW LAB)); Meyer, Perry A. (BATTELLE (PACIFIC NW LAB)); Stewart, Charles W. (BATTELLE (PACIFIC NW LAB))

2002-03-20T23:59:59.000Z

197

Analysis of Induced Gas Releases During Retrieval of Hanford Double-Shell Tank Waste  

DOE Green Energy (OSTI)

Radioactive waste is scheduled to be retrieved from Hanford double-shell tanks AN-103, AN-104, AN-105, and AW-101 to the vitrification plant beginning about 2009. Retrieval may involve decanting the supernatant liquid and/or mixing the waste with jet pumps. In these four tanks, which contain relatively large volumes of retained gas, both of these operations are expected to induce buoyant displacement gas releases that can potentially raise the tank headspace hydrogen concentration to very near the lower flammability limit. This report describes the theory and detailed physical models for both the supernatant decant and jet mixing processes and presents the results from applying the models to these operations in the four tanks. The technical bases for input parameter distributions are elucidated.

Wells, Beric E. (BATTELLE (PACIFIC NW LAB)); Cuta, Judith M. (BATTELLE (PACIFIC NW LAB)); Hartley, Stacey A. (BATTELLE (PACIFIC NW LAB)); Mahoney, Lenna A. (BATTELLE (PACIFIC NW LAB)); Meyer, Perry A. (BATTELLE (PACIFIC NW LAB)); Stewart, Charles W. (BATTELLE (PACIFIC NW LAB))

2002-09-25T23:59:59.000Z

198

Resolution of the nuclear criticality safety issue for the Hanford site high-level waste tanks  

SciTech Connect

This paper describes the approach used to resolve the Nuclear Criticality Safety Issue for the Hanford Site high-level waste tanks. Although operational controls have been in place at the Hanford Site throughout its operating life to minimize the amount of fissile material discarded as waste, estimates of the total amount of plutonium that entered the waste tanks range from 500 to 1,000 kg. Nuclear criticality safety concerns were heightened in 1991 based on a review of waste analysis results and a subsequent U.S. Department of Energy 1399 review of the nuclear criticality program. Although the DOE review team concluded that there was no imminent risk of a criticality at the Hanford Site tank farms, the team also stated its concern regarding the lack of definitive knowledge of the fissile material inventory and distribution within the waste tanks and the lack of sufficient management support for the overall criticality safety program. An in-depth technical review of the nuclear criticality safety of the waste tanks was conducted to develop a defensible technical basis to ensure that waste tanks are subcritical. The review covered all relevant aspects of nuclear criticality safety including neutronics and chemical and physical phenomena of the waste form under aging waste conditions as well as during routine waste management operations. This paper provides a review of the technical basis to support the conclusion that given current plutonium inventories and operating conditions, a nuclear criticality is incredible. The DOE has been requested to close the Nuclear Criticality Safety Issue. The Defense Nuclear Facilities Safety Board is currently reviewing the technicalbasis.

Bratzel, D.R.

1997-01-07T23:59:59.000Z

199

Hanford Tanks Initiative alternate retrieval system demonstrations - final report of testing performed by Grey Pilgrim LLC  

Science Conference Proceedings (OSTI)

A waste retrieval system has been defined to provide a safe and cost-effective solution to the Hanford Tanks Initiative. This system consists of the EMMA robotic manipulator (by GreyPilgrim LLC) and the lightweight Scarifier (by Waterjet Technology, Inc.) powered by a 36-kpsi Jet-Edge diesel powered high pressure pumping system. For demonstration and testing purposes, an air conveyance system was utilized to remove the waste from the simulated tank floor. The EMMA long reach manipulator utilized for this demonstration was 33 feet long. It consisted of 4 hydraulically controlled stages of varying lengths and coupling configurations. T

Berglin, E.J.

1997-07-24T23:59:59.000Z

200

COMPUTATIONAL FLUID DYNAMICS MODELING OF SCALED HANFORD DOUBLE SHELL TANK MIXING - CFD MODELING SENSITIVITY STUDY RESULTS  

SciTech Connect

The primary purpose of the tank mixing and sampling demonstration program is to mitigate the technical risks associated with the ability of the Hanford tank farm delivery and celtification systems to measure and deliver a uniformly mixed high-level waste (HLW) feed to the Waste Treatment and Immobilization Plant (WTP) Uniform feed to the WTP is a requirement of 24590-WTP-ICD-MG-01-019, ICD-19 - Interface Control Document for Waste Feed, although the exact definition of uniform is evolving in this context. Computational Fluid Dynamics (CFD) modeling has been used to assist in evaluating scaleup issues, study operational parameters, and predict mixing performance at full-scale.

JACKSON VL

2011-08-31T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1  

SciTech Connect

The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies.

Dukelow, G.T.; Hanson, G.A. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States)

1995-05-01T23:59:59.000Z

202

Final Environmental Impact Statement for the Tank Waste Remediation System, Hanford Site, Richland, Washington  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

for the Tank Waste Remediation System, Hanford Site, Richland, Washington for the Tank Waste Remediation System, Hanford Site, Richland, Washington file:///I|/Data%20Migration%20Task/EIS-0189-FEIS-Summary-1996.HTM[6/27/2011 11:21:59 AM] The National Environmental Policy Act (NEPA) requires Federal agencies to analyze the potential environmental impacts of their proposed actions to assist them in making informed decisions. A similar Washington State law, the State Environmental Policy Act (SEPA), requires State agencies, including the Washington State Department of Ecology (Ecology), to analyze environmental impacts before making decisions that could impact the environment. A major emphasis of both laws is to promote public awareness of these actions and provide opportunities for public involvement. Because NEPA and SEPA requirements are similar, the U.S. Department of Energy (DOE) and Ecology

203

Effects of Globally Waste Disturbing Activities on Gas Generation, Retention, and Release in Hanford Waste Tanks  

SciTech Connect

Various operations are authorized in Hanford single- and double-shell tanks that disturb all or a large fraction of the waste. These globally waste-disturbing activities have the potential to release a large fraction of the retained flammable gas and to affect future gas generation, retention, and release behavior. This report presents analyses of the expected flammable gas release mechanisms and the potential release rates and volumes resulting from these activities. The background of the flammable gas safety issue at Hanford is summarized, as is the current understanding of gas generation, retention, and release phenomena. Considerations for gas monitoring and assessment of the potential for changes in tank classification and steady-state flammability are given.

Stewart, Charles W.; Fountain, Matthew S.; Huckaby, James L.; Mahoney, Lenna A.; Meyer, Perry A.; Wells, Beric E.

2005-08-02T23:59:59.000Z

204

Review of the Technical Basis of the Hydrogen Control Limit for Operations in Hanford Tank Farms  

DOE Green Energy (OSTI)

The waste in Hanford tanks generates a mixture of flammable gases and releases it into the tank headspace. The potential hazard resulting from flammable gas generation requires that controls be established to prevent ignition and halt operations if gas concentrations reach levels of concern. In cases where only hydrogen is monitored, a control limit of 6,250 ppm hydrogen has been in use at Hanford for several years. The hydrogen-based control limit is intended to conservatively represent 25% of the lower flammability limit of a gas mixture, accounting for the presence of flammable gases other than hydrogen, with ammonia being the primary concern. This report reviews the technical basis of the current control limit based on observed and projected concentrations of hydrogen and ammonia representing a range of gas release scenarios. The conclusion supports the continued use of the current 6,250 ppm hydrogen control limit

Mahoney, Lenna A. (BATTELLE (PACIFIC NW LAB)); Stewart, Charles W. (BATTELLE (PACIFIC NW LAB))

2002-11-30T23:59:59.000Z

205

Caustic Recycle from Hanford Tank Waste Using Large Area NaSICON Structures (LANS)  

Science Conference Proceedings (OSTI)

This report presents the results of a 5-day test of an electrochemical bench-scale apparatus using a proprietary (NAS-GY) material formulation of a (Na) Super Ion Conductor (NaSICON) membrane in a Large Area NaSICON Structures (LANS) configuration. The primary objectives of this work were to assess system performance, membrane seal integrity, and material degradation while removing Na from Group 5 and 6 tank waste from the Hanford Site.

Fountain, Matthew S.; Sevigny, Gary J.; Balagopal, S.; Bhavaraju, S.

2009-03-31T23:59:59.000Z

206

Neutron and Gamma Probe Application to Hanford Tank 241-SY-101  

SciTech Connect

A neutron (moisture-sensitive) and gamma (in-situ radiation) probe technique has been utilized at a number of Hanford radioactive waste tanks for many years. This technology has been adapted for use in tank 241-SY-101's two Multifunction Instrument Trees (MITs) which have a hollow dry-well center opening two inches (51 cm) in diameter. These probes provide scans starting within a few inches of the tank bottom and traversing up through the top of the tank revealing a variety of waste features as a function of tank elevation. These features have been correlated with void fraction data obtained independently from two other devices, the Retained Gas Sampler (RGS) and the Void Fraction Instrument (VFI). The MIT probes offer the advantage of nearly continuous count-rate versus elevation scans and they can be operated significantly more often and at lower cost than temperature probes or the RGS or VFI devices while providing better depth resolution. The waste level in tank 241-SY-101 had been rising at higher rates than expected during 1998 and early 1999 indicating an increasing amount of trapped gas in the waste. The use of the MIT probes has assisted in evaluating changes in crust thickness and level and also in estimating relative changes in gas stored in the crust. This information is important in assuring that the tank remains in a safe configuration and will support safe waste transfer when those operations take place.

CANNON, N.S.

2000-02-01T23:59:59.000Z

207

Nuclear criticality project plan for the Hanford Site tank farms  

SciTech Connect

The mission of this project is to provide a defensible technical basis report in support of the Final Safety Analysis Report (FSAR). This technical basis report will also be used to resolve technical issues associated with the nuclear criticality safety issue. The strategy presented in this project plan includes an integrated programmatic and organizational approach. The scope of this project plan includes the provision of a criticality technical basis supporting document (CTBSD) to support the FSAR as well as for resolution of the nuclear criticality safety issue. Specifically, the CTBSD provides the requisite technical analysis to support the FSAR hazard and accident analysis as well as for the determination of the required FSAR limits and controls. The scope of The CTBSD will provide a baseline for understanding waste partitioning and distribution phenomena and mechanistics for current operational activities inclusive of single-shell tanks, double-shell tanks, double-contained receiver tanks, and miscellaneous underground storage tanks.. Although the FSAR does not include future operational activities, the waste partitioning and distribution phenomena and mechanistics work scope identified in this project plan provide a sound technical basis as a point of departure to support independent safety analyses for future activities. The CTBSD also provides the technical basis for resolution of the technical issues associated with the nuclear criticality safety issue. In addition to the CTBSD, additional documentation will be required to fully resolve U.S. Department of Energy-Headquarters administrative and programmatic issues. The strategy and activities defined in this project plan provide a CTBSD for the FSAR and for accelerated resolution of the safety issue in FY 1996. On April 30, 1992, a plant review committee reviewed the Final Safety Analysis Reports for the single-shell, double-shell, and aging waste tanks in light of the conclusions of the inadequate waste characterization with respect to fissile material. The review indicated that the conclusion in the FSARS, that a criticality is not credible, cannot be supported for a full range of potential tank constituents. Therefore, a USQ was declared. Development of a credible scenario leading to a criticality proved to be extremely difficult, given the paucity of data on the quantity and distribution of fissile material in the tanks. The objective of this project plan is to develop a strategy and technical approach to provide a CTBSD for the FSAR and for resolution of the nuclear criticality safety issue pertaining to tank farm waste storage and transfer operations. The strategy and technical approach identified in this project plan include definition of administrative and technical tasks. Technical analyses will include mechanistic studies, historical data review, and additional limited neutronics analysis. Completion of these studies will be documented in a CTBSD to support the existing criticality technical basis. The CTBSD will be incorporated in the criticality portion of the FSAR.

Bratzel, D.R., Westinghouse Hanford

1996-08-06T23:59:59.000Z

208

Assessment of alternative mitigation concepts for Hanford flammable gas tanks  

Science Conference Proceedings (OSTI)

This report provides a review and assessment of four selected mitigation concepts: pump jet mixing, sonic vibration, dilution, and heating. Though the relative levels of development of these concepts are quite different, some definite conclusions are made on their comparative feasibility. Key findings of this report are as follows. A mixer pump has proven to be a safe and effective active mitigation method in Tank 241-SY-101, and the authors are confident that mixer pumps will effectively mitigate other tanks with comparable waste configurations and properties. Low-frequency sonic vibration is also predicted to be effective for mitigation. Existing data cannot prove that dilution can mitigate gas release event (GRE) behavior. However, dilution is the only concept of the four that potentially offers passive mitigation. Like dilution, heating the waste cannot be proven with available information to mitigate GRE behavior. The designs, analyses, and data from which these conclusions are derived are presented along with recommendations.

Stewart, C.W.; Schienbein, L.A.; Hudson, J.D.; Eschbach, E.J.; Lessor, D.L.

1994-09-01T23:59:59.000Z

209

Hanford site tank waste remediation system programmatic environmental review report  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) committed in the Tank Waste Remediation System (TWRS) Environmental Impact Statement (EIS) Record of Decision (ROD) to perform future National Environmental Policy Act (NEPA) analysis at key points in the Program. Each review will address the potential impacts that new information may have on the environmental impacts presented in the TWRS EIS and support an assessment of whether DOE`s plans for remediating the tank waste are still pursuing the appropriate plan for remediation or whether adjustments to the program are needed. In response to this commitment, DOE prepared a Supplement Analysis (SA) to support the first of these reevaluations. Subsequent to the completion of the SA, the Phase IB negotiations process with private contractors resulted in several changes to the planned approach. These changes along with other new information regarding the TWRS Program have potential implications for Phase 1 and Phase 2 of tank waste retrieval and waste storage and/or disposal that may influence the environmental impacts of the Phased Implementation alternative. This report focuses on identifying those potential environmental impacts that may require NEPA analysis prior to authorization to begin facility construction and operations.

Haass, C.C.

1998-09-03T23:59:59.000Z

210

ALUMINUM REMOVAL AND SODIUM HYDROXIDE REGENERATION FROM HANFORD TANK WASTE BY LITHIUM HYDROTALCITE PRECIPITATION SUMMARY OF PRIOR LAB-SCALE TESTING  

Science Conference Proceedings (OSTI)

Scoping laboratory scale tests were performed at the Chemical Engineering Department of the Georgia Institute of Technology (Georgia Tech), and the Hanford 222-S Laboratory, involving double-shell tank (DST) and single-shell tank (SST) Hanford waste simulants. These tests established the viability of the Lithium Hydrotalcite precipitation process as a solution to remove aluminum and recycle sodium hydroxide from the Hanford tank waste, and set the basis of a validation test campaign to demonstrate a Technology Readiness Level of 3.

SAMS TL; GUILLOT S

2011-01-27T23:59:59.000Z

211

Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks  

DOE Green Energy (OSTI)

This report discusses concerns safety issues, and management at Hanford Tank Farm. Concerns center on the issue of flammable gas generation which could ignite, and on possible exothermic reactions of ferrocyanide compounds which were added to single shell tanks in the 1950's. It is believed that information concerning these issues has been mis-handled and the problems poorly managed. (CBS)

Not Available

1990-07-01T23:59:59.000Z

212

Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities  

Science Conference Proceedings (OSTI)

This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant.

JULYK, L.J.

1999-09-22T23:59:59.000Z

213

Research on jet mixing of settled sludges in nuclear waste tanks at Hanford and other DOE sites: A historical perspective  

SciTech Connect

Jet mixer pumps will be used in the Hanford Site double-shell tanks to mobilize and mix the settled solids layer (sludge) with the tank supernatant liquid. Predicting the performance of the jet mixer pumps has been the subject of analysis and testing at Hanford and other U.S. Department of Energy (DOE) waste sites. One important aspect of mixer pump performance is sludge mobilization. The research that correlates mixer pump design and operation with the extent of sludge mobilization is the subject of this report. Sludge mobilization tests have been conducted in tanks ranging from 1/25-scale (3 ft-diameter) to full scale have been conducted at Hanford and other DOE sites over the past 20 years. These tests are described in Sections 3.0 and 4.0 of this report. The computational modeling of sludge mobilization and mixing that has been performed at Hanford is discussed in Section 5.0.

Powell, M.R.; Onishi, Y.; Shekarriz, R.

1997-09-01T23:59:59.000Z

214

Functions and requirements for Hanford single-shell tank leakage detection and monitoring  

SciTech Connect

This document provides the initial functions and requirements for leakage detection and monitoring applicable to past and potential future leakage from the Hanford Site`s 149 single-shell high-level waste tanks. This mission is a part of the overall mission of the Westinghouse Hanford Company Tank Waste Remediation System division to remediate the tank waste in a safe and acceptable manner. Systems engineering principles are being applied to this effort. This document reflects the an initial step in the systems engineering approach to decompose the mission into primary functions and requirements. The document is considered approximately 30% complete relative to the effort required to produce a final version that can be used to support demonstration and/or procurement of technologies. The functions and requirements in this document apply to detection and monitoring of below ground leaks from SST containment boundaries and the resulting soil contamination. Leakage detection and monitoring is invoked in the TWRS Program in three fourth level functions: (1) Store Waste, (2) Retrieve Waste, and (3) Disposition Excess Facilities (as identified in DOE/RL-92-60 Rev. 1, Tank Waste Remediation System Functions and Requirements).

Cruse, J.M.; Ohl, P.C.

1995-04-19T23:59:59.000Z

215

Thermodynamic Model for Uranium Release from Hanford Site Tank Residual Waste  

Science Conference Proceedings (OSTI)

A thermodynamic model of U phase solubility and paragenesis was developed for Hanford tank residual waste that will remain after tank closure. The model was developed using a combination of waste composition data, waste leach test data, and thermodynamic modeling of the leach test data. The testing and analyses were conducted using actual Hanford tank residual waste. Positive identification of the U phases by X-ray diffraction (XRD) was generally not possible because solids in the waste were amorphous, or below the detection limit of XRD for both as-received residual waste and leached residual waste. Three leachant solutions were used in the studies, dionized water, CaCO3 saturated solution, and Ca(OH)2 saturated solution. Thermodynamic modeling verified that equilibrium between U phases in the initial residual waste samples and the leachants was attained in less than a month. The paragenetic sequence of secondary phases that occur as waste leaching progresses for two closure scenarios was identified. These results have significant implications for tank closure design.

Cantrell, Kirk J.; Deutsch, William J.; Lindberg, Michael J.

2011-01-26T23:59:59.000Z

216

Ammonia in simulated Hanford double-shell tank wastes: Solubility and effects on surface tension  

Science Conference Proceedings (OSTI)

Radioactive and wastes left from defense materials production activities are temporarily stored in large underground tanks at the Hanford Site in south central Washington State (Tank Waste Science Panel 1991). Some of these wastes are in the form of a thick slurry (``double-shell slurry``) containing sodium nitrate, sodium nitrite, sodium aluminate, sodium hydroxide, sodium carbonate, organic complexants and buffering agents, complexant fragments and other minor components (Herting et al. 1992a; Herting et al. 1992b; Campbell et al. 1994). As a result of thermal and radiolytic processes, a number of gases are known to be produced by some of these stored wastes, including ammonia, nitrous oxide, nitrogen, hydrogen, and methane (Babad et al. 1991; Ashby et al. 1992; Meisel et al. 1993; Ashby et al. 1993; Ashby et al. 1994; Bryan et al. 1993; US Department of Energy 1994). Before the emplacement of a mixer pump, these gases were retained in and periodically released from Tank 241-SY-101, a double-shell tank at the Hanford Site (Babad et al. 1992; US Department of Energy 1994). Gases are believed to be retained primarily in the form of bubbles attached to solid particles (Bryan, Pederson, and Scheele 1992), with very little actually dissolved in the liquid. Ammonia is an exception. The relation between the concentration of aqueous ammonia in such concentrated, caustic mixtures and the ammonia partial pressure is not well known, however.

Norton, J.D.; Pederson, L.R.

1994-09-01T23:59:59.000Z

217

Regulatory Closure Options for the Residue in the Hanford Site Single-Shell Tanks  

SciTech Connect

Liquid, mixed, high-level radioactive waste (HLW) has been stored in 149 single-shell tanks (SSTS) located in tank farms on the U.S. Department of Energy's (DOE's) Hanford Site. The DOE is developing technologies to retrieve as much remaining HLW as technically possible prior to physically closing the tank farms. In support of the Hanford Tanks Initiative, Sandia National Laboratories has addressed the requirements for the regulatory closure of the radioactive component of any SST residue that may remain after physical closure. There is significant uncertainty about the end state of each of the 149 SSTS; that is, the nature and amount of wastes remaining in the SSTS after retrieval is uncertain. As a means of proceeding in the face of these uncertainties, this report links possible end-states with associated closure options. Requirements for disposal of HLW and low-level radioactive waste (LLW) are reviewed in detail. Incidental waste, which is radioactive waste produced incidental to the further processing of HLW, is then discussed. If the low activity waste (LAW) fraction from the further processing of HLW is determined to be incidental waste, then DOE can dispose of that incidental waste onsite without a license from the U.S. Nuclear Regulatory Commissions (NRC). The NRC has proposed three Incidental Waste Criteria for determining if a LAW fraction is incidental waste. One of the three Criteria is that the LAW fraction should not exceed the NRC's Class C limits.

Cochran, J.R. Shyr, L.J.

1998-10-05T23:59:59.000Z

218

Initial Selection of Supplemental Treatment Technologies for Hanford's Low-Activity Tank Waste  

Science Conference Proceedings (OSTI)

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years (DOE 2002). A key element of the accelerated cleanup plan was a strategic initiative for acceleration of the tank waste program and completion of "tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (ETP) and using supplemental technologies for waste treatment and immobilization." The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). The objective was to complete required testing and evaluation that would "...bring an appropriate combination of the above technologies to deployment to supplement LAW treatment and immobilization in the WTP to achieve the completion of tank waste treatment by 2028." In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology have proposed to accelerate from 2012 to 2005 the Hanford Federal Facility Compliance Agreement (Tri-Party Agreement) milestone (M-62-08) associated with a final decision on treatment of the balance of tank waste that is beyond the capacity of the currently designed WTP.

Raymond, Richard E.; Powell, Roger W.; Hamilton, Dennis W.; Kitchen, William A.; Mauss, Billie M.; Brouns, Thomas M.

2004-07-15T23:59:59.000Z

219

Discovery of the First Leaking Double-Shell Tank - Hanford Tank 241-AY-102-14222  

SciTech Connect

A routine video inspection of the annulus space between the primary tank and secondary liner of double-shell tank 241-AY-102 was performed in August 2012. During the inspection, unexpected material was discovered. A subsequent video inspection revealed additional unexpected material on the opposite side of the tank, none of which had been observed during inspections performed in December 2006 and January 2007. A formal leak assessment team was established to review the tank's construction and operating histories, and preparations for sampling and analysis began to determine the material's origin. A new sampling device was required to collect material from locations that were inaccessible to the available sampler. Following its design and fabrication, a mock-up test was performed for the new sampling tool to ensure its functionality and capability of performing the required tasks. Within three months of the discovery of the unexpected material, sampling tools were deployed, material was collected, and analyses were performed. Results indicated that some of the unknown material was indicative of soil, whereas the remainder was consistent with tank waste. This, along with the analyses performed by the leak assessment team on the tank's construction history, lead to the conclusion that the primary tank was leaking into the annulus. Several issues were encountered during the deployment of the samplers into the annulus. As this was the first time samples had been required from the annulus of a double-shell tank, a formal lessons learned was created concerning designing equipment for unique purposes under time constraints.

Harrington, Stephanie J.; Sams, Terry L.

2013-11-06T23:59:59.000Z

220

Hanford Tank 241-C-106: Residual Waste Contaminant Release Model and Supporting Data  

SciTech Connect

This report was revised in May 2007 to correct values in Section 3.4.1.7, second paragraph, last sentence; 90Sr values in Tables 3.22 and 3.32; and 99Tc values Table 4.3 and in Chapter 5. In addition, the tables in Appendix F were updated to reflect corrections to the 90Sr values. The rest of the text remains unchanged from the original report issued in May 2005. CH2M HILL is producing risk/performance assessments to support the closure of single-shell tanks at the DOE's Hanford Site. As part of this effort, staff at PNNL were asked to develop release models for contaminants of concern that are present in residual sludge remaining in tank 241-C-106 (C-106) after final retrieval of waste from the tank. This report provides the information developed by PNNL.

Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

2007-05-23T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

STEADY-STATE FLAMMABLE GAS RELEASE RATE CALCULATION AND LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE  

SciTech Connect

Assess the steady-state flammability level at normal and off-normal ventilation conditions. The methodology of flammability analysis for Hanford tank waste is developed. The hydrogen generation rate model was applied to calculate the gas generation rate for 177 tanks. Flammability concentrations and the time to reach 25% and 100% of the lower flammability limit, and the minimum ventilation rate to keep from 100 of the LFL are calculated for 177 tanks at various scenarios.

HU TA

2007-10-26T23:59:59.000Z

222

Chemistry of application of calcination/dissolution to the Hanford tank waste inventory  

SciTech Connect

Approximately 330,000 metric tons of sodium-rich radioactive waste originating from separation of plutonium from irradiated uranium fuel are stored in underground tanks at the Hanford Site in Washington State. Fractionation of the waste into low-level waste (LLW) and high-level waste (HLW) streams is envisioned via partial water dissolution and limited radionuclide extraction operations. Under optimum conditions, LLW would contain most of the chemical bulk while HLW would contain virtually all of the transuranic and fission product activity. Calcination at around 850 C, followed by water dissolution, has been proposed as an alternative initial treatment of Hanford Site waste to improve waste dissolution and the envisioned LLW/HLW split. Results of literature and laboratory studies are reported on the application of calcination/dissolution (C/D) to the fractionation of the Hanford Site tank waste inventory. Both simulated and genuine Hanford Site waste materials were used in the lab tests. To evaluation confirmed that C/D processing reduced the amount of several components from the waste. The C/D dissolutions of aluminum and chromium allow redistribution of these waste components from the HLW to the LLW fraction. Comparisons of simple water-washing with C/D processing of genuine Hanford Site waste are also reported based on material (radionuclide and chemical) distributions to solution and solid residue phases. The lab results show that C/D processing yielded superior dissolution of aluminum and chromium sludges compared to simple water dissolution. 57 refs., 26 figs., 18 tabs.

Delegard, C.H.; Elcan, T.D.; Hey, B.E.

1994-05-01T23:59:59.000Z

223

HIGH-LEVEL WASTE FEED CERTIFICATION IN HANFORD DOUBLE-SHELL TANKS  

SciTech Connect

The ability to effectively mix, sample, certify, and deliver consistent batches of High Level Waste (HLW) feed from the Hanford Double Shell Tanks (DST) to the Waste Treatment and Immobilization Plant (WTP) presents a significant mission risk with potential to impact mission length and the quantity of HLW glass produced. DOE's River Protection Project (RPP) mission modeling and WTP facility modeling assume that individual 3785 cubic meter (l million gallon) HLW feed tanks are homogenously mixed, representatively sampled, and consistently delivered to the WTP. It has been demonstrated that homogenous mixing ofHLW sludge in Hanford DSTs is not likely achievable with the baseline design thereby causing representative sampling and consistent feed delivery to be more difficult. Inconsistent feed to the WTP could cause additional batch-to-batch operational adjustments that reduce operating efficiency and have the potential to increase the overall mission length. The Hanford mixing and sampling demonstration program will identify DST mixing performance capability, will evaluate representative sampling techniques, and will estimate feed batch consistency. An evaluation of demonstration program results will identify potential mission improvement considerations that will help ensure successful mission completion. This paper will discuss the history, progress, and future activities that will define and mitigate the mission risk.

THIEN MG; WELLS BE; ADAMSON DJ

2010-01-14T23:59:59.000Z

224

The Continued Need for Modeling and Scaled Testing to Advance the Hanford Tank Waste Mission  

SciTech Connect

Hanford tank wastes are chemically complex slurries of liquids and solids that can exhibit changes in rheological behavior during retrieval and processing. The Hanford Waste Treatment and Immobilization Plant (WTP) recently abandoned its planned approach to use computational fluid dynamics (CFD) supported by testing at less than full scale to verify the design of vessels that process these wastes within the plant. The commercial CFD tool selected was deemed too difficult to validate to the degree necessary for use in the design of a nuclear facility. Alternative, but somewhat immature, CFD tools are available that can simulate multiphase flow of non-Newtonian fluids. Yet both CFD and scaled testing can play an important role in advancing the Hanford tank waste missionin supporting the new verification approach, which is to conduct testing in actual plant vessels; in supporting waste feed delivery, where scaled testing is ongoing; as a fallback approach to design verification if the Full Scale Vessel Testing Program is deemed too costly and time-consuming; to troubleshoot problems during commissioning and operation of the plant; and to evaluate the effects of any proposed changes in operating conditions in the future to optimize plant performance.

Peurrung, Loni M.; Fort, James A.; Rector, David R.

2013-09-03T23:59:59.000Z

225

Potential for criticality in Hanford tanks resulting from retrieval of tank waste  

SciTech Connect

This report assesses the potential during retrieval operations for segregation and concentration of fissile material to result in a criticality. The sluicing retrieval of C-106 sludge to AY-102 and the operation of mixer pumps in SY-102 are examined in some detail. These two tanks (C-106, SY-102) were selected because of the near term plans for retrieval of these tanks and their high plutonium inventories relative to other tanks. Although all underground storage tanks are subcritical by a wide margin if assumed to be uniform in composition, the possibility retrieval operations could preferentially segregate the plutonium and locally concentrate it sufficiently to result in criticality was a concern. This report examines the potential for this segregation to occur.

Whyatt, G.A.; Sterne, R.J.; Mattigod, S.V. [and others

1996-09-01T23:59:59.000Z

226

Technology Review of Nondestructive Methods for Examination of Water Intrusion Areas on Hanfords Double-Shell Waste Tanks  

Science Conference Proceedings (OSTI)

Under a contract with CH2M Hill Hanford Group, Inc., PNNL has performed a review of the NDE technology and methods for examination of the concrete dome structure of Hanfords double-shell tanks. The objective was to provide a matrix of methodologies that could be evaluated based on applicability, ease of deployment, and results that could provide information that could be used in the ongoing structural analysis of the tank dome. PNNL performed a technology evaluation with the objective of providing a critical literature review for all applicable technologies based on constraints provided by CH2M HILL. These constraints were not mandatory, but were desired. These constraints included performing the evaluation without removing any soil from the top of the tank, or if necessary, requesting that the hole diameter needed to gain access to evaluate the top of the tank structure to be no greater than approximately 12-in. in diameter. PNNL did not address the details of statistical sampling requirements as they depend on an unspecified risk tolerance. PNNL considered these during the technology evaluation and have reported the results in the remainder of this document. Many of the basic approaches to concrete inspection that were reviewed in previous efforts are still in use. These include electromagnetic, acoustic, radiographic, etc. The primary improvements in these tools have focused on providing quantitative image reconstruction, thus providing inspectors and analysts with three-dimensional data sets that allow for operator visualization of relevant abnormalities and analytical integration into structural performance models. Available instruments, such as radar used for bridge deck inspections, rely on post-processing algorithms and do not provide real-time visualization. Commercially available equipment only provides qualitative indications of relative concrete damage. It cannot be used as direct input for structural analysis to assess fitness for use and if necessary to de-rate critical components. There are currently no tools that automatically convert the NDE data to formats compatible with structural analysis programs. While radiographic techniques still provide significant advantages in spatial resolution, non-ionizing techniques are still preferred. Radar imagining in the 15 GHz has become the most useful. Unfortunately the algorithms and underlying assumptions used in these reconstructions are proprietary, and it is not possible to assess the quality and limitations of the analytical methods used to generate the derived structural data. The hypothesis that water intrusion may contribute to potential rebar corrosion of the tank domes provided the primary guidance in reviewing and evaluating available NDE technologies. Of primary concern is the need to employ technologies that provide the best opportunity for visualizing the rebar and providing quantitative data that can be integrated into structural analysis efforts to better understand and quantify the structural capacity of the domes. The conclusion is that an imaging system capable of locating and quantifying the distribution and conditions of the cement, aggregate, and rebar will provide the most valuable baseline upon which to build a case for the integrity of the structure. If successful, such a system would fulfill the need to incorporate valuable data into current structural load capacity analysis.

Watkins, Michael L.; Pardini, Allan F.

2008-05-09T23:59:59.000Z

227

Mechanisms of gas bubble retention and release: results for Hanford Waste Tanks 241-S-102 and 241-SY-103 and single-shell tank simulants  

DOE Green Energy (OSTI)

Research at Pacific Northwest National Laboratory (PNNL) has probed the physical mechanisms and waste properties that contribute to the retention and release of flammable gases from radioactive waste stored in underground tanks at Hanford. This study was conducted for Westinghouse Hanford Company as part of the PNNL Flammable Gas Project. The wastes contained in the tanks are mixes of radioactive and chemical products, and some of these wastes are known to generate mixtures of flammable gases, including hydrogen, nitrous oxide, and ammonia. Because these gases are flammable, their retention and episodic release pose a number of safety concerns.

Gauglitz, P.A.; Rassat, S.D.; Bredt, P.R.; Konynenbelt, J.H.; Tingey, S.M.; Mendoza, D.P.

1996-09-01T23:59:59.000Z

228

Characterization and Potential Remediation Approaches for Vadose Zone Contamination at Hanford 241-SX Tank Farm  

Science Conference Proceedings (OSTI)

Unplanned releases of radioactive and hazardous wastes have occurred at the 241-SX Tank Farm on the U.S. Department of Energy Hanford Site in southeast Washington State. Interim and long-term mitigation efforts are currently under evaluation for 241-SX Tank Farm. Two contiguous interim surface barriers have been designed for deployment at 241-SX Tank Farm to reduce future moisture infiltration; however, construction of the surface barriers has been deferred to allow testing of alternative technologies for soil moisture reduction and possibly contaminant source term reduction. Previous tests performed by other organizations at the Hanford Site have demonstrated that: vadose zone desiccation using large diameter (greater than 4 inch) boreholes is feasible; under certain circumstances, mobile contaminants may be removed in addition to water vapor; and small diameter (approximately 2 inch) boreholes (such as those placed by the direct push hydraulic hammer) can be used to perform vapor extractions. Evaluation of the previous work combined with laboratory test results have led to the design of a field proof-of-principle test to remove water and possibly mobile contaminants at greater depths, using small boreholes placed with the direct push unit.

Eberlein, Susan J.; Sydnor, Harold A.; Parker, Danny L.; Glaser, Danney R.

2013-01-10T23:59:59.000Z

229

Ostwald Ripening and Its Effect on PuO2 Particle Size in Hanford Tank Waste  

Science Conference Proceedings (OSTI)

Between 1944 and 1989, the Hanford Site produced 60 percent (54.5 metric tons) of the United States weapons plutonium and produced an additional 12.9 metric tons of fuels-grade plutonium. High activity wastes, including plutonium lost from the separations processes used to isolate the plutonium, were discharged to underground storage tanks during these operations. Plutonium in the Hanford tank farms is estimated to be {approx}700 kg but may be up to {approx}1000 kg. Despite these apparent large quantities, the average plutonium concentration in the {approx}200 million liter tank waste volume is only about 0.003 grams per liter ({approx}0.0002 wt%). The plutonium is largely associated with low solubility metal hydroxide/oxide sludges where its low concentration and intimate mixture with neutron-absorbing elements (e.g., iron) are credited in nuclear criticality safety. However, concerns have been expressed that plutonium, in the form of plutonium hydrous oxide, PuO{sub 2} {center_dot} xH{sub 2}O, could undergo sufficient crystal growth through Ostwald ripening in the alkaline tank waste to potentially be separable from neutron absorbing constituents by settling or sedimentation. It was found that plutonium that entered the alkaline tank waste by precipitation through neutralization from acid solution is initially present as 2- to 3-nm (0.002- to 0.003-{mu}m) scale PuO{sub 2} {center_dot} xH{sub 2}O crystallite particles and grows from that point at exceedingly slow rates, posing no risk to physical segregation. These conclusions are reached by both general considerations of Ostwald ripening and specific observations of the behaviors of PuO{sub 2} and PuO{sub 2} {center_dot} xH{sub 2}O upon aging in alkaline solution.

Delegard, Calvin H.

2011-09-29T23:59:59.000Z

230

Simulant Development for Hanford Double-Shell Tank Mixing and Waste Feed Delivery Testing  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy Office of River Projection manages the River Protection Project, which has the mission to retrieve and treat the Hanford tank waste for disposal and close the tank farms (Certa et al. 2011). Washington River Protection Solutions, LLC (WRPS) is responsible for a primary objective of this mission which is to retrieve and transfer tank waste to the Hanford Waste Treatment and Immobilization Plant (WTP). A mixing and sampling program with four separate demonstrations is currently being conducted to support this objective and also to support activities in a plan for addressing safety concerns identified by the Defense Nuclear Facilities Safety Board related to the ability of the WTP to mix, sample, and transfer fast settling particles. Previous studies have documented the objectives, criteria, and selection of non-radioactive simulants for these four demonstrations. The identified simulants include Newtonian suspending liquids with densities and viscosities that span the range expected in waste feed tanks. The identified simulants also include non-Newtonian slurries with Bingham yield stress values that span a range that is expected to bound the Bingham yield stress in the feed delivery tanks. The previous studies identified candidate materials for the Newtonian and non-Newtonian suspending fluids, but did not provide specific recipes for obtaining the target properties and information was not available to evaluate the compatibility of the fluids and particles or the potential for salt precipitation at lower temperatures. The purpose of this study is to prepare small batches of simulants in advance of the demonstrations to determine specific simulant recipes, to evaluate the compatibility of the liquids and particles, and to determine if the simulants are stable for the potential range of test temperatures. The objective of the testing, which is focused primarily on the Newtonian and non-Newtonian fluids, is to determine the composition of simulant materials that give the desired density and viscosity or rheological parameters.

Gauglitz, Phillip A.; Tran, Diana N.; Buchmiller, William C.

2012-09-24T23:59:59.000Z

231

Evaluation of the potential for significant ammonia releases from Hanford waste tanks  

DOE Green Energy (OSTI)

Ammonia is ubiquitous as a component of the waste stored in the Hanford Site single-shell tanks (SSTs) and double-shell tanks (DSTs). Because ammonia is both flammable and toxic, concerns have been raised about the amount of ammonia stored in the tanks and the possible mechanisms by which it could be released from the waste into the head space inside the tanks as well as into the surrounding atmosphere. Ammonia is a safety issue for three reasons. As already mentioned, ammonia is a flammable gas and may contribute to a flammability hazard either directly, if it reaches a high enough concentration in the tank head space, or by contributing to the flammability of other flammable gases such as hydrogen (LANL 1994). Ammonia is also toxic and at relatively low concentrations presents a hazard to human health. The level at which ammonia is considered Immediately Dangerous to Life or Health (IDLH) is 300 ppm (WHC 1993, 1995). Ammonia concentrations at or above this level have been measured inside the head space in a number of SSTs. Finally, unlike hydrogen and nitrous oxide, ammonia is highly soluble in aqueous solutions, and large amounts of ammonia can be stored in the waste as dissolved gas. Because of its high solubility, ammonia behaves in a qualitatively different manner from hydrogen or other insoluble gases. A broader range of scenarios must be considered in modeling ammonia storage and release.

Palmer, B.J.; Anderson, C.M.; Chen, G.; Cuta, J.M.; Ferryman, T.A.; Terrones, G.

1996-07-01T23:59:59.000Z

232

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT BUCKLING EVALUATION METHODS AND RESULTS FOR THE PRIMARY TANKS  

SciTech Connect

This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste facility (AWF) primary tank ventilation system. The current buckling review focuses on the following tasks: (1) Evaluate the potential for progressive anchor bolt failure and the appropriateness of the safety factors that were used for evaluating local and global buckling. The analysis will specifically answer the following questions: (a) Can the EH-22 scenario develop if the vacuum is limited to -6.6-inch water gage (w.g.) by a relief valve? (b) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario can develop? (c) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario cannot develop? (2) Develop influence functions to estimate the axial stresses in the primary tanks for all reasonable combinations of tank loads based on detailed finite element analysis. The analysis must account for the variation in design details and operating conditions between the different DSTs. The analysis must also address the imperfection sensitivity of the primary tank to buckling. (3) Perform a detailed buckling analysis to determine the maximum allowable differential pressure for each of the DST primary tanks at the current specified limits on waste temperature, height, and specific gravity. Based on the concrete anchor bolt loads analysis and the small deformations that are predicted at the unfactored limits on vacuum and axial loads, it is very unlikely that the EH-22 scenario (i.e., progressive anchor bolt failure leading to global buckling of the tank under increased vacuum) could occur. After releasing Revision 0 of this report, an independent review of the Double Shell Tanks (DST) Thermal and Operating Loads Analysis (TaLA) combined with the Seismic Analysis was conducted by Dr. Robert P. Kennedy of RPK Structural Mechanics Consulting and Dr. Anestis S. Veletsos of Rice University. Revision I was then issued to address their review comments (included in Appendix D). Additional concerns involving the evaluation of concrete anchor loads and allowables were found during a second review by Drs. Kennedy and Veletsos (see Appendix G). Extensive additional analysis was performed on the anchors, which is detailed by Deibler et al. (2008a, 2008b). The current report (Revision 2) references this recent work, and additional analysis is presented to show that anchor loads do not concentrate significantly in the presence of a local buckle.

MACKEY TC; JOHNSON KI; DEIBLER JE; PILLI SP; RINKER MW; KARRI NK

2009-01-14T23:59:59.000Z

233

USE OF STREAM ANALYZER FOR SOLUBILITY PREDICTIONS OF SELECTED HANFORD TANK WASTE  

SciTech Connect

The Hanford Tank Waste Operations Simulator (HTWOS) models the mission to manage, retrieve, treat and vitrify Hanford waste for long-term storage and disposal. HTWOS is a dynamic, flowsheet, mass balance model of waste retrieval and treatment activities. It is used to evaluate the impact of changes on long-term mission planning. The project is to create and evaluate the integrated solubility model (ISM). The ISM is a first step in improving the chemistry basis in HTWOS. On principal the ISM is better than the current HTWOS solubility. ISM solids predictions match the experimental data well, with a few exceptions. ISM predictions are consistent with Stream Analyzer predictions except for chromium. HTWOS is producing more realistic results with the ISM.

PIERSON KL; BELSHER JD; HO QT

2012-11-02T23:59:59.000Z

234

HANFORD TANK CLEANUP UPDATE MAY 2009 [VISIT US AT WWW.WRPSTOC.COM OR WWW.HANFORD.GOV/ORP/ FOR MORE INFORMATION  

SciTech Connect

Retrieval of waste from single-shell tank C-110 resumed in January making it the first waste retrieval operation for WRPS since taking over Hanford's Tank Operations Contract last October. Now, with approximately 90 percent of the waste removed, WRPS believes that modified sluicing has reached the limits of the technology to remove any further waste and is preparing documentation for use in decision making about any future retrieval actions. Tank C-110 is located in C Fann near the center of the Hanford Site. It is a 530,000 gallon tank, built in 1946, and held approximately 126,000 gallons of sludge and other radioactive and chemical waste materials when retrieval resumed. Modified sluicing technology uses liquid waste from a nearby double-shell tank to break up, dissolve and mobilize the solid material so it can be pumped. Because of the variety of waste fon11S, sluicing is often not able to remove all of the waste. The remaining waste will next be sampled for analysis, and results will be used to guide decisions regarding future actions. Work is moving rapidly in preparation to retrieve waste from a second single-shell tank this summer and transfer it to safer double-shell tank storage. Construction activities necessary to retrieve waste from Tank C-104, a 530,000 gallon tank built in 1943, are approximately 60 percent complete as WRPS maintains its focus on reducing the risk posed by Hanford's aging single-shell waste tanks. C-104 is one of Hanford's oldest radioactive and chemical waste storage tanks, containing approximately 263,000 gallons of wet sludge with a top layer that is dry and powdery. This will be the largest sludge volume retrieval ever attempted using modified sluicing technology. Modified sluicing uses high pressure water or liquid radioactive waste sprayed from nozzles above the waste. The liquid dissolves and/or mobilizes the waste so it can be pumped. In addition to other challenges, tank C-104 contains a significant amount of plutonium and uranium. It also contains a host of contaminated legacy equipment so the entire process is being managed carefully to protect workers and the environment.

HOLLOWAY JN

2009-05-03T23:59:59.000Z

235

Hanford  

NLE Websites -- All DOE Office Websites (Extended Search)

Hanford Cleanup Site The Hanford Site mission focuses on environmental restoration, waste management, related scientific and environmental research and development of radioactive...

236

Radwaste Desk Reference  

Science Conference Proceedings (OSTI)

This volume of the Radwaste Desk Reference contains fundamental practical and regulatory information on the transportation of radioactive waste. Because its information is based entirely on industry practice, the work can serve as an extensive how-to manual for both the newcomer and the experienced radwaste professional.

2011-07-28T23:59:59.000Z

237

AN EVALUATION OF HANFORD SITE TANK FARM SUBSURFACE CONTAMINATION FY2007  

Science Conference Proceedings (OSTI)

The Tank Farm Vadose Zone (TFVZ) Project conducts activities to characterize and analyze the long-term environmental and human health impacts from tank waste releases to the vadose zone. The project also implements interim measures to mitigate impacts, and plans the remediation of waste releases from tank farms and associated facilities. The scope of this document is to report data needs that are important to estimating long-term human health and environmental risks. The scope does not include technologies needed to remediate contaminated soils and facilities, technologies needed to close tank farms, or management and regulatory decisions that will impact remediation and closure. This document is an update of ''A Summary and Evaluation of Hanford Site Tank Farm Subsurface Contamination''. That 1998 document summarized knowledge of subsurface contamination beneath the tank farms at the time. It included a preliminary conceptual model for migration of tank wastes through the vadose zone and an assessment of data and analysis gaps needed to update the conceptual model. This document provides a status of the data and analysis gaps previously defined and discussion of the gaps and needs that currently exist to support the stated mission of the TFVZ Project. The first data-gaps document provided the basis for TFVZ Project activities over the previous eight years. Fourteen of the nineteen knowledge gaps identified in the previous document have been investigated to the point that the project defines the current status as acceptable. In the process of filling these gaps, significant accomplishments were made in field work and characterization, laboratory investigations, modeling, and implementation of interim measures. The current data gaps are organized in groups that reflect Components of the tank farm vadose zone conceptual model: inventory, release, recharge, geohydrology, geochemistry, and modeling. The inventory and release components address residual wastes that will remain in the tanks and tank-farm infrastructure after closure and potential losses from leaks during waste retrieval. Recharge addresses the impacts of current conditions in the tank farms (i.e. gravel covers that affect infiltration and recharge) as well as the impacts of surface barriers. The geohydrology and geochemistry components address the extent of the existing subsurface contaminant inventory and drivers and pathways for contaminants to be transported through the vadose zone and groundwater. Geochemistry addresses the mobility of key reactive contaminants such as uranium. Modeling addresses conceptual models and how they are simulated in computers. The data gaps will be used to provide input to planning (including the upcoming C Farm Data Quality Objective meetings scheduled this year).

MANN, F.M.

2007-07-10T23:59:59.000Z

238

Assessment of New Calculation Method for Toxicological Sums-of-Fractions for Hanford Tank Farm Wastes  

SciTech Connect

The toxicological source terms used for potential accident assessment in the Hanford Tank Farms DSA are based on toxicological sums-of-fractions (SOFs) that were calculated based on the Best Basis Inventory (BBI) from May 2002, using a method that depended on thermodynamic equilibrium calculations of the compositions of liquid and solid phases. The present report describes a simplified SOF-calculation method that is to be used in future toxicological updates and assessments and compares its results (for the 2002 BBI) to those of the old method.

Mahoney, Lenna A.

2006-10-18T23:59:59.000Z

239

Technical basis for classification of low-activity waste fraction from Hanford site tanks  

SciTech Connect

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Petersen, C.A.

1996-09-20T23:59:59.000Z

240

Collaboration, Automation, and Information Management at Hanford High Level Radioactive Waste (HLW) Tank Farms - 14210  

Science Conference Proceedings (OSTI)

Washington River Protection Solutions (WRPS), operator of High Level Radioactive Waste (HLW) Tank Farms at the Hanford Site, is taking an over 20-year leap in technology, replacing systems that were monitored with clipboards and obsolete computer systems, as well as solving major operations and maintenance hurdles in the area of process automation and information management. While WRPS is fully compliant with procedures and regulations, the current systems are not integrated and do not share data efficiently, hampering how information is obtained and managed.

Aurah, Mirwaise Y.; Roberts, Mark A.

2013-12-12T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

INITIAL SELECTION OF SUPPLEMENTAL TREATMENT TECHNOLOGIES FOR HANFORDS LOW ACTIVITY TANK WASTE  

SciTech Connect

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology proposed to accelerate--from 2014 to 2006--the Hanford Federal Facility Agreement and Consent Order milestone (M-62-11) associated with a final decision on the balance of tank waste that is beyond the capacity of the WTP. The DOE Office of River Protection tank farm contractor, CH2M HILL Hanford Group, Inc. (CH2M HILL), was tasked with testing and evaluating selected supplemental technologies to support final decisions on tank waste treatment. Three technologies and corresponding vendors were selected to support an initial technology selection in 2003. The three technologies were containerized grout called cast stone (Fluor Federal Services); bulk vitrification (AMEC Earth and Environmental, Inc.); and steam reforming (THOR Treatment Technologies, LLC.). The cast stone process applies an effective grout waste formulation to the LAW and places the cement-based product in a large container for solidification and disposal. Unlike the WTP LAW treatment, which applies vitrification within continuous-fed joule-heated ceramic melters, bulk vitrification produces a glass waste form using batch melting within the disposal container. Steam reforming produces a granular denitrified mineral waste form using a high-temperature fluidized bed process. An initial supplemental technology selection was completed in December 2003, enabling DOE and CH2M HILL to focus investments in 2004 on the testing and production-scale demonstrations needed to support the 2006 milestone.

RAYMOND, R.E.

2004-02-20T23:59:59.000Z

242

Office of River Protection (DOE-ORP) Hanford Tank Waste Treatment Alternatives March 2000  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) is currently planning to retrieve, pretreat, immobilize and safely dispose of 53 million gallons of highly radioactive waste currently stored in underground tanks at Hanford Site. The DOE plan is a two-phased approach to privatizing the processing of hazardous and radioactive waste. Phase 1 is a proof-of-concept/commercial demonstration-scale effort whose objectives are to: demonstrate, the technical and business viability of using privatized facilities to treat Hanford tank waste; define and maintain required levels of radiological, nuclear, process and occupational safety; maintain environmental protection and compliance; and substantially reduce life-cycle costs and time required to treat Hanford tank waste. The Phase 1 effort consists of Part A and Part B. On September 25, 1996 (Reference 1), DOE signed a contract with BNFL, Inc. (BNFL) to commence with Phase 1, Part A. In August 1998, BNFL was authorized to proceed with Phase I, Part 6-1, a 24-month design phase that will-provide sufficient engineering and financial maturity to establish fixed-unit prices and financing terms for tank waste processing services in privately-owned and -operated facilities. By August 2000, DOE will decide whether to authorize BNFL to proceed with construction and operation of the proposed processing facilities, or pursue a different path. To support of the decision, DOE is evaluating alternatives to potentially enhance the BNFL tank waste processing contract, as well as, developing an alternate path forward should DOE decide to not continue the BNFL contract. The decision on whether to continue with the current privatization strategy (BNFL contract) or to pursue an alternate can not be made until the evaluation process leading up to the decision on whether to authorize BNFL to proceed with construction and operation (known as the Part 8-2 decision) is completed. The evaluation process includes reviewing and evaluating the information BNFL is scheduled to submit in April 2000, and negotiating the best mutually acceptable contract terms. The alternatives studies completed to-date are summarized in Reference 2.

WODRICH, D.D.

2000-03-24T23:59:59.000Z

243

Engineering study of the potential uses of salts from selective crystallization of Hanford tank wastes  

SciTech Connect

The Clean Salt Process (CSP) is the fractional crystallization of nitrate salts from tank waste stored on the Hanford Site. This study reviews disposition options for a CSP product made from Hanford Site tank waste. These options range from public release to onsite low-level waste disposal to no action. Process, production, safety, environment, cost, schedule, and the amount of CSP material which may be used are factors considered in each option. The preferred alternative is offsite release of clean salt. Savings all be generated by excluding the material from low-level waste stabilization. Income would be received from sales of salt products. Savings and income from this alternative amount to $1,027 million, excluding the cost of CSP operations. Unless public sale of CSP products is approved, the material should be calcined. The carbonate form of the CSP could then be used as ballast in tank closure and stabilization efforts. Not including the cost of CSP operations, savings of $632 million would be realized. These savings would result from excluding the material from low-level waste stabilization and reducing purchases of chemicals for caustic recycle and stabilization and closure. Dose considerations for either alternative are favorable. No other cost-effective alternatives that were considered had the capacity to handle significant quantities of the CSP products. If CSP occurs, full-scale tank-waste stabilization could be done without building additional treatment facilities after Phase 1 (DOE 1996). Savings in capital and operating cost from this reduction in waste stabilization would be in addition to the other gains described.

Hendrickson, D.W.

1996-04-30T23:59:59.000Z

244

Development of a Chemistry-Based, Predictive Method for Determining the Amount of Non-Pertechnetate Technetium in the Hanford Tanks: FY 2012 Progress Report  

Science Conference Proceedings (OSTI)

This report describes investigations directed toward understanding the extent of the presence of highly alkaline soluble, non-pertechnetate technetium (n-Tc) in the Hanford Tank supernatants. The goals of this report are to: a) present a review of the available literature relevant to the speciation of technetium in the Hanford tank supernatants, b) attempt to establish a chemically logical correlation between available Hanford tank measurements and the presence of supernatant soluble n-Tc, c) use existing measurement data to estimate the amount of n-Tc in the Hanford tank supernatants, and d) report on any likely, process-friendly methods to eventually sequester soluble n-Tc from Hanford tank supernatants.

Rapko, Brian M.; Bryan, Samuel A.; Bryant, Janet L.; Chatterjee, Sayandev; Edwards, Matthew K.; Houchin, Joy Y.; Janik, Tadeusz J.; Levitskaia, Tatiana G.; Peterson, James M.; Peterson, Reid A.; Sinkov, Sergey I.; Smith, Frances N.; Wittman, Richard S.

2013-01-30T23:59:59.000Z

245

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT SEISMIC ANALYSIS IN SUPPORT OF INCREASED LIQUID LEVEL IN 241-AP TANK FARMS  

Science Conference Proceedings (OSTI)

The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST System at Hanford. The "Double-Shell Tank (DST) Integrity Project - DST Thermal and Seismic Project" is in support of Tri-Party Agreement Milestone M-48-14.

MACKEY TC; ABBOTT FG; CARPENTER BG; RINKER MW

2007-02-16T23:59:59.000Z

246

Headspace vapor characterization of Hanford waste Tank 241-C-201: Results from samples collected on 06/19/96  

DOE Green Energy (OSTI)

This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-C-201 (Tank C-201) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary, of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. Detailed descriptions of the analytical results appear in the appendices.

Thomas, B.L.; Evans, J.C.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

1997-01-01T23:59:59.000Z

247

Headspace vapor characterization of Hanford waste Tank 241-C-202: Results from samples collected on 06/25/96  

DOE Green Energy (OSTI)

This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-C-202 (Tank C-202) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. Detailed descriptions of the analytical results appear in the appendices.

Pool, K.H.; Evans, J.C.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

1997-01-01T23:59:59.000Z

248

Spectrum shape-analysis techniques applied to the Hanford Tank Farms spectral gamma logs  

SciTech Connect

Gamma-ray spectra acquired with high-energy resolution by the spectral gamma logging systems (SGLSs) at the U.S. Department of Energy Hanford Tank Farms, Richland, Washington, are being analyzed for spectral shape characteristics. These spectral shapes, together with a conventional peak-area analysis, enable an analyst not only to identify the gamma-emitting species but also to determine in many instances its spatial distribution around a borehole and to identify the presence of the bremsstrahlung-producing contaminant {sup 90}Sr. The analysis relies primarily on the results of computer simulations of gamma spectra from the predominant radionuclide {sup 137}Cs for various spatial distributions. This log analysis methodology has evolved through an examination of spectral features from spectral logs taken at the SX, BY, and U Tank Farms at the Hanford Site. Initial results determined with this technique show it is possible, in most cases, to distinguish between concentrations of {sup 137}Cs. Work is continuing by experimentally measuring shape factors, incorporating spectrum shape processing in routine log analysis, and extending the techniques to additional radionuclides.

Wilson, R.D.

1997-05-01T23:59:59.000Z

249

Recharge Data Package for Hanford Single-Shell Tank Waste Management Areas  

Science Conference Proceedings (OSTI)

Pacific Northwest National Laboratory (PNNL) assists CH2M HILL Hanford Group, Inc., in its preparation of the Resource Conservation and Recovery Act (RCRA) Facility Investigation report. One of the PNNL tasks is to use existing information to estimate recharge rates for past and current conditions as well as future scenarios involving cleanup and closure of tank farms. The existing information includes recharge-relevant data collected during activities associated with a host of projects, including those of RCRA, the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), the CH2M HILL Tank Farm Vadose Zone Project, and the PNNL Remediation and Closure Science Project. As new information is published, the report contents can be updated. The objective of this data package was to use published data to provide recharge estimates for the scenarios being considered in the RCRA Facility Investigation. Recharge rates were estimated for areas that remain natural and undisturbed, areas where the vegetation has been disturbed, areas where both the vegetation and the soil have been disturbed, and areas that are engineered (e.g., surface barrier). The recharge estimates supplement the estimates provided by PNNL researchers in 2006 for the Hanford Site using additional field measurements and model analysis using weather data through 2006.

Fayer, Michael J.; Keller, Jason M.

2007-09-24T23:59:59.000Z

250

Mechanism of Phosphorus Removal from Hanford Tank Sludge by Caustic Leaching  

SciTech Connect

Two experiments were conducted to explore the mechanism by which phosphorus is removed from Hanford tank sludge by caustic leaching. In the first experiment, a series of phosphate salts were treated with 3 M NaOH under conditions prototypic of the actual leaching process to be performed in the Waste Treatment and Immobilization Plant (WTP). The phosphates used were aluminum phosphate, bismuth phosphate, chromium(III) phosphate, and ?-tri-calcium phosphate; all of these phases have previously been determined to exist in Hanford tank sludge. The leachate solution was sampled at selected time intervals and analyzed for the specific metal ion involved (Al, Bi, Ca, or Cr) and for P (total and as phosphate). The solids remaining after completion of the caustic leaching step were analyzed to determine the reaction product. In the second experiment, the dependence of P removal from bismuth phosphate was examined as a function of the hydroxide ion concentration. It was anticipated that a plot of log[phosphate] versus log[hydroxide] would provide insight into the phosphorus-removal mechanism. This report describes the test activities outlined in Section 6.3.2.1, Preliminary Investigation of Phosphate Dissolution, in Test Plan TP-RPP-WTP-467, Rev.1. The objectives, success criteria, and test conditions of Section 6.3.2.1 are summarized here.

Lumetta, Gregg J.

2008-03-05T23:59:59.000Z

251

Low temperature hydrothermal processing of organic contaminants in Hanford tank waste  

DOE Green Energy (OSTI)

Batch and continuous flow reactor tests at Pacific Northwest Laboratory (PNL) have shown that organics similar to those present in the single-shell and double-shell underground storage tanks at Hanford can be decomposed in the liquid phase at relatively mild temperatures of 150[degree]C to 350[degree]C in an aqueous process known as hydrothermal processing (HTP). The organics will react with the abundant oxidants such s nitrite already present in the Hanford tank waste to form hydrogen, carbon dioxide, methane, and ammonia. No air or oxygen needs to be added to the system. Ferrocyanides and free cyanide will hydrolyze at similar temperatures to produce formate and ammonia and may also react with nitrates or other oxides. During testing, the organic carbon was transformed first to oxalate at[approximately]310[degree]C and completely oxidized to carbonate at [approximately]350[degree]C accompanied by hydroxide consumption. Solids were formed at higher temperatures, causing a small-diameter outlet tube to plug. The propensity for plugging was reduced by diluting the feed with concentrated hydroxide.

Jones, E.O.; Pederson, L.R.; Freeman, H.D.; Schmidt, A.J. (Pacific Northwest Lab., Richland, WA (United States)); Babad, H. (Westinghouse Hanford Co., Richland, WA (United States))

1993-02-01T23:59:59.000Z

252

Effects of Hanford tank simulant waste on plastic packaging to components  

Science Conference Proceedings (OSTI)

We have developed a chemical compatibility program for the evaluation of plastic packaging components which may be incorporated in packaging for transporting mixed waste forms. Consistent with the methodology outlined in this paper, we have performed the second phase of this experimental program to determine the effects of simulant Hanford Tank mixed wastes on packaging materials. This effort involved the comprehensive testing of five plastic liner materials in the aqueous mixed waste simulant. The testing protocol involved exposing the respective materials to {approximately}1, 3, 6, and 40 kGy of gamma radiation followed by 7, 14, 28, 180 day exposures to the waste simulant at 18, 50, and 60{degree}C. From the limited data analyses performed to date in this study, we have identified the fluorocarbon Kel-F{trademark} as having the greatest chemical compatibility after having been exposed to 40 kGy gamma radiation followed by exposure to the Hanford Tank simulant mixed waste at 60{degree}C. The most stricking observation from this study was the poor performance of Teflon under these conditions.

Nigrey, P.J.; Dickens, T.G.

1995-12-01T23:59:59.000Z

253

Comprehensive testing to measure the response of fluorocarbon rubber (FKM) to Hanford tank waste simulant  

Science Conference Proceedings (OSTI)

This report presents the findings of the Chemical Compatibility Program developed to evaluate plastic packaging components that may be incorporated in packaging mixed-waste forms for transportation. Consistent with the methodology outlined in this report, the authors performed the second phase of this experimental program to determine the effects of simulant Hanford tank mixed wastes on packaging seal materials. That effort involved the comprehensive testing of five plastic liner materials in an aqueous mixed-waste simulant. The testing protocol involved exposing the materials to {approximately}143, 286, 571, and 3,670 Krad of gamma radiation and was followed by 7-, 14-, 28-, 180-day exposures to the waste simulant at 18, 50, and 60 C. Fluorocarbon (FKM) rubber samples subjected to the same protocol were then evaluated by measuring seven material properties: specific gravity, dimensional changes, mass changes, hardness, compression set, vapor transport rates, and tensile properties. From the analyses, they determined that FKM rubber is not a good seal material to withstand aqueous mixed wastes having similar composition to the one used in this study. They have determined that FKM rubber has limited chemical durability after exposure to gamma radiation followed by exposure to the Hanford tank simulant mixed waste at elevated temperatures above 18 C.

NIGREY,PAUL J.; BOLTON,DENNIS L.

2000-02-01T23:59:59.000Z

254

Low temperature hydrothermal processing of organic contaminants in Hanford tank waste  

DOE Green Energy (OSTI)

Batch and continuous flow reactor tests at Pacific Northwest Laboratory (PNL) have shown that organics similar to those present in the single-shell and double-shell underground storage tanks at Hanford can be decomposed in the liquid phase at relatively mild temperatures of 150{degree}C to 350{degree}C in an aqueous process known as hydrothermal processing (HTP). The organics will react with the abundant oxidants such s nitrite already present in the Hanford tank waste to form hydrogen, carbon dioxide, methane, and ammonia. No air or oxygen needs to be added to the system. Ferrocyanides and free cyanide will hydrolyze at similar temperatures to produce formate and ammonia and may also react with nitrates or other oxides. During testing, the organic carbon was transformed first to oxalate at{approximately}310{degree}C and completely oxidized to carbonate at {approximately}350{degree}C accompanied by hydroxide consumption. Solids were formed at higher temperatures, causing a small-diameter outlet tube to plug. The propensity for plugging was reduced by diluting the feed with concentrated hydroxide.

Jones, E.O.; Pederson, L.R.; Freeman, H.D.; Schmidt, A.J. [Pacific Northwest Lab., Richland, WA (United States); Babad, H. [Westinghouse Hanford Co., Richland, WA (United States)

1993-02-01T23:59:59.000Z

255

Tank Vapor Characterization Project -- Headspace vapor characterization of Hanford waste Tank 241-C-107: Results from samples collected on 01/17/96  

DOE Green Energy (OSTI)

This report describes the analytical results of vapor samples taken from the headspace of waste storage tank 241-C-107 (Tank C-107) at the Hanford Site in Washington State. The results described in this report were obtained to compare vapor sampling of the tank headspace using the Vapor Sampling System (VSS) and In Situ Vapor Sampling (ISVS) system with and without high efficiency particulate air (HEPA) prefiltration. The results include air concentrations of water (H{sub 2}O) and ammonia (NH{sub 3}), permanent gases, total non-methane hydrocarbons (TO-12), and individual organic analytes collected in SUMMA{trademark} canisters and on triple sorbent traps (TSTs). Samples were collected by Westinghouse Hanford Company (WHC) and analyzed by Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volume measurements provided by WHC.

Thomas, B.L.; Evans, J.C.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

1996-07-01T23:59:59.000Z

256

THE APPARENT SOLUBILITY OF ALUMINUM(III) IN HANFORD HIGH-LEVEL WASTE TANKS  

SciTech Connect

The solubility of aluminum in Hanford nuclear waste impacts on the process ability of the waste by a number of proposed treatment options. For many years, Hanford staff has anecdotally noted that aluminum appears to be considerably more soluble in Hanford waste than the simpler electrolyte solutions used as analogues. There has been minimal scientific study to confirm these anecdotal observations, however. The present study determines the apparent solubility product for gibbsite in 50 tank samples. The ratio of hydroxide to aluminum in the liquid phase for the samples is calculated and plotted as a function of total sodium molarity. Total sodium molarity is used as a surrogate for ionic strength, because the relative ratios of mono, di and trivalent anions are not available for all of the samples. These results were compared to the simple NaOH-NaAl(OH{sub 4})H{sub 2}O system, and the NaOH-NaAl(OH{sub 4})NaCl-H{sub 2}O system data retrieved from the literature. The results show that gibbsite is apparently more soluble in the samples than in the simple systems whenever the sodium molarity is greater than two. This apparent enhanced solubility cannot be explained solely by differences in ionic strength. The change in solubility with ionic strength in simple systems is small compared to the difference between aluminum solubility in Hanford waste and the simple systems. The reason for the apparent enhanced solubility is unknown, but could include. kinetic or thermodynamic factors that are not present in the simple electrolyte systems. Any kinetic explanation would have to explain why the samples are always supersaturated whenever the sodium molarity is above two. Real waste characterization data should not be used to validate thermodynamic solubility models until it can be confirmed that the apparent enhanced gibbsite solubility is a thermodynamic effect and not a kinetic effect.

REYNOLDS JG

2012-06-20T23:59:59.000Z

257

DEMONSTRATION OF SIMULATED WASTE TRANSFERS FROM TANK AY-102 TO THE HANFORD WASTE TREATMENT FACILITY  

SciTech Connect

In support of Hanford's AY-102 Tank waste certification and delivery of the waste to the Waste Treatment and Immobilization Plant (WTP), Savannah River National Laboratory (SRNL) was tasked by the Washington River Protection Solutions (WRPS) to evaluate the effectiveness of mixing and transferring the waste in the Double Shell Tank (DST) to the WTP Receipt Tank. This work is a follow-on to the previous 'Demonstration of Internal Structures Impacts on Double Shell Tank Mixing Effectiveness' task conducted at SRNL 1. The objective of these transfers was to qualitatively demonstrate how well waste can be transferred out of a mixed DST tank and to provide insights into the consistency between the batches being transferred. Twelve (12) different transfer demonstrations were performed, varying one parameter at a time, in the Batch Transfer Demonstration System. The work focused on visual comparisons of the results from transferring six batches of slurry from a 1/22nd scale (geometric by diameter) Mixing Demonstration Tank (MDT) to six Receipt Tanks, where the consistency of solids in each batch could be compared. The simulant used in this demonstration was composed of simulated Hanford Tank AZ-101 supernate, gibbsite particles, and silicon carbide particles, the same simulant/solid particles used in the previous mixing demonstration. Changing a test parameter may have had a small impact on total solids transferred from the MDT on a given test, but the data indicates that there is essentially no impact on the consistency of solids transferred batch to batch. Of the multiple parameters varied during testing, it was found that changing the nozzle velocity of the Mixer Jet Pumps (MJPs) had the biggest impact on the amount of solids transferred. When the MJPs were operating at 8.0 gpm (22.4 ft/s nozzle velocity, U{sub o}D=0.504 ft{sup 2}/s), the solid particles were more effectively suspended, thus producing a higher volume of solids transferred. When the MJP flow rate was reduced to 5 gpm (14 ft/s nozzle velocity, U{sub o}D = 0.315 ft{sup 2}/s) to each pump, dead zones formed in the tank, resulting in fewer solids being transferred in each batch to the Receipt Tanks. The larger, denser particles were displaced (preferentially to the smaller particles) to one of the two dead zones and not re-suspended for the duration of the test. As the liquid level dropped in the MDT, re-suspending the particles became less effective (6th batch). The poor consistency of the solids transferred in the 6th batch was due to low liquid level in the MDT, thus poor mixing by the MJPs. Of the twelve tests conducted the best transfer of solids occurred during Test 6 and 8 where the MJP rotation was reduced to 1.0 rpm.

Adamson, D.; Poirier, M.; Steeper, T.

2009-12-03T23:59:59.000Z

258

Determination of ring correction factors for leaded gloves used in grab sampling activities at Hanford tank farms  

Science Conference Proceedings (OSTI)

This study evaluates the effectiveness of lead lined gloves in reducing extremity dose from two sources specific to tank waste sampling activities: (1) sludge inside glass sample jars and (2) sludge as thin layer contamination on the exterior surface of sample jars. The response of past and present Hanford Extremity Dosimeters (ring) designs under these conditions is also evaluated.

RATHBONE, B.A.

1999-06-24T23:59:59.000Z

259

Statements of work for FY 1996 to 2001 for the Hanford Low-Level Tank Waste Performance Assessment Project  

SciTech Connect

The statements of work for each activity and task of the Hanford Low-Level Tank Waste Performance Assessment project are given for the fiscal years 1996 through 2001. The end product of this program is approval of a final performance assessment by the Department of Energy in the year 2000.

Mann, F.M.

1995-06-07T23:59:59.000Z

260

HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION & PLANNING FOR REVRIEVAL TREATMENT & EVENTUAL DISPOSAL AT WIPP  

SciTech Connect

The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP).

KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

2006-01-18T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

ESTIMATING HIGH LEVEL WASTE MIXING PERFORMANCE IN HANFORD DOUBLE SHELL TANKS  

SciTech Connect

The ability to effectively mix, sample, certify, and deliver consistent batches of high level waste (HLW) feed from the Hanford double shell tanks (DSTs) to the Waste Treatment and Immobilization Plant (WTP) presents a significant mission risk with potential to impact mission length and the quantity of HLW glass produced. The Department of Energy's (DOE's) Tank Operations Contractor (TOC), Washington River Protection Solutions (WRPS) is currently demonstrating mixing, sampling, and batch transfer performance in two different sizes of small-scale DSTs. The results of these demonstrations will be used to estimate full-scale DST mixing performance and provide the key input to a programmatic decision on the need to build a dedicated feed certification facility. This paper discusses the results from initial mixing demonstration activities and presents data evaluation techniques that allow insight into the performance relationships of the two small tanks. The next steps, sampling and batch transfers, of the small scale demonstration activities are introduced. A discussion of the integration of results from the mixing, sampling, and batch transfer tests to allow estimating full-scale DST performance is presented.

THIEN MG; GREER DA; TOWNSON P

2011-01-13T23:59:59.000Z

262

Laboratory Demonstration of the Pretreatment Process with Caustic and Oxidative Leaching Using Actual Hanford Tank Waste  

Science Conference Proceedings (OSTI)

This report describes the bench-scale pretreatment processing of actual tank waste materials through the entire baseline WTP pretreatment flowsheet in an effort to demonstrate the efficacy of the defined leaching processes on actual Hanford tank waste sludge and the potential impacts on downstream pretreatment processing. The test material was a combination of reduction oxidation (REDOX) tank waste composited materials containing aluminum primarily in the form of boehmite and dissolved S saltcake containing Cr(III)-rich entrained solids. The pretreatment processing steps tested included caustic leaching for Al removal solids crossflow filtration through the cell unit filter (CUF) stepwise solids washing using decreasing concentrations of sodium hydroxide with filtration through the CUF oxidative leaching using sodium permanganate for removing Cr solids filtration with the CUF follow-on solids washing and filtration through the CUF ion exchange processing for Cs removal evaporation processing of waste stream recycle for volume reduction combination of the evaporated product with dissolved saltcake. The effectiveness of each process step was evaluated by following the mass balance of key components (such as Al, B, Cd, Cr, Pu, Ni, Mn, and Fe), demonstrating component (Al, Cr, Cs) removal, demonstrating filterability by evaluating filter flux rates under various processing conditions (transmembrane pressure, crossflow velocities, wt% undissolved solids, and PSD) and filter fouling, and identifying potential issues for WTP. The filterability was reported separately (Shimskey et al. 2008) and is not repeated herein.

Fiskum, Sandra K.; Billing, Justin M.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Snow, Lanee A.

2009-01-01T23:59:59.000Z

263

Predicting Peak Hydrogen Concentrations from Spontaneous Gas Releases in Hanford Waste Tanks  

DOE Green Energy (OSTI)

Buoyant displacement gas release events (BDGRE) are spontaneous gas releases that occur in a few of the Hanford radioactive waste storage tanks when gas accumulation makes the sediment layer buoyant with respect to the liquid. BDGREs are assumed to be likely if the ratio of the predicted sediment gas fraction and neutral buoyancy gas fraction, or buoyancy ratio, exceeds unity. Based on the observation that the buoyancy ratio is also an empirical indicator of BDGRE size, a new methodology is derived that formally correlates the buoyancy ratio and the peak headspace hydrogen concentration resulting from BDGREs. The available data on the six historic BDGRE tanks, AN-103, AN-104, AN-105, AW-101, SY-103, and SY-101, are studied in detail to describe both the waste state and the corresponding distribution of BDGREs. The range of applicability of the buoyancy ratio-based models is assessed based on the modeling assumptions and availability of tank data. Recommendations are given for extending the range of the models applicability.

Stewart, Charles W.; Hartley, Stacey A.; Meyer, Perry A.; Wells, Beric E.

2005-07-15T23:59:59.000Z

264

The radiolytic and radiolytically induced gas generation in Hanford waste tanks  

DOE Green Energy (OSTI)

A task force operating in ANL/CHM has been developing a mechanistic understanding of the radiolytic processes that lead to the generation and retention of gases within tanks of radioactive waste at the Hanford site. This chemistry is one of the important factors that must be considered in devising remediation procedures to eliminate the great potential hazard of these tanks. A quantitative description of much of the chemistry involved in the production of H{sub 2} and, to a lesser extent, in the production of N{sub 2}O has been achieved. Direct radiolytic generation was experimentally quantified and this new information was utilized in computer modeling to provide predictive capabilities so that changes of chemical composition of various waste tanks under different remediation procedures could be assessed. Oxygen in the waste solutions is effectively consumed upon irradiation and thus is of no concern. The mechanism of the radiolytic degradation of the chelators was established. The end products are simple organic molecules, in particularly, formaldehyde and glyoxylate, that are very efficient in the thermal generation of H{sub 2}

Jonah, C.D.; Meisel, D.; Sauer, M.C. Jr.

1994-06-01T23:59:59.000Z

265

Characterization of the corrosion behavior of the carbon steel liner in Hanford Site single-shell tanks  

SciTech Connect

Six safety initiatives have been identified for accelerating the resolution of waste tank safety issues and closure of unreviewed safety questions. Safety Initiative 5 is to reduce safety and environmental risk from tank leaks. Item d of Safety Initiative 5 is to complete corrosion studies of single-shell tanks to determine failure mechanisms and corrosion control options to minimize further degradation by June 1994. This report has been prepared to fulfill Safety Initiative 5, Item d. The corrosion mechanisms that apply to Hanford Site single-shell tanks are stress corrosion cracking, pitting/crevice corrosion, uniform corrosion, hydrogen embrittlement, and microbiologically influenced corrosion. The corrosion data relevant to the single-shell tanks dates back three decades, when results were obtained from in-situ corrosion coupons in a few single-shell tanks. Since that time there have been intertank transfers, evaporation, and chemical alterations of the waste. These activities have changed the character and the present composition of the waste is not well characterized. All conclusions and recommendations are made in the absence of relevant laboratory experimental data and tank inspection data. The report attempts to identify the failure mechanisms by a literature survey of carbon steel data in environments similar to the single-shell tank wastes, and by a review of the work performed at the Savannah River Site where similar wastes are stored in similar carbon steel tanks. Based on these surveys, and in the absence of data specific to Hanford single-shell tanks, it may be concluded that the single-shell tanks identified as leakers failed primarily by stress corrosion cracking due to the presence of high nitrate/low hydroxide wastes and residual stresses. In addition, some failures may be attributed to pitting under crevices in low hydroxide locations.

Anantatmula, R.P.; Schwenk, E.B. [Westinghouse Hanford Co., Richland, WA (United States); Danielson, M.J. [Pacific Northwest Lab., Richland, WA (United States)

1994-06-01T23:59:59.000Z

266

Effect of Antifoam Agent on Oxidative Leaching of Hanford Tank Sludge Simulants  

SciTech Connect

Oxidative leaching of simulant tank waste containing an antifoam agent (AFA) to reduce the chromium content of the sludge was tested using permanganate as the oxidant in 0.25 M NaOH solutions. AFA is added to the waste treatment process to prevent foaming. The AFA, Dow Corning Q2-3183A, is a surface-active polymer that consists of polypropylene glycol, polydimethylsiloxane, octylphenoxy polyethoxy ethanol, treated silica, and polyether polyol. Some of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste slurries contain high concentrations of undissolved solids that would exhibit undesirable behavior without AFA addition. These tests were conducted to determine the effect of the AFA on oxidative leaching of Cr(III) in waste by permanganate. It has not previously been determined what effect AFA has on the permanganate reaction. This study was conducted to determine the effect AFA has on the oxidation of the chromium, plus plutonium and other criticality-related elements, specifically Fe, Ni and Mn. During the oxidative leaching process, Mn is added as liquid permanganate solution and is converted to an insoluble solid that precipitates as MnO2 and becomes part of the solid waste. Caustic leaching was performed followed by an oxidative leach at either 25C or 45C. Samples of the leachate and solids were collected at each step of the process. Initially, Battelle-Pacific Northwest Division (PNWD) was contracted by Bechtel National, Inc. to perform these further scoping studies on oxidative alkaline leaching. The data obtained from the testing will be used by the WTP operations to develop procedures for permanganate dosing of Hanford tank sludge solids during oxidative leaching. Work was initially conducted under contract number 24590-101-TSA-W000-00004. In February 2007, the contract mechanism was switched to Pacific Northwest National Laboratory (PNNL) operating Contract DE-AC05-76RL01830. In summary, this report describes work focused on determining the effect of AFA on chromium oxidation by permanganate with Hanford sludge simulant.

Rapko, Brian M.; Jones, Susan A.; Lumetta, Gregg J.; Peterson, Reid A.

2010-02-26T23:59:59.000Z

267

Mechanisms of gas retention and release: Experimental results for Hanford waste tanks 241-AW-101 and 241-AN-103  

DOE Green Energy (OSTI)

The 177 storage tanks at Hanford contain a vast array of radioactive waste forms resulting, primarily, from nuclear materials processing. Through radiolytic, thermal, and other decomposition reactions of waste components, gaseous species including hydrogen, ammonia, and the oxidizer nitrous oxide are generated within the waste tanks. Many of these tanks are known to retain and periodically release quantities of these flammable gas mixtures. The primary focus of the Flammable Gas Project is the safe storage of Hanford tank wastes. To this end, we strive to develop an understanding of the mechanisms of flammable gas retention and release in Hanford tanks through laboratory investigations on actual tank wastes. These results support the closure of the Flammable Gas Unreviewed Safety Question (USQ) on the safe storage of waste tanks known to retain flammable gases and support resolution of the broader Flammable Gas Safety Issue. The overall purpose of this ongoing study is to develop a comprehensive and thorough understanding of the mechanisms of flammable gas retention and release. The first objective of the current study was to classify bubble retention and release mechanisms in two previously untested waste materials from Tanks 241-AN-103 (AN-103) and 241-AW-101 (AW-101). Results were obtained for retention mechanisms, release characteristics, and the maximum gas retention. In addition, unique behavior was also documented and compared with previously studied waste samples. The second objective was to lengthen the duration of the experiments to evaluate the role of slowing bubble growth on the retention and release behavior. Results were obtained for experiments lasting from a few hours to a few days.

Rassat, S.D.; Gauglitz, P.A.; Bredt, P.R.; Mahoney, L.A.; Forbes, S.V.; Tingey, S.M.

1997-09-01T23:59:59.000Z

268

Slurry growth, gas retention, and flammable gas generation by Hanford radioactive waste tanks: Synthetic waste studies, FY 1991  

DOE Green Energy (OSTI)

Of 177 high-level waste storage tanks on the Hanford Site, 23 have been placed on a safety watch list because they are suspected of producing flammable gases in flammable or explosive concentrate. One tankin particular, Tank 241-SY-101 (Tank 101-SY), has exhibited slow increases in waste volume followed by a rapid decrease accompanied by venting of large quantities of gases. The purpose of this study is to help determine the processes by which flammable gases are produced, retained, and eventually released from Tank 101-SY. Waste composition data for single- and double-shell waste tanks on the flammable gas watch listare critically reviewed. The results of laboratory studies using synthetic double-shell wastes are summarized, including physical and chemical properties of crusts that are formed, the stoichiometry and rate ofgas generation, and mechanisms responsible for formation of a floating crust.

Bryan, S.A.; Pederson, L.R.; Ryan, J.L.; Scheele, R.D.; Tingey, J.M.

1992-08-01T23:59:59.000Z

269

Level sensor replacement/sampling of Tank 241-SY-101 at the Hanford Site  

SciTech Connect

The US Department of Energy (DOE) is responsible for management and storage of waste accumulated from the processing of defense reactor irradiated fuels for plutonium recovery at the Hanford Site. DOE is proposing to remove three level detectors from Tank 241-SY-101 and analyze the waste that is presently encrusted on the detectors. The proposed sampling is less intrusive than core sampling and will provide data regarding characterization of the crust to support future core sampling. The purpose of this environmental assessment (EA) is to provide information about the proposed action such that a decision can be made on whether a Finding of No Significant Impact should be issued or an environmental impact statement should be prepared. Therefore, this EA evaluates the proposed action and the no action alternative, in keeping with requirements of the National Environmental Policy Act of 1969 (NEPA) and regulations of the Council on Environmental Quality, Title 40, Code of Federal Regulations, parts 1500--1508. 6 refs.

Not Available

1990-01-01T23:59:59.000Z

270

Implementation of an Integrated Information Management System for the US DOE Hanford Tank Farms Project - 14224  

SciTech Connect

In its role as the Tank Operations Contractor at the U.S. Department of Energy?s site in Hanford, WA, Washington River Protection Solutions, LLC is implementing an integrated document control and configuration management system. This system will combine equipment data with technical document data that currently resides in separate disconnected databases. The new system will provide integrated information, enabling users to more readily identify the documents that relate to a structure, system, or component and vice-versa. Additionally, the new system will automate engineering work processes through electronic workflows, and where practical and feasible provide integration with design authoring tools. Implementation of this system will improve configuration management of the technical baseline, increase work process efficiencies, support the efficient design of future large projects, and provide a platform for the efficient future turnover of technical baseline data and information.

Joyner, William Scott; Knight, Mark A.

2013-11-14T23:59:59.000Z

271

Evaluation of cracking in the 241-AZ tank farm ventilation line at the Hanford Site  

Science Conference Proceedings (OSTI)

In the period from April to October of 1988, a series of welding operations on the outside of the AZ Tank Farm ventilation line piping at the Hanford Site produced unexpected and repeated cracking of the austenitic stainless steel base metal and of a seam weld in the pipe. The ventilation line is fabricated from type 304L stainless steel pipe of 24 inch diameter and 0.25 inch wall thickness. The pipe was wrapped in polyethylene bubble wrap and buried approximately 12 feet below grade. Except for the time period between 1980 and 1987, impressed current cathodic protection has been applied to the pipe since its installation in 1974. The paper describes the history of the cracking of the pipe, the probable cracking mechanisms, and the recommended future action for repair/replacement of the pipe.

ANANTATMULA, R.P.

1999-10-20T23:59:59.000Z

272

Simulant Development for Hanford Tank Farms Double Valve Isolation (DVI) Valves Testing  

SciTech Connect

Leakage testing of a representative sample of the safety-significant isolation valves for Double Valve Isolation (DVI) in an environment that simulates the abrasive characteristics of the Hanford Tank Farms Waste Transfer System during waste feed delivery to the Waste Treatment and Immobilization Plant (WTP) is to be conducted. The testing will consist of periodic leak performed on the DVI valves after prescribed numbers of valve cycles (open and close) in a simulated environment representative of the abrasive properties of the waste and the Waste Transfer System. The valve operations include exposure to cycling conditions that include gravity drain and flush operation following slurry transfer. The simulant test will establish the performance characteristics and verify compliance with the Documented Safety Analysis. Proper simulant development is essential to ensure that the critical process streams characteristics are represented, National Research Council report Advice on the Department of Energy's Cleanup Technology Roadmap: Gaps and Bridges

Wells, Beric E.

2012-12-21T23:59:59.000Z

273

An assessment of the dilution required to mitigate Hanford tank 241-SY-101  

Science Conference Proceedings (OSTI)

A group of experts from PNL and WHC convened November 2 and 3, 1994, to screen the current state of knowledge about dilution and reach a consensus on the minimum dilution ratio that will achieve passive mitigation of Tank 241-SY-101 wastes and the dilution ratio that would satisfy the given cross-site transfer criteria with reasonable assurance. The panel evaluated the effects of dilution on the parameters important in gas generation, retention, and release and reached the following conclusions, which are deduced from the existing body of data, experience, and analyses: (1) Dissolution of solids is the single most important aspect of mitigation by dilution. We are confident that diluting until nitrates, nitrites, and aluminum salts are dissolved will mitigate Hanford flammable gas tanks; (2) Sufficient solids dissolution can be achieved in Tank 241-SY-101 at a dilution ratio of 1:1, which will result in a average specific gravity of approximately 1.35. It is likely that a 0.5:1 dilution will also mitigate 241-SY-101, but the current uncertainty is too high to recommend this dilution ratio; (3) The recommended dilution requires a diluent with at least 2 molar free hydroxide, because aluminum probably precipitates at lower hydroxide concentrations. The transfer criteria for Tank 241-SY-101 waste were also evaluated. These criteria have been specified as solids content {<=}30% (volume), viscosity {<=}30% cP and density <1.5 g/mL. (1) Solids content is the limiting criterion if it is defined as volume fraction of settled solids. A 1:1 dilution will satisfy this criterion at nominal premixing conditions in Tank 241-SY-101; however, analysis of Window E core samples suggests that up to 1.5:1 might be required. If the solids content is interpreted simply as solids volume fraction no further dilution is necessary, because Tank 241-SY-101 waste (excluding the crust) is already below 30%; (2) Bulk density is the next limiting criterion and is met at 0.4:1 dilution.

Hudson, J.D.; Bredt, P.R.; Felmy, A.R.; Stewart, C.W.; Tingey, J.M.; Trent, D.S. [Pacific Northwest Lab., Richland, WA (United States); Barney, G.S.; Herting, D.L.; Larrick, A.P.; Reynolds, D.A. [Westinghouse Hanford Co., Richland, WA (United States)

1995-02-01T23:59:59.000Z

274

ONE SYSTEM INTEGRATED PROJECT TEAM: RETRIEVAL AND DELIVERY OF THE HANFORD TANK WASTES FOR VITRIFICATION IN THE WASTE TREATMENT PLANT  

SciTech Connect

The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction ofWTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration & Controls, Front-End Design & Project Definition, Commissioning, Nuclear Safety & Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH&QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant Foundation-Configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan.

HARP BJ; KACICH RM; SKWAREK RJ

2012-12-20T23:59:59.000Z

275

One System Integrated Project Team: Retrieval And Delivery Of The Hanford Tank Wastes For Vitrification In The Waste Treatment Plant  

Science Conference Proceedings (OSTI)

The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank wastes and for building and operating the WTP. The tank wastes are the result of Hanford's nearly fifty (50) years of plutonium production. In the intervening years, waste characteristics have been increasingly better understood. However, waste characteristics that are uncertain and will remain as such represent a significant technical challenge in terms of retrieval, transport, and treatment, as well as for design and construction ofWTP. What also is clear is that the longer the waste remains in the tanks, the greater the risk to the environment and the people of the Pacific Northwest. The goal of both projects - tank operations and waste treatment - is to diminish the risks posed by the waste in the tanks at the earliest possible date. About two hundred (200) WTP and TOC employees comprise the IPT. Individual work groups within One System include Technical, Project Integration & Controls, Front-End Design & Project Definition, Commissioning, Nuclear Safety & Engineering Systems Integration, and Environmental Safety and Health and Quality Assurance (ESH&QA). Additional functions and team members will be added as the WTP approaches the operational phase. The team has undertaken several initiatives since its formation to collaborate on issues: (1) alternate scenarios for delivery of wastes from the tank farms to WTP; (2) improvements in managing Interface Control Documents; (3) coordination on various technical issues, including the Defense Nuclear Facilities Nuclear Safety Board's Recommendation 2010-2; (4) deployment of the SmartPlant? Foundation-configuration Management System; and (5) preparation of the joint contract deliverable of the Operational Readiness Support Plan.

Harp, Benton J. [Department of Energy, Office of River Protection, Richland, Washington (United States); Kacich, Richard M. [Bechtel National, Inc., Richland, WA (United States); Skwarek, Raymond J. [Washington River Protection Solutions LLC, Richland, WA (United States)

2012-12-20T23:59:59.000Z

276

Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102  

SciTech Connect

The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m{sup 3}) of supernatant liquid and 95,000 gallons (360 m{sup 3}) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom.

Y Onishi; KP Recknagle; BE Wells

2000-08-09T23:59:59.000Z

277

Spherical Resorcinol-Formaldehyde Resin Testing for Cesium Removal from Hanford Tank Waste Simulant  

SciTech Connect

A new spherical form of resorcinol-formaldehyde (RF) resin was tested for efficacy of cesium removal from Hanford tank waste. Two spherical RF formulations, prepared by varying curing temperature, were tested. Both resins had a tight particle size distribution and a high degree of sphericity. Small-scale column testing (on {approx}20-mL resin beds) was conducted evaluating the cesium load profile with AZ-102 simulated tank waste and the cesium elution profile using 0.5 M HNO3 eluant. The load and elution profiles were compared in side-by-side testing with ground-gel RF resin and SuperLig? 644, the Waste Treatment Plant baseline ion exchanger. Although capacity was not as high at the other resins tested, the spherical RF resin met plant cesium loading requirements with the AZ-102 simulant matrix. Excellent reproducibility of cesium load and elution was demonstrated over three process cycles with no evidence of degraded performance. Residual cesium on the resin beds after elution was nearly a factor of 10 lower than that of the ground-gel RF and SuperLig? 644.

Fiskum, Sandra K.; Blanchard, David L.; Steele, Marilyn J.; Thomas, Kathie K.; Trang-Le, Truc LT; Thorson, Murray R.

2006-08-01T23:59:59.000Z

278

Steam reforming as a method to treat Hanford underground storage tank (UST) wastes  

Science Conference Proceedings (OSTI)

This report summarizes a Sandia program that included partnerships with Lawrence Livermore National Laboratory and Synthetica Technologies, Inc. to design and test a steam reforming system for treating Hanford underground storage tank (UST) wastes. The benefits of steam reforming the wastes include the resolution of tank safety issues and improved radionuclide separations. Steam reforming destroys organic materials by first gasifying, then reacting them with high temperature steam. Tests indicate that up to 99% of the organics could be removed from the UST wastes by steam exposure. In addition, it was shown that nitrates in the wastes could be destroyed by steam exposure if they were first distributed as a thin layer on a surface. High purity alumina and nickel alloys were shown to be good candidates for materials to be used in the severe environment associated with steam reforming the highly alkaline, high nitrate content wastes. Work was performed on designing, building, and demonstrating components of a 0.5 gallon per minute (gpm) system suitable for radioactive waste treatment. Scale-up of the unit to 20 gpm was also considered and is feasible. Finally, process demonstrations conducted on non-radioactive waste surrogates were carried out, including a successful demonstration of the technology at the 0.1 gpm scale.

Miller, J.E.; Kuehne, P.B. [eds.] [and others

1995-07-01T23:59:59.000Z

279

Geochemistry and Distribution of Contaminants in the Vadose Zone of the Single-Shell Tank Waste Management Areas at the Hanford Site  

Science Conference Proceedings (OSTI)

This chapter provides a description of the geochemical processes that affect contaminant mobility in the vadose zone at the single-shell tank waste management areas located at the Hanford Site.

Cantrell, Kirk J.

2008-01-17T23:59:59.000Z

280

Flammable Gas Release Estimates for Modified Sluicing Retrieval of Waste from Selected Hanford Single-Shell Tanks  

DOE Green Energy (OSTI)

The high-level radioactive wastes in many single-shell tanks (SSTs) at the Hanford Site are to be retrieved by a modified sluicing method. Retrieval operations will hydraulically erode and dissolve the saltcake waste, and the resulting brine will then be pumped to a double-shell tank (DST). Waste gases residing in the solid waste matrix will be released into the tank headspace when the matrix is eroded or dissolved. These retained waste gases include the flammable species hydrogen, methane, and ammonia, and there is a concern that these flammable gases could produce a flammable mixture in the tank headspaces during the retrieval operations. This report combines conservative retained gas inventory estimates and tank data with anticipated waste retrieval rates to estimate the potential headspace flammability of selected SSTs during waste retrieval operations. The SSTs considered here are ten of the twelve 241-S farm tanks (tanks 241-S-107 and 241-S-111 are excluded from consideration here) and tank 241-U-107 (U-107).

Huckaby, James L.; Wells, Beric E.

2003-05-13T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Hanford Tanks 241-C-203 and 241 C 204: Residual Waste Contaminant Release Model and Supporting Data  

SciTech Connect

This report was revised in May 2007 to correct 90Sr values in Chapter 3. The changes were made on page 3.9, paragraph two and Table 3.10; page 3.16, last paragraph on the page; and Tables 3.21 and 3.31. The rest of the text remains unchanged from the original report issued in October 2004. This report describes the development of release models for key contaminants that are present in residual sludge remaining after closure of Hanford Tanks 241-C-203 (C-203) and 241-C-204 (C-204). The release models were developed from data generated by laboratory characterization and testing of samples from these two tanks. Key results from this work are (1) future releases from the tanks of the primary contaminants of concern (99Tc and 238U) can be represented by relatively simple solubility relationships between infiltrating water and solid phases containing the contaminants; and (2) high percentages of technetium-99 in the sludges (20 wt% in C-203 and 75 wt% in C-204) are not readily water leachable, and, in fact, are very recalcitrant. This is similar to results found in related studies of sludges from Tank AY-102. These release models are being developed to support the tank closure risk assessments performed by CH2M HILL Hanford Group, Inc., for the U.S. Department of Energy.

Deutsch, William J.; Krupka, Kenneth M.; Lindberg, Michael J.; Cantrell, Kirk J.; Brown, Christopher F.; Schaef, Herbert T.

2007-05-23T23:59:59.000Z

282

Performance evaluation of rotating pump jet mixing of radioactive wastes in Hanford Tanks 241-AP-102 and -104  

Science Conference Proceedings (OSTI)

The purpose of this study was to confirm the adequacy of a single mixer pump to fully mix the wastes that will be stored in Tanks 241-AP-102 and -104. These Hanford double-shell tanks (DSTs) will be used as staging tanks to receive low-activity wastes from other Hanford storage tanks and, in turn, will supply the wastes to private waste vitrification facilities for eventual solidification. The TEMPEST computer code was applied to Tanks AP-102 and -104 to simulate waste mixing generated by the 60-ft/s rotating jets and to determine the effectiveness of the single rotating pump to mix the waste. TEMPEST simulates flow and mass/heat transport and chemical reactions (equilibrium and kinetic reactions) coupled together. Section 2 describes the pump jet mixing conditions the authors evaluated, the modeling cases, and their parameters. Section 3 reports model applications and assessment results. The summary and conclusions are presented in Section 4, and cited references are listed in Section 5.

Onishi, Y.; Recknagle, K.P.

1998-07-01T23:59:59.000Z

283

Headspace vapor characterization of Hanford waste tank 241-U-109: Results from samples collected on 8/10/95  

DOE Green Energy (OSTI)

This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-109 (Tank U-109) At the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. This tank is on the Hydrogen Waste List. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases and total non-methane hydrocarbons is listed in a table. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples is also listed in the table. Detailed descriptions of the analytical results appear in the text.

Evans, J.C.; Thomas, B.L.; Pool, K.H.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

1996-05-01T23:59:59.000Z

284

ALUMINUM READINESS EVALUATION FOR ALUMINUM REMOVAL AND SODIUM HYDROXIDE REGENRATION FROM HANFORD TANK WASTE BY LITHIUM HYDROTALCITE PRECIPITATION  

SciTech Connect

A Technology Readiness Evaluation (TRE) performed by AREV A Federal Services, LLC (AFS) for Washington River Protection Solutions, LLC (WRPS) shows the lithium hydrotalcite (LiHT) process invented and patented (pending) by AFS has reached an overall Technology Readiness Level (TRL) of 3. The LiHT process removes aluminum and regenerates sodium hydroxide. The evaluation used test results obtained with a 2-L laboratory-scale system to validate the process and its critical technology elements (CTEs) on Hanford tank waste simulants. The testing included detailed definition and evaluation for parameters of interest and validation by comparison to analytical predictions and data quality objectives for critical subsystems. The results of the TRE would support the development of strategies to further mature the design and implementation of the LiHT process as a supplemental pretreatment option for Hanford tank waste.

SAMS TL; MASSIE HL

2011-01-27T23:59:59.000Z

285

Clean option: An alternative strategy for Hanford Tank Waste Remediation. Volume 2, Detailed description of first example flowsheet  

SciTech Connect

Disposal of high-level tank wastes at the Hanford Site is currently envisioned to divide the waste between two principal waste forms: glass for the high-level waste (HLW) and grout for the low-level waste (LLW). The draft flow diagram shown in Figure 1.1 was developed as part of the current planning process for the Tank Waste Remediation System (TWRS), which is evaluating options for tank cleanup. The TWRS has been established by the US Department of Energy (DOE) to safely manage the Hanford tank wastes. It includes tank safety and waste disposal issues, as well as the waste pretreatment and waste minimization issues that are involved in the ``clean option`` discussed in this report. This report describes the results of a study led by Pacific Northwest Laboratory to determine if a more aggressive separations scheme could be devised which could mitigate concerns over the quantity of the HLW and the toxicity of the LLW produced by the reference system. This aggressive scheme, which would meet NRC Class A restrictions (10 CFR 61), would fit within the overall concept depicted in Figure 1.1; it would perform additional and/or modified operations in the areas identified as interim storage, pretreatment, and LLW concentration. Additional benefits of this scheme might result from using HLW and LLW disposal forms other than glass and grout, but such departures from the reference case are not included at this time. The evaluation of this aggressive separations scheme addressed institutional issues such as: radioactivity remaining in the Hanford Site LLW grout, volume of HLW glass that must be shipped offsite, and disposition of appropriate waste constituents to nonwaste forms.

Swanson, J.L.

1993-09-01T23:59:59.000Z

286

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SUMMARY OF COMBINED THERMAL AND OPERATING LOADS WITH SEISMIC ANALYSIS  

SciTech Connect

This report summarizes the results of the Double-Shell Tank Thermal and Operating Loads Analysis (TaLA) combined with the Seismic Analysis. This combined analysis provides a thorough, defensible, and documented analysis that will become a part of the overall analysis of record for the Hanford double-shell tanks (DSTs). The bases of the analytical work presented herein are two ANSYS{reg_sign} finite element models that were developed to represent a bounding-case tank. The TaLA model includes the effects of temperature on material properties, creep, concrete cracking, and various waste and annulus pressure-loading conditions. The seismic model considers the interaction of the tanks with the surrounding soil including a range of soil properties, and the effects of the waste contents during a seismic event. The structural evaluations completed with the representative tank models do not reveal any structural deficiencies with the integrity of the DSTs. The analyses represent 60 years of use, which extends well beyond the current date. In addition, the temperature loads imposed on the model are significantly more severe than any service to date or proposed for the future. Bounding material properties were also selected to provide the most severe combinations. While the focus of the analyses was a bounding-case tank, it was necessary during various evaluations to conduct tank-specific analyses. The primary tank buckling evaluation was carried out on a tank-specific basis because of the sensitivity to waste height, specific gravity, tank wall thickness, and primary tank vapor space vacuum limit. For this analysis, the occurrence of maximum tank vacuum was classified as a service level C, emergency load condition. The only area of potential concern in the analysis was with the buckling evaluation of the AP tank, which showed the current limit on demand of l2-inch water gauge vacuum to exceed the allowable of 10.4 inches. This determination was based on analysis at the design waste temperature of 350 F and the full 60-year corrosion allowance on the tank wall of 0.060 inch. However, analysis at a more realistic temperature of 250 F or corrosion allowance of 0.025 inch results in an acceptable demand/capacity ratio according to the ASME code criteria. Thus, buckling of the primary tank is judged to be unlikely for the current lack of corrosion in the tanks, and the expectation that the maximum waste temperature will not exceed 210 F. The reinforced concrete structure was evaluated as specified by the American Concrete Institute (ACI) code requirements for nuclear safety-related structures (ACI-349). The demand was demonstrated to be lower than the capacity at all locations. Revision 1 is being issued to document changes to the anchor bolt evaluation. RPP-RPT-32237 Rev. 1, Hanford Double-Shell Tank Thermal and Seismic Project-Increased Liquid Level Analysis for 241AP Tank Farms, described changes to the anchor bolt modeling and evaluation which were implemented in response to the independent reviewer's comments. Similar changes have been made in the bounding tank analysis and are documented in RPP-RPT-28968 Rev. 1. The conclusions of the previous releases of this report remain unchanged.

MACKEY TC; DEIBLER JE; RINKER MW; JOHNSON KI; ABATT FG; KARRI NK; PILLI SP; STOOPS KL

2009-01-15T23:59:59.000Z

287

Report on the EH special review of occupational safety and health programs for the Hanford high-level waste tanks  

DOE Green Energy (OSTI)

This report documents a review of the occupational safety and health programs currently in effect at the tank farms located at the Hanford Reservation in Washington State. The review was undertaken by the Office of Environment, Safety and Health (EH) at the request of the Office of Environmental Restoration and Waste Management (EM) to determine whether issues important to worker safety and health have been properly identified, prioritized, and resolved. To carry out this task, four categories of safety and health activities were reviewed. The first category involved examination of management issues associated with the toxicity, flammability, and explosivity of gases and vapors generated by wastes. The second focused on waste tank characterization and technology programs that have been initiated at Hanford to identify, characterize and mitigate hazards associated with tanks generating hydrogen or containing ferrocyanides or organic compounds. The third evaluated worker safety and health programs necessary to support hazardous waste site operations it the tank farms. The fourth dealt with interim corrective actions currently in place, pending full implementation of site-specific safety and health programs to address waste vapor toxicity, flammability, and explosivity hazards.

Not Available

1992-11-01T23:59:59.000Z

288

Headspace vapor characterization of Hanford waste Tank 241-BX-110: Results from samples collected on 04/30/96  

DOE Green Energy (OSTI)

This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-BX-110 (Tank BX-110) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in a table. The three highest concentration analytes detected in SUMMA{trademark} canister and triple sorbent trap samples are also listed in the table. Detailed descriptions of the analytical results appear in the appendices.

Evans, J.C.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Silvers, K.L.

1997-01-01T23:59:59.000Z

289

Changes in the pore network structure of Hanford sediment after reaction with caustic tank wastes  

Science Conference Proceedings (OSTI)

At the former nuclear weapon production site in Hanford, WA, caustic radioactive tank waste leaks into subsurface sediments and causes dissolution of quartz and aluminosilicate minerals, and precipitation of sodalite and cancrinite. This work examines changes in pore structure due to these reactions in a previously-conducted column experiment. The column was sectioned and 2D images of the pore space were generated using backscattered electron microscopy and energy dispersive X-ray spectroscopy. A pre-precipitation scenario was created by digitally removing mineral matter identified as secondary precipitates. Porosity, determined by segmenting the images to distinguish pore space from mineral matter, was up to 0.11 less after reaction. Erosion-dilation analysis was used to compute pore and throat size distributions. Images with precipitation had more small and fewer large pores. Precipitation decreased throat sizes and the abundance of large throats. These findings agree with previous findings based on 3D X-ray CMT imaging, observing decreased porosity, clogging of small throats, and little change in large throats. However, 2D imaging found an increase in small pores, mainly in intragranular regions or below the resolution of the 3D images. Also, an increase in large pores observed via 3D imaging was not observed in the 2D analysis. Changes in flow conducting throats that are the key permeability-controlling features were observed in both methods.

Crandell, L. E.; Peters, Catherine A.; Um, Wooyong; Jones, Keith W.; Lindquist, W.Brent

2012-04-01T23:59:59.000Z

290

In situ determination of rheological properties and void fraction: Hanford Waste Tank 241-SY-103  

Science Conference Proceedings (OSTI)

This report presents the results of the operation of the void fraction instrument (VFI) and ball rheometer in Hanford Tank 241-SY-103. The two instruments were deployed through risers 17C and 22A in July and August 1995 to gather data on the gas content and rheology of the waste. The results indicate that the nonconvective sludge layer contains up to 12% void and an apparent viscosity of 104 to 105 cP with a yield strength less than 210 Pa. The convective layer measured zero void and had no measurable yield strength. Its average viscosity was about 45 cP, and the density was less than 1.5 g/cc. The average void fraction was 0.047 {plus_minus} 0.015 at riser 17C and 0.091 {plus_minus} 0.015 at riser 22A. The stored gas volume based on these void fraction measurements is 213 {plus_minus} 42 M{sup 3} at 1 atmosphere.

Shepard, C.L.; Stewart, C.W.; Alzheimer, J.M.; Terrones, G.; Chen, G. [Pacific Northwest Lab., Richland, WA (United States); Wilkins, N.E. [Westinghouse Hanford Co., Richland, WA (United States)

1995-11-01T23:59:59.000Z

291

Response of ethylene propylene diene monomer rubber (EPDM) to simulant Hanford tank waste  

Science Conference Proceedings (OSTI)

This report presents the findings of the Chemical Compatibility Program developed to evaluate plastic packaging components that may be incorporated in packaging mixed-waste forms for transportation. Consistent with the methodology outlined in this report, the author performed the second phase of this experimental program to determine the effects of simulant Hanford tank mixed wastes on packaging seal materials. That effort involved the comprehensive testing of five plastic liner materials in an aqueous mixed-waste simulant. The testing protocol involved exposing the materials to {approximately}143, 286, 571, and 3,670 krad of gamma radiation and was followed by 7-, 14-, 28-, 180-day exposures to the waste simulant at 18, 50, and 60 C. Ethylene propylene diene monomer (EPDM) rubber samples subjected to the same protocol were then evaluated by measuring seven material properties: specific gravity, dimensional changes, mass changes, hardness, compression set, vapor transport rates, and tensile properties. The author has determined that EPDM rubber has excellent resistance to radiation, this simulant, and a combination of these factors. These results suggest that EPDM is an excellent seal material to withstand aqueous mixed wastes having similar composition to the one used in this study.

NIGREY,PAUL J.

2000-02-01T23:59:59.000Z

292

Comprehensive testing to measure the response of butyl rubber to Hanford tank waste simulant  

Science Conference Proceedings (OSTI)

This report presents the findings of the Chemical Compatibility Program developed to evaluate plastic packaging components that may be incorporated in packaging mixed-waste forms for transportation. Consistent with the methodology outlined in this report, the authors performed the second phase of this experimental program to determine the effects of simulant Hanford tank mixed wastes on packaging seal materials. That effort involved the comprehensive testing of five plastic liner materials in an aqueous mixed-waste simulant. The testing protocol involved exposing the materials to {approximately}143, 286, 571, and 3,670 krad of gamma radiation and was followed by 7-, 14-, 28-, 180-day exposures to the waste simulant at 18, 50, and 60 C. Butyl rubber samples subjected to the same protocol were then evaluated by measuring seven material properties: specific gravity, dimensional changes, mass changes, hardness, compression set, vapor transport rates, and tensile properties. From the analyses, they determined that butyl rubber has relatively good resistance to radiation, this simulant, and a combination of these factors. These results suggest that butyl rubber is a relatively good seal material to withstand aqueous mixed wastes having similar composition to the one used in this study.

NIGREY,PAUL J.

2000-05-01T23:59:59.000Z

293

Mineral Dissolution and Secondary Precipitation on Quartz Sand in Simulated Hanford Tank Solutions Affecting Subsurface Porosity  

SciTech Connect

Highly alkaline nuclear waste solutions have been released from underground nuclear waste storage tanks and pipelines into the vadose zone at the U.S. Department of Energys Hanford Site in Washington, causing mineral dissolution and re-precipitation upon contact with subsurface sediments. High pH caustic NaNO3 solutions with and without dissolved Al were reacted with quartz sand through flow-through columns stepwise at 45, 51, and 89C to simulate possible reactions between leaked nuclear waste solution and primary subsurface mineral. Upon reaction, Si was released from the dissolution of quartz sand, and nitrate-cancrinite [Na8Si6Al6O24(NO3)2] precipitated on the quartz surface as a secondary mineral phase. Both steady-state dissolution and precipitation kinetics were quantified, and quartz dissolution apparent activation energy was determined. Mineral alteration through dissolution and precipitation processes results in pore volume and structure changes in the subsurface porous media. In this study, the column porosity increased up to 40.3% in the pure dissolution column when no dissolved Al was present in the leachate, whereas up to a 26.5% porosity decrease was found in columns where both dissolution and precipitation were observed because of the presence of Al in the input solution. The porosity change was also confirmed by calculation using the dissolution and precipitation rates and mineral volume changes.

Wang, Guohui; Um, Wooyong

2012-11-23T23:59:59.000Z

294

Geochemical data package for the Hanford immobilized low-activity tank waste performance assessment (ILAW PA)  

Science Conference Proceedings (OSTI)

Lockheed Martin Hanford Company (LMHC) is designing and assessing the performance of disposal facilities to receive radioactive wastes that are stored in single- and double-shell tanks at the Hanford Site. The preferred method of disposing of the portion that is classified as low-activity waste is to vitrify the liquid/slurry and place the solid product in near-surface, shallow-land burial facilities. The LMHC project to assess the performance of these disposal facilities is the Hanford Immobilized Low-Activity Tank Waste (ILAW) Performance Assessment (PA) activity. The goal of this project is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the porewater of the vadose zone. Pacific Northwest National Laboratory assists LMHC in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the disposal facility, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (K{sub d}) and the thermodynamic solubility product (K{sub sp}), respectively. In this data package, the authors approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. In future geochemical data packages, they will determine whether a more rigorous measure of solubility is necessary or warranted based on the dose predictions emanating from the ILAW 2001 PA and reviewers' comments. The K{sub d}s and solution concentration limits for each contaminant are direct inputs to subsurface flow and transport codes used to predict the performance of the ILAW system. In addition to the best-estimate K{sub d}s, a reasonable conservative value and a range are provided. They assume that K{sub d} values are log normally distributed over the cited ranges. Currently, they do not give estimates for the range in solubility limits or their uncertainty. However, they supply different values for both the K{sub d}s and solution concentration limits for different spatial zones in the ILAW system and supply time-varying K{sub d}s for the concrete zone, should the final repository design include concrete vaults or cement amendments to buffer the system pH.

DI Kaplan; RJ Serne

2000-02-24T23:59:59.000Z

295

SURFACE GEOPHYSICAL EXPLORATION DEVELOPING NONINVASIVE TOOLS TO MONITOR PAST LEAKS AROUND HANFORD TANK FARMS  

SciTech Connect

A characterization program has been developed at Hanford to image past leaks in and around the underground storage tank facilities. The program is based on electrical resistivity, a geophysical technique that maps the distribution of electrical properties of the subsurface. The method was shown to be immediately successful in open areas devoid of underground metallic infrastructure, due to the large contrast in material properties between the highly saline waste and the dry sandy host environment. The results in these areas, confirmed by a limited number of boreholes, demonstrate a tendency for the lateral extent of the underground waste plume to remain within the approximate footprint of the disposal facility. In infrastructure-rich areas, such as tank farms, the conventional application of electrical resistivity using small point-source surface electrodes initially presented a challenge for the resistivity method. The method was then adapted to directly use the buried infrastructure as electrodes for both transmission of electrical current and measurements of voltage. For example, steel-cased wells that surround the tanks were used as long electrodes, which helped to avoid much of the infrastructure problems. Overcoming the drawbacks of the long electrode method has been the focus of our work over the past seven years. The drawbacks include low vertical resolution and limited lateral coverage. The lateral coverage issue has been improved by supplementing the long electrodes with surface electrodes in areas devoid of infrastructure. The vertical resolution has been increased by developing borehole electrode arrays that can fit within the small-diameter drive casing of a direct push rig. The evolution of the program has led to some exceptional advances in the application of geophysical methods, including logistical deployment of the technology in hazardous areas, development of parallel processing resistivity inversion algorithms, and adapting the processing tools to accommodate electrodes of all shapes and locations. The program is accompanied by a full set of quality assurance procedures that cover the layout of sensors, measurement strategies, and software enhancements while insuring the integrity of stored data. The data have been shown to be useful in identifying previously unknown contaminant sources and defining the footprint of precipitation recharge barriers to retard the movement of existing contamination.

MYERS DA; RUCKER DF; LEVITT MT; CUBBAGE B; NOONAN GE; MCNEILL M; HENDERSON C

2011-06-17T23:59:59.000Z

296

Screening values for Non-Carcinogenic Hanford Waste Tank Vapor Chemicals that Lack Established Occupational Exposure Limits  

SciTech Connect

Over 1,500 different volatile chemicals have been reported in the headspaces of tanks used to store high-level radioactive waste at the U.S. Department of Energy's Hanford Site. Concern about potential exposure of tank farm workers to these chemicals has prompted efforts to evaluate their toxicity, identify chemicals that pose the greatest risk, and incorporate that information into the tank farms industrial hygiene worker protection program. Established occupation exposure limits for individual chemicals and petroleum hydrocarbon mixtures have been used elsewhere to evaluate about 900 of the chemicals. In this report headspace concentration screening values were established for the remaining 600 chemicals using available industrial hygiene and toxicological data. Screening values were intended to be more than an order of magnitude below concentrations that may cause adverse health effects in workers, assuming a 40-hour/week occupational exposure. Screening values were compared to the maximum reported headspace concentrations.

Poet, Torka S.; Mast, Terryl J.; Huckaby, James L.

2006-02-06T23:59:59.000Z

297

Mathematical modeling of mixer pump performance for agitation of radioactive slurries in one-million-gallon underground storage tanks at Hanford  

SciTech Connect

The objective of this work is to analyze the Hanford Waste Vitrification Project (HWVP) feed preparation tank mixing pump agitation design. This was accomplished by (1) reviewing mixing pump characteristics, (2) performing computer modeling of jet mixing and particulate material transport, (3) evaluating the propensity of the tank and mixing pump design to maintain particulate material in the tank in a uniformly mixed state, and (4) identifying important design parameters required to ensure optimum homogeneity and solids content during batch transfers.

Bamberger, J.A.; Eyler, L.L.; Dodge, R.E.

1993-04-01T23:59:59.000Z

298

Evaluation of mitigation strategies in Facility Group 1 double-shell flammable-gas tanks at the Hanford Site  

SciTech Connect

Radioactive nuclear waste at the Hanford Site is stored in underground waste storage tanks at the site. The tanks fall into two main categories: single-shell tanks (SSTs) and double-shell tanks (DSTs). There are a total of 149 SSTs and 28 DSTs. The wastes stored in the tanks are chemically complex. They basically involve various sodium salts (mainly nitrite, nitrate, carbonates, aluminates, and hydroxides), organic compounds, heavy metals, and various radionuclides, including cesium, strontium, plutonium, and uranium. The waste is known to generate flammable gas (FG) [hydrogen, ammonia, nitrous oxide, hydrocarbons] by complex chemical reactions. The process of gas generation, retention, and release is transient. Some tanks reach a quasi-steady stage where gas generation is balanced by the release rate. Other tanks show continuous cycles of retention followed by episodic release. There currently are 25 tanks on the Flammable Gas Watch List (FGWL). The objective of this report is to evaluate possible mitigation strategies to eliminate the FG hazard. The evaluation is an engineering study of mitigation concepts for FG generation, retention, and release behavior in Tanks SY-101, AN-103, AN 104, An-105, and Aw-101. Where possible, limited quantification of the effects of mitigation strategies on the FG hazard also is considered. The results obtained from quantification efforts discussed in this report should be considered as best-estimate values. Results and conclusions of this work are intended to help in establishing methodologies in the contractor`s controls selection analysis to develop necessary safety controls for closing the FG unreviewed safety question. The general performance requirements of any mitigation scheme are discussed first.

Unal, C.; Sadasivan, P.; Kubic, W.L.; White, J.R.

1997-11-01T23:59:59.000Z

299

HANFORD DST THERMAL & SEISMIC PROJECT ANSYS BENCHMARK ANALYSIS OF SEISMIC INDUCED FLUID STRUCTURE INTERACTION IN A HANFORD DOUBLE SHELL PRIMARY TANK  

Science Conference Proceedings (OSTI)

M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratories (PNNL) to perform seismic analysis of the Hanford Site Double-Shell Tanks (DSTs) in support of a project entitled ''Double-Shell Tank (DSV Integrity Project-DST Thermal and Seismic Analyses)''. The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST System at Hanford in support of Tri-Party Agreement Milestone M-48-14. The work described herein was performed in support of the seismic analysis of the DSTs. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). The overall seismic analysis of the DSTs is being performed with the general-purpose finite element code ANSYS. The overall model used for the seismic analysis of the DSTs includes the DST structure, the contained waste, and the surrounding soil. The seismic analysis of the DSTs must address the fluid-structure interaction behavior and sloshing response of the primary tank and contained liquid. ANSYS has demonstrated capabilities for structural analysis, but the capabilities and limitations of ANSYS to perform fluid-structure interaction are less well understood. The purpose of this study is to demonstrate the capabilities and investigate the limitations of ANSYS for performing a fluid-structure interaction analysis of the primary tank and contained waste. To this end, the ANSYS solutions are benchmarked against theoretical solutions appearing in BNL 1995, when such theoretical solutions exist. When theoretical solutions were not available, comparisons were made to theoretical solutions of similar problems and to the results from Dytran simulations. The capabilities and limitations of the finite element code Dytran for performing a fluid-structure interaction analysis of the primary tank and contained waste were explored in a parallel investigation (Abatt 2006). In conjunction with the results of the global ANSYS analysis reported in Carpenter et al. (2006), the results of the two investigations will be compared to help determine if a more refined sub-model of the primary tank is necessary to capture the important fluid-structure interaction effects in the tank and if so, how to best utilize a refined sub-model of the primary tank. Both rigid tank and flexible tank configurations were analyzed with ANSYS. The response parameters of interest are total hydrodynamic reaction forces, impulsive and convective mode frequencies, waste pressures, and slosh heights. To a limited extent: tank stresses are also reported. The results of this study demonstrate that the ANSYS model has the capability to adequately predict global responses such as frequencies and overall reaction forces. Thus, the model is suitable for predicting the global response of the tank and contained waste. On the other hand, while the ANSYS model is capable of adequately predicting waste pressures and primary tank stresses in a large portion of the waste tank, the model does not accurately capture the convective behavior of the waste near the free surface, nor did the model give accurate predictions of slosh heights. Based on the ability of the ANSYS benchmark model to accurately predict frequencies and global reaction forces and on the results presented in Abatt, et al. (2006), the global ANSYS model described in Carpenter et al. (2006) is sufficient for the seismic evaluation of all tank components except for local areas of the primary tank. Due to the limitations of the ANSYS model in predicting the convective response of the waste, the evaluation of primary tank stresses near the waste free surface should be supplemented by results from an ANSYS sub-model of the primary tank that incorporates pressures from theoretical solutions or from Dytran solutions. However, the primary tank is expected to have low demand to capacity ratios in the upper wall. Moreover, due to the less than desired mesh resolution in the primary tank knuckle of the global ANSYS model, the evaluation of the primary tank stresses in the lo

MACKEY, T.C.

2006-03-14T23:59:59.000Z

300

STEADY STATE FLAMMABLE GAS RELEASE RATE CALCULATION & LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE [SEC 1 & 2  

DOE Green Energy (OSTI)

Flammable gases such as hydrogen, ammonia, and methane are observed in the tank dome space of the Hanford Site high-level waste tanks. This report assesses the steady-state flammability level under normal and off-normal ventilation conditions in the tank dome space for 177 double-shell tanks and single-shell tanks at the Hanford Site. The steady-state flammability level was estimated from the gas concentration of the mixture in the dome space using estimated gas release rates, Le Chatelier's rule and lower flammability limits of fuels in an air mixture. A time-dependent equation of gas concentration, which is a function of the gas release and ventilation rates in the dome space, has been developed for both soluble and insoluble gases. With this dynamic model, the time required to reach the specified flammability level at a given ventilation condition can be calculated. In the evaluation, hydrogen generation rates can be calculated for a given tank waste composition and its physical condition (e.g., waste density, waste volume, temperature, etc.) using the empirical rate equation model provided in Empirical Rate Equation Model and Rate Calculations of Hydrogen Generation for Hanford Tank Waste, HNF-3851. The release rate of other insoluble gases and the mass transport properties of the soluble gas can be derived from the observed steady-state gas concentration under normal ventilation conditions. The off-normal ventilation rate is assumed to be natural barometric breathing only. A large body of data is required to do both the hydrogen generation rate calculation and the flammability level evaluation. For tank waste that does not have sample-based data, a statistical-based value from probability distribution regression was used based on data from tanks belonging to a similar waste group. This report (Revision 3) updates the input data of hydrogen generation rates calculation for 177 tanks using the waste composition information in the Best-Basis Inventory Detail Report in the Tank Waste Information Network System, and the waste temperature data in the Surveillance Analysis Computer System (SACS) (dated July 2003). However, the release rate of methane, ammonia, and nitrous oxide is based on the input data (dated October 1999) as stated in Revision 0 of this report. Scenarios for adding waste to existing waste levels (dated July 2003) have been studied to determine the gas generation rates and the effect of smaller dome space on the flammability limits to address the issues of routine water additions and other possible waste transfer operations. In the flammability evaluation with zero ventilation, the sensitivity to waste temperature and to water addition was calculated for double-shell tanks 241-AY-102, 241-AN-102,241-AZ-101,241-AN-107,241-AY-101 and 241-AZ-101. These six have the least margin to flammable conditions among 28 double-shell tanks.

HU, T.A.

2003-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Solid Radwaste Radionuclide Measurements  

Science Conference Proceedings (OSTI)

Methods employed at U.S. nuclear power plants to assay low level solid radwaste were reviewed to identify those aspects of the assay process that have substantial improvement potential and to develop recommendations on programs to develop more effective methods. Discussions were held on practices at 41 nuclear stations and in-depth reviews were performed at 14 sites. Recommendations for future efforts are provided, particularly with reference to demonstrating adherence to proposed regulations.

1982-11-01T23:59:59.000Z

302

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT INCREASED LIQUID LEVEL ANALYSIS FOR 241-AP TANK FARMS  

SciTech Connect

The essential difference between Revision 1 and the original issue of this report is the analysis of the anchor bolts that tie the steel dome of the primary tank to the concrete tank dome. The reevaluation of the AP anchor bolts showed that (for a given temperature increase) the anchor shear load distribution did not change significantly from the initially higher stiffness to the new secant shear stiffness. Therefore, the forces and displacements of the other tank components such as the primary tanks stresses, secondary liner strains, and concrete tank forces and moments also did not change significantly. Consequently, the revised work in Revision 1 focused on the changes in the anchor bolt responses and a full reevaluation of all tank components was judged to be unnecessary.

TC MACKEY; JE DEIBLER; MW RINKER; KI JOHNSON; SP PILLI; NK KARRI; FG ABATT; KL STOOPS

2009-01-14T23:59:59.000Z

303

Selection of AT-Tank Analysis Equipment for Determining Completion of Mixing and Particle Concentration in Hanford Waste Tanks  

SciTech Connect

This document will describe the functions and requirements of the at-tank analysis system concept developed by the Robotics Technology Development Program (RTDP) and Berkeley Instruments. It will discuss commercially available at-tank analysis equipment, and compare those that meet the stated functions and requirements. This is followed by a discussion of the considerations used in the selection of instrumentation for the concept design, and an overall description of the proposed at-tank analysis system.

Dodson, M.G.; Ozanich, R.M.; Bailey, S.A.

1999-06-10T23:59:59.000Z

304

THE APPLICATION OF ELECTROCHEMICAL NOISE BASED CORROSION MONITORING TO NUCLEAR WASTE TANK VAPOR SPACE ENVIRONMENTS AT THE HANFORD SITE  

Science Conference Proceedings (OSTI)

Vapor space corrosion data collected by electrochemical noise (EN) based corrosion probes installed in double shell tanks (DSTs) at the Department of Energy's Hanford Site in Richland, Washington have historically been characterized by surprisingly high levels in current. In late 2003, a program was established to assess the significance of archived Hanford DST vapor space EN data. This program showed that the high vapor space current levels are likely the result of crevice corrosion on the vapor space electrodes. The design of DST vapor space electrodes provides tight metal-to-metal and gaskeito-metal interfaces necessary for this type of localized corrosion to occur. In-tank activities (splashing, etc.), or more likely condensation of water vapor in the vapor space, provide the necessary moisture. Because crevice corrosion appears to be active on the vapor space EN electronics, data collected from these electrodes are not likely to be applicable to the large flat metal surfaces that make up the bulk of the DST domes and upper walls. The data do, however, indicate that conditions in the DST vapor spaces are conducive to accelerated crevice corrosion at creviced areas in the tank vapor space (overlapping joints, riser interfaces, equipment penetrations, etc.) under high humidity conditions.

EDGEMON, G.L.

2005-04-04T23:59:59.000Z

305

EVALUATION OF THE INTEGRATED SOLUBILITY MODEL, A GRADED APPROACH FOR PREDICTING PHASE DISTRIBUTION IN HANFORD TANK WASTE  

SciTech Connect

The mission of the DOE River Protection Project (RPP) is to store, retrieve, treat and dispose of Hanford's tank waste. Waste is retrieved from the underground tanks and delivered to the Waste Treatment and Immobilization Plant (WTP). Waste is processed through a pretreatment facility where it is separated into low activity waste (LAW), which is primarily liquid, and high level waste (HLW), which is primarily solid. The LAW and HLW are sent to two different vitrification facilities and glass canisters are then disposed of onsite (for LAW) or shipped off-site (for HLW). The RPP mission is modeled by the Hanford Tank Waste Operations Simulator (HTWOS), a dynamic flowsheet simulator and mass balance model that is used for mission analysis and strategic planning. The integrated solubility model (ISM) was developed to improve the chemistry basis in HTWOS and better predict the outcome of the RPP mission. The ISM uses a graded approach to focus on the components that have the greatest impact to the mission while building the infrastructure for continued future improvement and expansion. Components in the ISM are grouped depending upon their relative solubility and impact to the RPP mission. The solubility of each group of components is characterized by sub-models of varying levels of complexity, ranging from simplified correlations to a set of Pitzer equations used for the minimization of Gibbs Energy.

PIERSON KL; BELSHER JD; SENIOW KR

2012-10-19T23:59:59.000Z

306

A Value of Information approach to data quality objectives for the Hanford high-level waste tanks  

SciTech Connect

This report summarizes a Pacific Northwest Laboratory review of the organic-nitrate reaction safety issue in the Hanford single-shell tanks. This study employed a decision analytic method known as Value of Information (VOI). VOI analysis is a special form of decision analysis that has an information collection alternative as one of the initial decision choices. This type of decision analysis, therefore results in the ability to specify the preferred information collection alternative, taking into account all information gathering and other relevant alternatives. For example, the risk reduction benefit associated with further sampling to quantify total organic carbon inventory or to improve information on energetics can be compared to the risk reduction benefit of better temperature monitoring, operational restrictions, or mitigation by moisture control. This approach allows freedom from built-in assumptions, e.g., that all tanks must be sampled to some degree or that all tanks must be deemed intrinsically safe by some means or another. It allows for each tank management decision to be judged in terms of risk reduction from the current state of affairs, and for that state of affairs to be continuously updated to incorporate new information on tank contents, the phenomenology of safety issues, or the effectiveness of mitigation schemes.

Wood, T.W.; Hunter, V.L. [Pacific Northwest Lab., Richland, WA (United States); Ulvila, J.W. [Decision Science Associates (United States)

1995-02-01T23:59:59.000Z

307

Minutes of the Tank Waste Science Panel meeting July 9--1, 1991. Hanford Tank Safety Project  

Science Conference Proceedings (OSTI)

The fifth meeting of the Tank Waste Science Panel was held July 9--11, 1991, in Atlanta, Georgia. The subject areas included the generation, retention, and release of gases from Tank 241-SY-101 and the chemistry of ferrocyanide wastes.

Strachan, D.M. [comp.

1992-04-01T23:59:59.000Z

308

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT DYTRAN BENCHMARK ANALYSIS OF SEISMICALLY INDUCED FLUID STRUCTURE INTERACTION IN FLAT TOP TANKS  

SciTech Connect

The work reported in this document was performed in support of a project entitled ''Double-Shell Tank (DST) Integrity Project - DST Thermal and Seismic Analyses''. The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST System at Hanford. The work described herein was performed in support of the seismic analysis of the DSTs. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). The work herein was motivated by review comments from a Project Review Meeting held on March 20-21, 2006. One of the recommendations from that meeting was that the effects of the interaction between the tank liquid and the roof be further studied (Rinker, Deibler, Johnson, Karri, Pilli, Abatt, Carpenter, and Hendrix - Appendix E of RPP-RPT-28968, Rev. 1). The reviewers recommended that solutions be obtained for seismic excitation of flat roof tanks containing liquid with varying headspace between the top of the liquid and the tank roof. It was recommended that the solutions be compared with simple, approximate procedures described in BNL (1995) and Malhotra (2005). This report documents the results of the requested studies and compares the predictions of Dytran simulations to the approximate procedures in BNL (1995) and Malhotra (2005) for flat roof tanks. The four cases analyzed all employed a rigid circular cylindrical flat top tank with a radius of 450 in. and a height of 500 in. The initial liquid levels in the tank were 460,480,490, and 500 in. For the given tank geometry and the selected seismic input, the maximum unconstrained slosh height of the liquid is slightly greater than 25 in. Thus, the initial liquid level of 460 in. represents an effectively roofless tank, the two intermediate liquid levels lead to intermittent interaction between the liquid and tank roof, and the 500 in. liquid level represents a completely full tank with no sloshing. Although this work was performed in support of the seismic analysis of the Hanford DSTs, the tank models in this study are for an idealized flat top configuration. Moreover, the liquid levels used in the present models are for study purposes only and are independent of the actual operating levels of the DSTs. The response parameters that are evaluated in this study are the total hydrodynamic reaction forces, the peak convective hydrodynamic forces, the fundamental convective frequencies, the liquid pressures, and peak slosh heights. The results show that the Dytran solutions agree well with the known solutions for the roofless tank and completely full tank. At the two intermediate liquid levels, there are some significant differences between the Dytran results and the approximate estimates. The results show that the estimates of peak hydrodynamic reaction forces appearing in BNL (1995) and Malhotra (2005) are reasonable and generally conservative relative to the Dytran solutions. At the 460 and 480 in. liquid levels, Dytran underestimates the convective component of the reaction force compared to the estimated in BNL (1995) and Malhotra (2005), but the convective component of the reaction force is small relative to the total reaction force. At the 490 in. liquid levels, the peak convective reaction force is more than twice as large as predicted by the approximate methods in BNL (1995) and Malhotra (2005). All three methods give similar answers for the fundamental convective frequency at the 460 and 480 in. liquid levels, but the Dytran solution indicates a significant increase in the apparent convective frequency at the 490 in. liquid level that is caused by the interaction with the roof. The peak wall pressures in the tank at the two intermediate liquid levels are essentially the same as for a roofless tank in the lower two-thirds of the tank wall, but diverge from that solution in the upper third of the tank wall. The estimates of peak wall pressures appearing in BNL (1995) are quite conservative lower in the tank, but may underestimate the peak wall pressures closer to the tank roof. Finally, the peak roof pre

MACKEY, T.C.

2007-02-16T23:59:59.000Z

309

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT ESTABLISHMENT OF METHODOLOGY FOR TIME DOMAIN SOIL STRUCTURE INTERACTION ANALYSIS OF HANFORD DST  

Science Conference Proceedings (OSTI)

M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratories (PNNL) to perform seismic analysis of the Hanford Site Double-Shell Tanks (DSTs) in support of a project entitled ''Double-Shell Tank DSV Integrity Project-DST Thermal and Seismic Analyses''. The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST System at Hanford in support of Tri-Party Agreement Milestone M-48-14. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). The work statement provided to M&D (PNNL 2003) required that the seismic analysis of the DST assess the impacts of potentially non-conservative assumptions in previous analyses and account for the additional soil mass due to the as-found soil density increase, the effects of material degradation, additional thermal profiles applied to the full structure including the soil-structure response with the footings, the non-rigid (low frequency) response of the tank roof, the asymmetric seismic-induced soil loading, the structural discontinuity between the concrete tank wall and the support footing and the sloshing of the tank waste. The seismic analysis considers the interaction of the tank with the surrounding soil, and the effects of the primary tank contents. The DST and the surrounding soil are modeled as a system of finite elements. The depth and width of the soil incorporated into the analysis model are sufficient to obtain appropriately accurate analytical results. The analyses required to support the work statement differ from previous analysis of the DSTs in that the soil-structure interaction (SSI) model includes several (nonlinear) contact surfaces in the tank structure, and the contained waste must be modeled explicitly in order to capture the fluid-structure interaction behavior between the primary tank and contained waste. Soil-structure interaction analyses are traditionally solved in the frequency domain, but frequency domain analysis is limited to systems with linear responses. The nonlinear character of the coupled SSI model and tank structural model requires that the seismic analysis be solved in the time domain. However, time domain SSI analysis is somewhat nontraditional and requires that the appropriate methodology be developed and demonstrated. Moreover, the analysis of seismically induced fluid-structure interaction between the explicitly modeled waste and the primary tank must be benchmarked against known solutions to simpler problems before being applied to the more complex analysis of the DSTs. The objective of this investigation is to establish the methodology necessary to perform the required SSI analysis of the DSTs in the time domain. Specifically, the analysis establishes the capabilities and limitations of the time domain codes ANSYS and Dytran for performing seismic SSI analysis of the DSTs. The benchmarking of the codes Dytran and ANSYS for performing seismically induced fluid-structure interaction (FSI) between the contained waste and the DST primary tank are documented in Abatt (2006) and Carpenter and Abatt (2006), respectively. The results of those two studies show that both codes have the capability to analyze the fluid-structure interaction behavior of the primary tank and contained waste. As expected, Dytran appears to have more robust capabilities for FSI analysis. The ANSYS model used in that study captures much of the FSI behavior, but does have some limitations for predicting the convective response of the waste and possibly the response of the waste in the knuckle region of the primary tank. While Dytran appears to have somewhat stronger capabilities for the analysis of the FSI behavior in the primary tank, it is more practical for the overall analysis to use ANSYS. Thus, Dytran served the purpose of helping to identify limitations in the ANSYS FSI analysis so that those limitations can be addressed in the structural evaluation of the primary tank. The limitations of ANSYS for predicting the details of the convective

MACKEY, T.C.

2006-03-14T23:59:59.000Z

310

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SENSITIVITY OF DOUBLE SHELL DYNAMIC RESPONSE TO THE WASTE ELASTIC PROPERTIES  

SciTech Connect

The purpose of this study was to determine the sensitivity of the dynamic response of the Hanford double-shell tanks (DSTs) to the assumptions regarding the constitutive properties of the contained waste. In all cases, the waste was modeled as a uniform linearly elastic material. The focus of the study was on the changes in the modal response of the tank and waste system as the extensional modulus (elastic modulus in tension and compression) and shear modulus of the waste were varied through six orders of magnitude. Time-history analyses were also performed for selected cases and peak horizontal reaction forces and axial stresses at the bottom of the primary tank were evaluated. Because the analysis focused on the differences in the responses between solid-filled and liquid-filled tanks, it is a comparative analysis rather than an analysis of record for a specific tank or set of tanks. The shear modulus was varied between 4 x 10{sup 3} Pa and 4.135 x 10{sup 9} Pa. The lowest value of shear modulus was sufficient to simulate the modal response of a liquid-containing tank, while the higher values are several orders of magnitude greater than the upper limit of expected properties for tank contents. The range of elastic properties used was sufficient to show liquid-like response at the lower values, followed by a transition range of semi-solid-like response to a clearly identifiable solid-like response. It was assumed that the mechanical properties of the tank contents were spatially uniform. Because sludge-like materials are expected only to exist in the lower part of the tanks, this assumption leads to an exaggeration of the effects of sludge-like materials in the tanks. The results of the study show that up to a waste shear modulus of at least 40,000 Pa, the modal properties of the tank and waste system are very nearly the same as for the equivalent liquid-containing tank. This suggests that the differences in critical tank responses between liquid-containing tanks and tanks containing sludge-like materials having a shear modulus not exceeding 40,000 Pa are unlikely to be greater than those due to the uncertainties involved in the definition of the design ground motion or in the properties of the tank-waste system. This is the fundamental conclusion of the study. The study also shows that increasing the waste extensional modulus and shear modulus does not lead to increased mass participation at the impulsive frequency of the liquid-containing system. Instead, increasing the waste stiffness eventually leads to fundamental changes in the modal properties including an increase in the fundamental system frequency.

MACKEY TC; ABATT FG; JOHNSON KI

2009-01-16T23:59:59.000Z

311

TESTING VAPOR SPACE AND LIQUID-AIR INTERFACE CORROSION IN SIMULATED ENVIRONMENTS OF HANFORD DOUBLE-SHELLED TANKS  

Science Conference Proceedings (OSTI)

Electrochemical coupon testing were performed on 6 Hanford tank solution simulants and corresponding condensate simulants to evaluate the susceptibility of vapor space and liquid/air interface corrosion. Additionally, partial-immersion coupon testing were performed on the 6 tank solution simulants to compliment the accelerated electrochemical testing. Overall, the testing suggests that the SY-102 high nitrate solution is the most aggressive of the six solution simulants evaluated. Alternatively, the most passive solution, based on both electrochemical testing and coupon testing, was AY-102 solution. The presence of ammonium nitrate in the simulants at the lowest concentration tested (0.001 M) had no significant effect. At higher concentrations (0.5 M), ammonium nitrate appears to deter localized corrosion, suggesting a beneficial effect of the presence of the ammonium ion. The results of this research suggest that there is a threshold concentration of ammonium ions leading to inhibition of corrosion, thereby suggesting the need for further experimentation to identify the threshold.

Hoffman, E.

2013-05-30T23:59:59.000Z

312

Initial report on the application of laser ablation - inductively coupled plasma mass spectrometry for the analysis of radioactive Hanford Tank Waste materials  

Science Conference Proceedings (OSTI)

Initial LA/MS analyses of Hanford tank waste samples were performed successfully using laboratory and hot cell LA/MS instrumentation systems. The experiments described in this report have demonstrated that the LA/MS data can be used to provide rapid analysis of solid, radioactive Hanford tank waste samples to identify major, minor, and trace constituents (elemental and isotopic) and fission products and radioactive isotopes. The ability to determine isotopic constituents using the LA/MS method yielded significant advantages over ICP/AES analysis by providing valuable information on fission products and radioactive constituents.

Smith, M.R.; Hartman, J.S.; Alexander, M.L.; Mendoza, A.; Hirt, E.H.; Stewart, T.L.; Hansen, M.A.; Park, W.R.; Peters, T.J.; Burghard, B.J.

1996-12-01T23:59:59.000Z

313

Initial laboratory studies into the chemical and radiological aging of organic materials in underground storage tanks at the Hanford Complex  

SciTech Connect

The underground storage tanks at the Hanford Complex contain wastes generated over many years from plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct bearing on several specific safety issues, including potential energy releases from these tanks. The major portion of organic materials that have been added to the tanks consists of tributyl phosphate, dibutyl phosphate, butyl alcohol, hexone (methyl isobutyl ketone), normal paraffin hydrocarbons (NPH), ethylenediaminetetraacetic acid (EDTA), hydroxyethylethylenediaminetriadetic acid (HEDTA), other complexants, and lesser quantities of ion exchange polymers and minor organic compounds. A study of how thermal and radiological processes that may have changed the composition of organic tanks constituents has been initiated after a review of the open literature revealed little information was available about the rates and products of these processes under basic pH conditions. This paper will detail the initial findings as they relate to gas generation, e.g. H{sub 2}, CO, NH{sub 3}, CH{sub 4}, and to changes in the composition of the organic and inorganic components brought about by ``Aging`` processes.

Samuels, W.D.; Camaioni, D.M. [Pacific Northwest Lab., Richland, WA (United States); Babad, H. [Westinghouse Hanford Co., Richland, WA (United States)

1994-03-01T23:59:59.000Z

314

Structural analysis and evaluation of a mixer pump in a double-shell tank at the Hanford Site  

DOE Green Energy (OSTI)

The double-shell waste tank 241-SY-101 is a 1,000,000 gallon tank used to store radioactive waste at the Hanford Site near Richland, Washington. With time the waste has formed two layers of sludge, a convective and a nonconvective layer. In addition, a crest has formed over the surface of the waste, isolating the convective layer from the vapor space. Ongoing reactions in the waste cause a buildup of hydrogen molecules that become trapped within the nonconvective layer and under the crust. Over time, this hydrogen buildup increases pressure on the crest from beneath. Every 100 to 140 days, the pressure is released when the crust lifts upward in what is called a waste rollover. To prevent the release of a large volume of hydrogen to the vapor space, a mixer pump has been designed to be installed in the tank to circulate the waste and reduce or prevent the hydrogen buildup. The structural analysis and evaluation designed as part of the hydrogen mitigation test process and presented herein addresses the response of the mixer pump and the tank dome resulting from expected operational and design loads. The loads include deadweight, waste rollover, asymmetric thrust, and pump vibration, as well as seismic loads. The seismically induced loads take into consideration both the convective and the impulsive effects of the waste-filled tank. The structural evaluations were performed in accordance with applicable national codes and standards. The qualification of the mixer pump required the design of a unique mounting assembly to transfer the loads from the pump to the surrounding soil without overstressing the structural components such as the dome penetration riser. Also, special consideration was given to minimize the additional stresses in the already stressed concrete tank dome.

Rezvani, M.A.; Strehlow, J.P. [Westinghouse Hanford Co., Richland, WA (United States); Baliga, R. [ADVENT Engineering Services, Inc., San Ramon, CA (United States)

1993-08-01T23:59:59.000Z

315

Action plan for response to abnormal conditions in Hanford high level radioactive liquid waste storage tanks containing flammable gases. Revision 1  

DOE Green Energy (OSTI)

Radioactive liquid waste tends to produce hydrogen as a result of the interaction of gamma radiation and water. In tanks containing organic chelating agents, additional hydrogen gas as well as nitrous oxide and ammonia can be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site, contain waste that retains the gases produced in them until large quantities are released rapidly to the tank vapor space. Tanks filled to near capacity have relatively little vapor space; therefore, if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture may result. The most notable waste tank with a flammable gas problem is tank 241-SY-101. Waste in this tank has occasionally released enough flammable gas to burn if an ignition source had been present inside of the tank. Several other waste tanks exhibit similar behavior to a lesser magnitude. Administrative controls have been developed to assure that these Flammable Gas Watch List tanks are safely maintained. Responses have also been developed for off-normal conditions which might develop in these tanks. In addition, scientific and engineering studies are underway to further understand and mitigate the behavior of the Flammable Gas Watch List tanks.

Sherwood, D.J.

1994-03-01T23:59:59.000Z

316

Organic reactivity analysis in Hanford single-shell tanks: Experimental and modeling basis for an expanded safety criterion  

SciTech Connect

De-spite demonstrated safe storage in terms of chemical stability of the Hanford high level waste for many decades, including decreasing waste temperatures and continuing aging of chemicals to less energetic states, concerns continue relative to assurance of long-term safe storage. Review of potential chemical safety hazards has been of particular recent interest in response to serious incidents within the Nuclear Weapons Complexes in the former Soviet Union (the 1957 Kyshtym and the 1993 Tomsk-7 incidents). Based upon an evaluation of the extensive new information and understanding that have developed over the last few years, it is concluded that the Hanford waste is stored safely and that concerns related to potential chemical safety hazards are not warranted. Spontaneous bulk runaway reactions of the Kyshtym incident type and other potential condensed-phase propagating reactions can be ruled out by assuring appropriate tank operating controls are in place and by limiting tank intrusive activities. This paper summarizes the technical basis for this position.

Fauske, H. [Fauske and Associates, Inc. (United States); Grigsby, J.M. [G & P Consulting, Inc. (United States); Turner, D.A.; Babad, H.; Meacham, J.E. [Westinghouse Hanford Co., Richland, WA (United States)

1996-01-01T23:59:59.000Z

317

One System Integreated Project Team Progress in Coordinating Hanford Tank Farms and the Waste Treatment Plant - 14214  

SciTech Connect

The One System Integrated Project Team (IPT) was formed at the Hanford Site in late 2011 as a way to improve coordination and itegration between the Hanford Tank Waste Treatment and Immobilization Plant (WTP) and the Tank Operations Contractor (TOC) on interfaces between the two projects, and to eliminate duplication and exploit opportunities for synergy. The IPT is composed of jointly staffed groups that work on technical issues of mutal interest, front-end design and project definition, nuclear safety, plant engineering system integration, commissioning, planning and scheduling, and environmental, safety, health and quality (ESH&Q) areas. In the past year important progress has been made in a number of areas as the organization has matured and additional opportunities have been identified. Areas covered in this paper include: Support for development of the Office of Envirnmental Management (EM) framework document to progress the Office of River Protection's (ORP) River Protection Project (RPP) mission; Stewardship of the RPP flowsheet; Collaboration with Savannah River Site (SRS), Savannah River National Laboratory (SRNL), and Pacific Northwest National Laboratory (PNNL); Operations programs integration, and; Further development of the waste acceptance criteria.

Skwarek, Raymond J.; Harp, Ben J.; Duncan, Garth M.

2013-12-18T23:59:59.000Z

318

A safety assessment for proposed pump mixing operations to mitigate episodic gas releases in tank 241-SY-101: Hanford Site,Richland, Washington  

DOE Green Energy (OSTI)

This safety assessment addresses each of the elements required for the proposed action to remove a slurry distributor and to install, operate, and remove a mixing pump in Tank 241-SY-101,which is located within the Hanford Site, Richland, Washington.The proposed action is required as part of an ongoing evaluation of various mitigation concepts developed to eliminate episodic gas releases that result in hydrogen concentrations in the tank dome space that exceed the lower flammability limit.

Lentsch, J.W.

1996-07-01T23:59:59.000Z

319

Safety assessment for proposed pump mixing operations to mitigate episodic gas releases in tank 241-101-SY: Hanford Site, Richland, Washington  

DOE Green Energy (OSTI)

This safety assessment addresses each of the elements required for the proposed action to remove a slurry distributor and to install, operate, and remove a mixing pump in Tank 241-SY-101, which is located within the Hanford Site, Richland, Washington. The proposed action is required as part of an ongoing evaluation of various mitigation concepts developed to eliminate episodic gas releases that result in hydrogen concentrations in the tank dome space that exceed the lower flammability limit.

Lentsch, J.W., Westinghouse Hanford

1996-05-16T23:59:59.000Z

320

DEVELOPMENT OF A MACRO-BATCH QUALIFICATION STRATEGY FOR THE HANFORD TANK WASTE TREATMENT AND IMMOBILIZATION PLANT  

Science Conference Proceedings (OSTI)

The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: ? Limitations of mixing/blending capability of the Hanford Tank Farm; ? The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; ? The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and ? The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the following: ? Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; ? Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; ? Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; ? Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and ? Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF.

Herman, C.

2013-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Completion of Hanford Tanks Initiative characterization milestone T04-98-523  

SciTech Connect

The HTI subsurface characterization task will use the Hanford Cone Penetrometer platform (CPP) to deploy soil sensor and sampling probes into the vadose zone/soils around AX-104 during FY-99. This document provides copies of the first data collected from the HTI sensor probes during vendor field developmental tests performed at a Cold test site in the Hanford 200 East area. Conduct of the initial test also established completion of a major contractor milestone of the HTI Characterization task (MS T04-98-523: Complete preparation of the HTICP probes and transfer to Hanford/HTI. Conduct an initial MSP push using the CPP).

IWATATE, D.F.

1998-10-23T23:59:59.000Z

322

SUMMARY PLAN FOR BENCH-SCALE REFORMER AND PRODUCT TESTING TREATABILITY STUDIES USING HANFORD TANK WASTE  

SciTech Connect

This paper describes the sample selection, sample preparation, environmental, and regulatory considerations for shipment of Hanford radioactive waste samples for treatability studies of the FBSR process at the Savannah River National Laboratory and the Pacific Northwest National Laboratory.

ROBBINS RA

2011-02-11T23:59:59.000Z

323

PERFORMANCE ASSESSMENT TO SUPPORT CLOSURE OF SINGLE-SHELL TANK WASTE MANAGEMENT AREA C AT THE HANFORD SITE  

Science Conference Proceedings (OSTI)

Current proposed regulatory agreements (Consent Decree) at the Hanford Site call for closure of the Single-Shell Tank (SST) Waste Management Area (WMA) C in the year 2019. WMA C is part of the SST system in 200 East area ofthe Hanford Site and is one of the first tank farm areas built in mid-1940s. In order to close WMA C, both tank and facility closure activities and corrective actions associated with existing soil and groundwater contamination must be performed. Remedial activities for WMA C and corrective actions for soils and groundwater within that system will be supported by various types of risk assessments and interim performance assessments (PA). The U.S. Department of Energy, Office of River Protection (DOE-ORP) and the State ofWashington Department of Ecology (Ecology) are sponsoring a series of working sessions with regulators and stakeholders to solicit input and to obtain a common understanding concerning the scope, methods, and data to be used in the planned risk assessments and PAs to support closure of WMA C. In addition to DOE-ORP and Ecology staff and contractors, working session members include representatives from the U.S. Enviromnental Protection Agency, the U.S. Nuclear Regulatory Commission (NRC), interested tribal nations, other stakeholders groups, and members of the interested public. NRC staff involvement in the working sessions is as a technical resource to assess whether required waste determinations by DOE for waste incidental to reprocessing are based on sound technical assumptions, analyses, and conclusions relative to applicable incidental waste criteria.

BERGERON MP

2010-01-14T23:59:59.000Z

324

Composition and quantities of retained gas measured in Hanford waste tanks 241-U-103, S-106, BY-101, and BY-109  

DOE Green Energy (OSTI)

This report provides the results obtained for the single-shell tanks (SSTs) sampled with the Retained Gas Sampler (RGS) during 1997: Tanks 241-U-103, 241-S-106, 241-BY-101, and 241-BY-109. The RGS is a modified version of the core sampler used at Hanford. It is designed specifically to be used in concert with the gas extraction equipment in the hot cell to capture and extrude a gas-containing waste sample in a hermetically sealed system. The four tanks represent several different types of flammable gas SSTs. Tank U-103 is on the Flammable Gas Watch List (FGWL) and is one of the highest-priority group of SSTs that show evidence of significant gas retention. Tank S-106, though not a FGWL tank, has a uniquely high barometric pressure response and continuing rapid surface level rise, indicating a large and increasing volume of retained gas. Tanks BY-101 and BY-109 are not on the FGWL but were chosen to test the effect of recent salt-well pumping on gas retention. Section 2 of this report provides an overview of the process by which retained gases in the Hanford tanks are sampled and analyzed. A detailed description of the procedure used to reduce and analyze the data is provided in Section 3. Tank-by-tank results are covered in Section 4 (with the data presented in the order in which the tanks were sampled), and an RGS system performance overview is given in Section 5. Section 6 presents conclusions from these analyses and recommendations for further research. The cited references are listed in Section 7. Appendix A describes the procedures used to extract gas and ammonia from the samples, Appendix B contains detailed laboratory data from each of the tanks, and Appendix C gives field sampling data.

Mahoney, L.A.; Antoniak, Z.I.; Bates, J.M.

1997-12-01T23:59:59.000Z

325

Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington  

SciTech Connect

The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for continued operation. Code reconciliation issues and material degradation under aging conditions are addressed. Although the criteria were developed for double-shell tanks, many of the provisions are equally applicable to single-shell tanks. However, the criteria do not apply to the evaluation of tank appurtenances and buried piping.

Julyk, L.J.; Day, A.D.; Dyrness, A.D.; Moore, C.J.; Peterson, W.S.; Scott, M.A.; Shrivastava, H.P.; Sholman, J.S.; Watts, T.N.

1995-09-01T23:59:59.000Z

326

Congressional, State Officials Tour Hanford's Test Site for Safe...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Congressional, State Officials Tour Hanford's Test Site for Safe Tank Waste Cleanup Congressional, State Officials Tour Hanford's Test Site for Safe Tank Waste Cleanup September...

327

An Initial Evaluation Of Characterization And Closure Options For Underground Pipelines Within A Hanford Site Single-Shell Tank Farm  

SciTech Connect

The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and pipeline removal or treatment technologies. The evaluation accounted for the potential high worker risk, high cost, and schedule impacts associated with characterization, removal, or treatment of pipelines within Waste Management Area C for closure. This assessment was compared to the unknown, but estimated low, long-term impacts to groundwater associated with remaining waste residuals should the pipelines be left "as is" and an engineered surface barrier or landfill cap be placed. This study also recommended that no characterization or closure actions be assumed or started for the pipelines within Waste Management Area C, likewise with the premise that a surface barrier or landfill cap be placed over the pipelines.

Badden, Janet W. [Washington River Protection Solutions, LLC, Richland, WA (United States); Connelly, Michael P. [Washington River Protection Solutions, LLC, Richland, WA (United States); Seeley, Paul N. [Cenibark International, Inc., Kennewick (United States); Hendrickson, Michelle L. [Washington State Univ., Richland (United States). Dept. of Ecology

2013-01-10T23:59:59.000Z

328

Review of Management of Safety Systems at the Hanford Tank Farms...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Maintenance CRAD Criteria, Review and Approach Document CSE Cognizant System Engineer DOE U.S. Department of Energy DSA Documented Safety Analysis DST Double Shell Tank EIR...

329

RCRA Assessment Plan for Single-Shell Tank Waste Management Area B-BX-BY at the Hanford Site  

Science Conference Proceedings (OSTI)

This document was prepared as a groundwater quality assessment plan revision for the single-shell tank systems in Waste Management Area B-BX-BY at the Hanford Site. Groundwater monitoring is conducted at this facility in accordance with 40 CFR Part 265, Subpart F. In FY 1996, the groundwater monitoring program was changed from detection-level indicator evaluation to a groundwater quality assessment program when elevated specific conductance in downgradient monitoring well 299 E33-32 was confirmed by verification sampling. During the course of the ensuing investigation, elevated technetium-99 and nitrate were observed above the drinking water standard at well 299-E33-41, a well located between 241-B and 241-BX Tank Farms. Earlier observations of the groundwater contamination and tank farm leak occurrences combined with a qualitative analysis of possible solutions, led to the conclusion that waste from the waste management area had entered the groundwater and were observed in this well. Based on 40 CFR 265.93 [d] paragraph (7), the owner-operator must continue to make the minimum required determinations of contaminant level and rate/extent of migrations on a quarterly basis until final facility closure. These continued determinations are required because the groundwater quality assessment was implemented prior to final closure of the facility.

Narbutovskih, Susan M.

2006-09-29T23:59:59.000Z

330

Recycle Waste Collection Tank (RWCT) simulant testing in the PVTD feed preparation system  

Science Conference Proceedings (OSTI)

(This is part of the radwaste vitrification program at Hanford.) RWCT was to routinely receive final canister decontamination sand blast frit and rinse water, Decontamination Waste Treatment Tank bottoms, and melter off-gas Submerged Bed Scrubber filter cake. In order to address the design needs of the RWCT system to meet performance levels, the PNL Vitrification Technology (PVTD) program used the Feed Preparation Test System (FPTS) to evaluate its equipment and performance for a simulant of RWCT slurry. (FPTS is an adaptation of the Defense Waste Processing Facility feed preparation system and represents the initially proposed Hanford Waste Vitrification Plant feed preparation system designed by Fluor-Daniel, Inc.) The following were determined: mixing performance, pump priming, pump performance, simulant flow characterization, evaporator and condenser performance, and ammonia dispersion. The RWCT test had two runs, one with and one without tank baffles.

Abrigo, G.P.; Daume, J.T.; Halstead, S.D.; Myers, R.L.; Beckette, M.R.; Freeman, C.J.; Hatchell, B.K.

1996-03-01T23:59:59.000Z

331

Flammable Gas Release Estimates for Modified Sluicing Retrieval of Waste from Selected Hanford Single-Shell Tanks  

DOE Green Energy (OSTI)

The high-level radioactive wastes in many single-shell tanks (SSTs) at the Hanford Site are to be retrieved by a modified sluicing method that uses water jets to dissolve the water-soluble waste and mobilize the water-insoluble waste. Retrieval operations will liberate any waste gases trapped in the wetted solid waste matrix, and these gases will be released into the tank headspaces. Because the trapped gases include the flammable species hydrogen, methane, and ammonia, a concern exists that a flammable mixture could be formed in the tank headspaces. This report combines conservative retained gas inventory estimates and tank data with anticipated waste retrieval rates to estimate the potential headspace flammability of selected SSTs during modified sluicing waste retrieval operations. Considered here are nine of the 12 tanks from the 241-S tank farm (241-S-107, 241-S-111, and 241-S 112 are not considered) and Tank 241-U-107. This report is intended to support the specification of process controls that ensure flammable conditions do not develop in the tank headspaces. Consequently, the physical scenarios considered, the models developed to estimate retained gas releases and the tank headspace compositions under these scenarios, and the model input data are intended to conservatively assess the potential to reach headspace flammability. The analyses are intended to address worst-case conditions and establish reasonable upper bounds on the achievable flammability of the tank headspaces. Flammable retained gas inventories, for example, are based on the 95th percentile developed by Barker and Hedengren (2003), giving 95% confidence that actual inventories are smaller than those used in the calculations. Gas releases and headspace flammability were evaluated for three general scenarios: a very aggressive dissolution and erosion of saltcake waste by water jets impinging on the waste surface, the drainage of interstitial liquids from saltcake during a shutdown of the retrieval process, and the dissolution of saltcake by unsaturated liquids during a shutdown of the retrieval process. The simple model of waste retrieval using the modified sluicing approach indicated that the flammable gas headspace concentrations can rapidly approach the action level of 25% of the lower flammability limit (LFL) when the tank is passively ventilated. While it is not necessary to use the portable exhauster to maintain the headspace hydrogen concentration below this action level, retrieval rates would probably be limited by the slow removal of flammable gases by passive ventilation. It was determined that using a portable exhauster anywhere in the assumed operating range of 270 to 475 cfm would prevent the headspaces from reaching the 25% of LFL action level even if the water jets are very effective at eroding the saltcake. Specific guidelines are developed to ensure that, in the event of a catastrophic loss of the retrieval pump and portable exhauster, headspace flammability will not reach the LFL. This report is Revision 1 of PNNL-14271. This revision expands the analysis of interstitial liquid drainage-induced gas releases to address a general retrieval scenario (the previous version of this report assumed a center-out retrieval approach and conditions). Tank waste conditions (waste volumes, interstitial liquid levels, temperatures, retained gas void fractions, etc.) have also been updated from the previous version.

Huckaby, James L.; Wells, Beric E.

2004-03-05T23:59:59.000Z

332

Review of the Hanford Tank Farms Radiological Controls Activity-Level Implementation, December 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

Tank Farms Tank Farms Radiological Controls Activity-Level Implementation May 2011 December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope.................................................................................................................................................... 2 4.0 Methodology ........................................................................................................................................

333

STEADY STATE FLAMMABLE GAS RELEASE RATE CALCULATION AND LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE  

DOE Green Energy (OSTI)

Assess the steady-state flammability level at normal and off-normal ventilation conditions. The hydrogen generation rate was calculated for 177 tanks using the rate equation model. Flammability calculations based on hydrogen, ammonia, and methane were performed for 177 tanks for various scenarios.

HU TA

2009-10-26T23:59:59.000Z

334

Review of the Hanford Tank Farms Radiological Controls Activity-Level Implementation, December 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Tank Farms Tank Farms Radiological Controls Activity-Level Implementation May 2011 December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose................................................................................................................................................. 1 2.0 Background .......................................................................................................................................... 1 3.0 Scope.................................................................................................................................................... 2 4.0 Methodology ........................................................................................................................................

335

Removal of floating organic in Hanford Waste Tank 241-C-103 restart plan  

Science Conference Proceedings (OSTI)

The decision whether or not to remove the organic layer from Waste Tank 241-C-103 was deferred until May, 1995. The following restart plan was prepared for removal of the organic if the decision is to remove the organic from the waste tank 241-C-103.

Wilson, T.R.; Hanson, C.

1994-10-03T23:59:59.000Z

336

STEADY STATE FLAMMABLE GAS RELEASE RATE CALCULATION & LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE  

DOE Green Energy (OSTI)

Assess the steady-state flammability level at normal and off-normal ventilation conditions. The hydrogen generation rate was calculated for 177 tanks using the rate equation model. Flammability calculations based on hydrogen, ammonia, and methane were performed for 177 tanks for various scenarios.

HU, T.A.

2005-10-27T23:59:59.000Z

337

STEADY STATE FLAMMABLE GAS RELEASE RATE CALCULATION & LOWER FLAMMABILITY LEVEL EVALUATION FOR HANFORD TANK WASTE  

DOE Green Energy (OSTI)

Assess the steady-state flammability level at normal and off-normal ventilation conditions. The hydrogen generation rate was calculated for 177 tanks using the rate equation model. Flammability calculations based on hydrogen, ammonia, and methane were performed for 177 tanks for various scenarios.

HU, T.A.

2004-10-27T23:59:59.000Z

338

Hanford Double-Shell Tank Inspection Annual Report Calendar Year 2012  

SciTech Connect

The double-shell tanks (DSTs) were constructed between 1968 and 1986. They will have exceeded their design life before the waste can be removed and trasferred to the Waste Treatment and Immobilization Plant for vitrification. The Double-Shell Tank Integrity Project has been established to evaluate tank aging, and ensure that each tank is structurally sound for continued use. This is the first issue of the Double-Shell Tank Inspection Annual Report. The purpose of this issue is to summarize the results of DST inspections conducted from the beginnng of the inspection program through the end of CY2012. Hereafter, the report will be updated annually with summaries of the past year's DST inspection activities.

Petermann, Tasha M.; Boomer, Kayle D.; Washenfelder, D. J.

2013-12-02T23:59:59.000Z

339

Caustic Recycle from Hanford Tank Waste Using NaSICON Ceramic Membrane Salt Splitting Process  

Science Conference Proceedings (OSTI)

A family of inorganic ceramic materials, called sodium (Na) Super Ion Conductors (NaSICON), has been studied at Pacific Northwest National Laboratory (PNNL) to investigate their ability to separate sodium from radioactively contaminated sodium salt solutions for treating U.S. Department of Energy (DOE) tank wastes. Ceramatec Inc. developed and fabricated a membrane containing a proprietary NAS-GY material formulation that was electrochemically tested in a bench-scale apparatus with both a simulant and a radioactive tank-waste solution to determine the membrane performance when removing sodium from DOE tank wastes. Implementing this sodium separation process can result in significant cost savings by reducing the disposal volume of low-activity wastes and by producing a NaOH feedstock product for recycle into waste treatment processes such as sludge leaching, regenerating ion exchange resins, inhibiting corrosion in carbon-steel tanks, or retrieving tank wastes.

Fountain, Matthew S.; Kurath, Dean E.; Sevigny, Gary J.; Poloski, Adam P.; Pendleton, J.; Balagopal, S.; Quist, M.; Clay, D.

2009-02-20T23:59:59.000Z

340

Fluid dynamics, particulate segregation, chemical processes, and natural ore analog discussions that relate to the potential for criticality in Hanford tanks  

SciTech Connect

This report presents an in-depth review of the potential for nuclear criticality to occur in Hanford defense waste tanks during past, current and future safe storage and maintenance operations. The report also briefly discusses the potential impacts of proposed retrieval activities, although retrieval was not a main focus of scope. After thorough review of fluid dynamic aspects that focus on particle segregation, chemical aspects that focus on solubility and adsorption processes that might concentrate plutonium and/or separate plutonium from the neutron absorbers in the tank waste, and ore-body formation and mining operations, the interdisciplinary team has come to the conclusion that there is negligible risk of nuclear critically under existing storage conditions in Hanford site underground waste storage tanks. Further, for the accident scenarios considered an accidental criticality is incredible.

Barney, G.S.

1996-09-27T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Understanding waste phenomenology to reduce the amount of sampling and analysis required to resolve Hanford waste tank safety issues  

SciTech Connect

Safety issues associated with Hanford Site waste tanks arose because of inadequate safety analyses and high levels of uncertainty over the release of radioactivity resulting from condensed phase exothermic chemical reactions (organic solvent fires, organic complexant-nitrate reactions, and ferrocyanide-nitrate reactions). The approach to resolving the Organic Complexant, Organic Solvent, and Ferrocyanide safety issues has changed considerably since 1990. The approach formerly utilized core sampling and extensive analysis of the samples with the expectation the data would provide insight into the hazard. This resulted in high costs and the generation of a large amount of data that was of limited value in resolving the safety issues. The new approach relies on an understanding of the hazard phenomenology to focus sampling and analysis on those analytes that are key to ensuring safe storage of the waste.

Meacham, J.E.; Babad, H.

1996-02-01T23:59:59.000Z

342

GLASS FORMULATION FOR THE HANFORD TANK WASTE TREATMENT AND IMMOBILIZATION PLANT (WTP)  

SciTech Connect

A computational method for formulating Hanford HLW glasses was developed that is based on empirical glass composition-property models, accounts for all associated uncertainties, and can be solved in Excel{sup R} in minutes. Calculations for all waste form processing and compliance requirements included. Limited experimental validation performed.

KRUGER AA; VIENNA JD; KIM DS; JAIN V

2009-05-27T23:59:59.000Z

343

Hanford Tank 241-S-112 Residual Waste Composition and Leach Test Data  

SciTech Connect

This report presents the results of laboratory characterization and testing of two samples (designated 20406 and 20407) of residual waste collected from tank S-112 after final waste retrieval. These studies were completed to characterize the residual waste and assess the leachability of contaminants from the solids. This is the first report from this PNNL project to describe the composition and leach test data for residual waste from a salt cake tank. All previous PNNL reports (Cantrell et al. 2008; Deutsch et al. 2006, 2007a, 2007b, 2007c) describing contaminant release models, and characterization and testing results for residual waste in single-shell tanks were based on samples from sludge tanks.

Cantrell, Kirk J.; Krupka, Kenneth M.; Geiszler, Keith N.; Lindberg, Michael J.; Arey, Bruce W.; Schaef, Herbert T.

2008-08-29T23:59:59.000Z

344

Ferrocyanide Safety Program: Analysis of postulated energetic reactions and resultant aerosol generation in Hanford Site Waste Tanks  

Science Conference Proceedings (OSTI)

This report reviews work done to estimate the possible consequences of postulated energetic reactions in ferrocyanide waste stored in underground tanks at the Hanford Site. The issue of explosive reactions was raised in the 1987 Environmental Impact Statement (EIS), where a detonation-like explosion was postulated for the purpose of defining an upper bound on dose consequences for various disposal options. A review of the explosion scenario by the General Accounting Office (GAO) indicated that the aerosol generation and consequent radioactive doses projected for the explosion postulated in the EIS were understated by one to two orders of magnitude. The US DOE has sponsored an extensive study of the hazard posed by uncontrolled exothermic reactions in ferrocyanide waste, and results obtained during the past three years have allowed this hazard to be more realistically assessed. The objective of this report is to summarize the improved knowledge base that now indicates that explosive or vigorous chemical reactions are not credible in the ferrocyanide waste stored in underground tanks. This improved understanding supports the decision not to proceed with further analyses or predictions of the consequences of such an event or with aerosol tests in support of such predictions. 53 refs., 2 tabs.

Postma, A.K. [G and P Consulting, Inc., Dallas, OR (United States); Dickinson, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1995-09-01T23:59:59.000Z

345

Geochemical Processes Data Package for the Vadose Zone in the Single-Shell Tank Waste Management Areas at the Hanford Site  

SciTech Connect

This data package discusses the geochemistry of vadose zone sediments beneath the single-shell tank farms at the U.S. Department of Energys (DOEs) Hanford Site. The purpose of the report is to provide a review of the most recent and relevant geochemical process information available for the vadose zone beneath the single-shell tank farms and the Integrated Disposal Facility. Two companion reports to this one were recently published which discuss the geology of the farms (Reidel and Chamness 2007) and groundwater flow and contamination beneath the farms (Horton 2007).

Cantrell, Kirk J.; Zachara, John M.; Dresel, P. Evan; Krupka, Kenneth M.; Serne, R. Jeffrey

2007-09-28T23:59:59.000Z

346

Detection and Quantitative Analysis of Chemical Species in Hanford Tank Materials Using Raman Spectroscopy Technology: FY94Florida State University Raman Spectroscopy Report  

Science Conference Proceedings (OSTI)

This report provides a summary of work completed in FY-94 by FSU to develop and investigate the feasibility of using Raman spectroscopy with Hanford tank waste materials. Raman performance impacts from sample morphology, including the effects of absorption, particle size, density, color and refractive index, are discussed. An algorithm for relative species concentration measurement from Raman data is presented. An Algorithm for applying Raman to tank waste core screening is presented and discussed. A library of absorption and Raman spectra are presented that support this work.

Reich, F.R.

1997-08-11T23:59:59.000Z

347

Steady State Flammable Gas Release Rate Calculation and Lower Flammability Level Evaluation for Hanford Tank Waste  

DOE Green Energy (OSTI)

Assess the steady-state flammability level at normal and off-normal ventilation conditions. Hydrogen generation rate was calculated for 177 tanks using rate equation model. Ammonia liquid/vapor equilibrium model is incorporated into the methodology for ammonia analysis.

HU, T.A.

2001-02-23T23:59:59.000Z

348

Geochemical Characterization Data Package for the Vadose Zone in the Single-Shell Tank Waste Management Areas at the Hanford Site  

SciTech Connect

This data package discusses the geochemistry of vadose zone sediments beneath the single-shell tank (SST) farms at the U.S. Department of Energys (DOEs) Hanford Site. The purpose of the report is to provide a review of the most recent and relevant geochemical information available for the vadose zone beneath the SST farms and the Integrated Disposal Facility (IDF).

Cantrell, Kirk J.; Brown, Christopher F.; Serne, R. Jeffrey; Krupka, Kenneth M.

2008-01-07T23:59:59.000Z

349

Memorandum of Understanding Between the United States Department of Energy and the Washington State Department of Ecology for Development of the Hanford Site Tank Closure and Waste Management EIS ("TC&WM EIS")  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

THE THE UNITED STATES DEPARTMENT OF ENERGY, AND THE WASHINGTON STATE DEPARTMENT OF ECOLOGY, FOR DEVELOPMENT OF THE HANFORD SITE TANK CLOSURE AND WASTE MANAGEMENT EIS ("TC&WM EIS") I. INTRODUCTION The U.S. Department of Energy (DOE) and Washington State Department of Ecology (Ecology) have mutual responsibilities for accomplishing cleanup of the Hanford Site as well as continuing ongoing waste management activities consistent with applicable federal and state laws and regulations. The Hanford Federal Facility Agreement and Consent Order (otherwise called the "Tri-Party Agreement", or "TPA") contains various enforceable milestones that apply to tank waste management activities. DOE is also required to comply with applicable requirements of

350

Review of Nuclear Criticality Safety Requirements Implementation for Hanford Tank Farms Facility  

SciTech Connect

In November 1999, the Deputy Secretary of the Department of Energy directed a series of actions to strengthen the Department's ongoing nuclear criticality safety programs. A Review Plan describing lines of inquiry for assessing contractor programs was included. The Office of River Protection completed their assessment of the Tank Farm Contractor program in May 2000. This document supports that assessment by providing a compliance statement for each line of inquiry.

DEFIGH PRICE, C.

2000-08-09T23:59:59.000Z

351

Assessment of New Calculation Method for Toxicological Sums-of-Fractions for Hanford Tank Wastes  

SciTech Connect

The toxicological source terms used for potential accident assessment in the Tank Farms DSA are based on toxicological sums-of-fractions (SOFs) that were calculated in fiscal years 2002 and 2003 based on the Best Basis Inventory (BBI) from May 2002, using the method described by Cowley et al. (2003). The present report describes a modified SOF-calculation method that is to be used in future toxicological updates and assessments and compares its results (for the 2002 BBI) to those of the old method. The new method generally calculated different (usually larger) SOFs than the old. The dominant reason was the more conservative way in which the new method represents concentration variability, in that it uses the waste layer with the maximum SOF to represent the tank SOF. The old method had used a tank-average waste composition and SOF. Differences between thermodynamically modeled and BBI solubilities were the next most common reason for differences between old (modeled) and new (BBI) SOFs, particularly in the liquid phase. The solubility-related changes in SOF were roughly equally distributed between increases and decreases. Changes in the effective toxicities of TOC and lead, which resulted from changes in the compounds in which these analytes were considered to be present, were the third most common reason. These toxicity changes increased SOFs and therefore were in a conservative direction.

Mahoney, Lenna A.

2006-09-26T23:59:59.000Z

352

Initial parametric study of the flammability of plume releases in Hanford waste tanks  

SciTech Connect

This study comprised systematic analyses of waste tank headspace flammability following a plume-type of gas release from the waste. First, critical parameters affecting plume flammability were selected, evaluated, and refined. As part of the evaluation the effect of ventilation (breathing) air inflow on the convective flow field inside the tank headspace was assessed, and the magnitude of the so-called {open_quotes}numerical diffusion{close_quotes} on numerical simulation accuracy was investigated. Both issues were concluded to be negligible influences on predicted flammable gas concentrations in the tank headspace. Previous validation of the TEMPEST code against experimental data is also discussed, with calculated results in good agreements with experimental data. Twelve plume release simulations were then run, using release volumes and flow rates that were thought to cover the range of actual release volumes and rates. The results indicate that most plume-type releases remain flammable only during the actual release ends. Only for very large releases representing a significant fraction of the volume necessary to make the entire mixed headspace flammable (many thousands of cubic feet) can flammable concentrations persist for several hours after the release ends. However, as in the smaller plumes, only a fraction of the total release volume is flammable at any one time. The transient evolution of several plume sizes is illustrated in a number of color contour plots that provide insight into plume mixing behavior.

Antoniak, Z.I.; Recknagle, K.P.

1997-08-01T23:59:59.000Z

353

DESIGN OF THE DEMOSNTRATION BULK VITRIFICATION SYSTEM FOR THE SUPPLEMENTAL TREATMENT OF LOW ACTIVITY TANK WASTE AT HANFORD  

SciTech Connect

In June 2004, the Demonstration Bulk Vitrification System (DBVS) was initiated with the intent to design, construct, and operate a full-scale bulk vitrification pilot-plant to treat low-activity tank waste from Hanford Tank 241-S-109. The DBVS facility uses In-Container Vitrification{trademark} (ICV{trademark}) at the core of the treatment process. The basic process steps combine liquid low-activity waste (LAW) and glassformers; dry the mixture; and then vitrify the mixture in a batch feed-while-melt process in a refractory lined steel container. Off-gases are processed through a state-of-the-art air pollution control system including sintered-metal filtration, thermal oxidation, acid gas scrubbing, and high-efficiency particulate air (HEPA) and high-efficiency gas adsorber (HEGA) filtration. Testing has focused on development and validation of the waste dryer, ICV, and sintered-metal filters (SMFs) equipment, operations enhancements, and glass formulation. With a parallel testing and design process, testing has allowed improvements to the DBVS equipment configuration and operating methodology, since its original inception. Design improvements include optimization of refractory panels in the ICV, simplifying glassformer addition equipment, increasing the number of waste feed chutes to the ICV, and adding capability for remote clean-out of piping, In addition, the U.S. Department of Energy (DOE) has provided an independent review of the entire DBVS process. While the review did not find any fatal flaws, some technical issues were identified that required a re-evaluation of the DBVS design and subsequent changes to the design. A 100 percent design package for the pilot plant will be completed and submitted to DOE for review in early 2008 that incorporates process improvements substantiated through testing and reviews. This paper provides a description of the bulk vitrification process and a discussion of major equipment design changes that have occurred based on full-scale testing over the past two years and DOE reviews.

VAN BEEK JE

2008-02-14T23:59:59.000Z

354

Meeting Summary for Development of the Hanford Site C Tank Farm Performance Assessment  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6064 (2) Revision Number: 0 (3) Effective Date: 04/15/2010 6064 (2) Revision Number: 0 (3) Effective Date: 04/15/2010 (4) Document Type: [I Digital Image ElHard copy (a) Number of pages (including the DRF) or 15 Z PDF Video number of digital images (5) Release Type 0 New l Cancel 11: Page Change l complete Revision (6) Document Title: Meeting Minutes for the WMA C PA Features, Events, and Processes Working Session (7) Change/Release Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Description: Waste Management Area C performance assessment on Features, Events, and Processes (8) Change N/A Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, and Component N/A N/A (SSC) and Building (b) System Designator: (d) Equipment ID Number (EIN): Number:

355

RADIOACTIVE DEMONSTRATION OF MINERALIZED WASTE FORMS MADE FROM HANFORD LOW ACTIVITY WASTE (TANK FARM BLEND) BY FLUIDIZED BED STEAM REFORMATION (FBSR)  

Science Conference Proceedings (OSTI)

The U.S. Department of Energys Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanfords tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Supplemental Treatment is likely to be required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTPs LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750C) continuous method by which LAW can be processed irrespective of whether the waste contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be comparable to LAW glass, i.e. leaches Tc-99, Re and Na at 6 (the Hanford IDF criteria for Na) in the first few hours. The granular and monolithic waste forms also pass the EPA Toxicity Characteristic Leaching Procedure (TCLP) for all Resource Conservation and Recovery Act (RCRA) components at the Universal Treatment Standards (UTS). Two identical Benchscale Steam Reformers (BSR) were designed and constructed at SRNL, one to treat non-radioactive simulants and the other to treat actual radioactive wastes. The results from the non-radioactive BSR were used to determine the parameters needed to operate the radioactive BSR in order to confirm the findings of non-radioactive FBSR pilot scale and engineering scale tests and to qualify an FBSR LAW waste form for applications at Hanford. Radioactive testing commenced using SRS LAW from Tank 50 chemically trimmed to look like Hanfords blended LAW known as the Rassat simulant as this simulant composition had been tested in the non-radioactive BSR, the non-radioactive pilot scale FBSR at the Science Applications International Corporation-Science and Technology Applications Research (SAIC-STAR) facility in Idaho Falls, ID and in the TTT Engineering Scale Technology Demonstration (ESTD) at Hazen Research Inc. (HRI) in Denver, CO. This provided a tie back between radioactive BSR testing and non-radioactive BSR, pilot scale, and engineering scale testing. Approximately six hundred grams of non-radioactive and radioactive BSR product were made for extensive testing and comparison to the non-radioactive pilot scale tests performed in 2004 at SAIC-STAR and the engineering scale test performed in 2008 at HRI with the Rassat simulant. The same mineral phases and off-gas species were found in the radioactive and non-radioactive testing. The granular ESTD and BSR products (radioactive and non-radioactive) were analyzed for to

Jantzen, C. M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Hall, H. K.; Miller, D. H.; Missimer, D. M.; Nash, C. A.; Williams, M. F.

2013-08-21T23:59:59.000Z

356

Hanford Site Tank 241-C-108 Residual Waste Contaminant Release Models and Supporting Data  

SciTech Connect

This report presents the results of laboratory characterization, testing, and analysis for a composite sample (designated 20578) of residual waste collected from single-shell tank C-108 during the waste retrieval process after modified sluicing. These studies were completed to characterize concentration and form of contaminant of interest in the residual waste; assess the leachability of contaminants from the solids; and develop release models for contaminants of interest. Because modified sluicing did not achieve 99% removal of the waste, it is expected that additional retrieval processing will take place. As a result, the sample analyzed here is not expected to represent final retrieval sample.

Cantrell, Kirk J.; Krupka, Kenneth M.; Geiszler, Keith N.; Arey, Bruce W.; Schaef, Herbert T.

2010-06-18T23:59:59.000Z

357

Contaminant desorption during long-term leaching of hydroxide-weathered Hanford sediments  

E-Print Network (OSTI)

137 in sediments at the Hanford Site, Washington. Environ.during simulated leaks of Hanford waste tanks. Appl.subsurface sediments from the Hanford site, USA. Geochim.

Thompson, A.

2010-01-01T23:59:59.000Z

358

Estimating Contaminant Release Concentrations from Hanford ...  

& Transport Model Long-Term Performance Assessment ... sludge provide upper limit on future releases. 9 Metals Concentrations in Hanford Tank ...

359

Identification of Non-Pertechnetate Species in Hanford Tank Waste, Their Synthesis, Characterization, and Fundamental Chemistry  

Science Conference Proceedings (OSTI)

Technetium, as pertechnetate (TcO4 -), is a mobile species in the environment. This characteristic, along with its long half-life, (99Tc, t1/2 = 213,000 a) makes technetium a major contributor to the long-term hazard associated with low level waste (LLW) disposal. Technetium partitioning from the nuclear waste at DOE sites may be required so that the LLW forms meet DOE performance assessment criteria. Technetium separations assume that technetium exists as TcO4 - in the waste. However, years of thermal, chemical, and radiolytic digestion in the presence of organic material, has transformed much of the TcO4 - into unidentified, stable, reduced, technetium complexes. To successfully partition technetium from tank wastes, it will be necessary to either remove these technetium species with a new process, or reoxidize them to TcO4 - so that conventional pertechnetate separation schemes will be successful.

Schroeder, Norman C.; Ashley, Kenneth R.; Olivares, Jose A.

2004-06-15T23:59:59.000Z

360

Summary of the HANFORD SITE  

E-Print Network (OSTI)

will be welded. Some Tri-Party Agreement milestones completed in 2002 were related to work on Hanford tanks. #12 paragraphs. Solid waste may originate from work on the Hanford Site or from sources offsite, with contributions from CH2M HILL Hanford Group, Inc.; S.M. Stoller Corporation; Fluor Hanford, Inc. and its

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Automated Sampling and Sample Pneumatic Transport of High Level Tank Wastes at the Hanford Waste Treatment Plant  

Science Conference Proceedings (OSTI)

This paper describes the development work, and design and engineering tasks performed, to provide a fully automated sampling system for the Waste Treatment Plant (WTP) project at the Hanford Site in southeastern Washington State, USA. WTP is being built to enable the emptying and immobilization of highly active waste resulting from processing of irradiated nuclear fuel since the 1940's. The Hanford Tank Wastes are separated into Highly Level Waste (HLW), and Low Active Waste (LAW) fractions, which are separately immobilized by vitrification into borosilicate glass. Liquid samples must be taken of the waste and Glass Forming Chemicals (GFCs) before vitrification, and analyzed to insure the glass products will comply with specifications established in the WTP contract. This paper describes the non-radioactive testing of the sampling of the HLW and LAW melter feed simulants that was performed ahead of final equipment design. These trials were essential to demonstrate the effectiveness and repeatability of the integrated sampling system to collect representative samples, free of cross-contamination. Based on existing tried and proven equipment, the system design is tailored to meet the WTP project's specific needs. The design provides sampling capabilities from 47 separate sampling points and includes a pneumatic transport system to move the samples from the 3 separate facilities to the centralized analytical laboratory. The physical and rheological compositions of the waste simulants provided additional challenges in terms of the sample delivery, homogenization, and sample capture equipment design requirements. The activity levels of the actual waste forms, specified as 486 E9 Bq/liter (Cs-137), 1.92 E9 Bq/liter (Co-60), and 9.67 E9 Bq/liter (Eu-154), influenced the degree of automation provided, and justified the minimization of manual intervention needed to obtain and deliver samples from the process facilities to the analytical laboratories. Maintaining high integrity primary and secondary confinement, including during the cross-site transportation of the samples, is a key requirement that is achieved and assured at all times. (authors)

Phillips, C.; Richardson, J. E. [BNG America, 2345 Stevens Drive, Richland, WA, 99354 (United States)

2006-07-01T23:59:59.000Z

362

Data acquisition and control system for the High-Level Waste Tank Farm at Hanford, Washington  

SciTech Connect

The High-Level Nuclear Waste Storage Tank 241-SY-101 periodically releases flammable gasses. Mitigation experiments to release the gasses continuously to avoid a catastrophic build-up are planned for FY93 and beyond. Los Alamos has provided a data acquisition and control system (DACS) to monitor and control mitigation experiments on SY-101. The DACS consists of a data acquisition trailer to house the electronic components and computers in a friendly environment, a computer system running process control software for monitoring and controlling the tests, signal conditioners to convert the instrument signals to a usable form for the DACS, programmable logic controllers to process sensor signals and take action quickly, a fast data acquisition system for recording transient data, and a remote monitoring system to monitor the progress of the experiment. Equipment to monitor the release of the gasses was also provided. The first experiment involves a mixer pump to mix the waste and allow the gasses to be released at the surface of the liquid as the gas is being formed. The initial tests are scheduled for July 1993.

Hoida, H.W.; Hatcher, C.R.; Trujillo, L.T.; Holt, D.H. [Los Alamos National Lab., NM (United States); Vargo, G.F. [Westinghouse Hanford Co., Richland, WA (United States); Martin, J.; Stastny, G.; Echave, R. [EG and G Energy Measurements, Inc., Las Vegas, NV (United States); Eldridge, K. [Eldridge Engineering, Spokane, WA (United States)

1993-08-01T23:59:59.000Z

363

Time-Temperature-Transformation Study of Simulated Hanford Tank Waste (AZ-101) and Optimization of Glass Formulation for Processing Such Waste  

SciTech Connect

This paper presents the current results of a study for the optimization of the quality of the wasteform to be produced by vitrification of Hanford High Level Waste (HLW). A simulant of the content of Hanford Tank AZ-101 has been used for the experiments. A first phase of the research focused on the wasteform composition and showed that a high quality and chemical-resistant wasteform can be formed incorporating 60 weight % of dried waste into a borosilicate glass enriched with zinc oxide and boric acid and provided some indication about the heat treatment of the melt. A second phase of the study, still in progress, refines these findings. A detailed crystallinity survey of the waste form after various heat treatments has been performed, culminating in the development of a time-temperature-transformation (TTT) diagram. The results of the first phase of research and preliminary results from the second phase are described.

Ramsey, W. G.; Kauffman, B. M.; Bricka, M.; Meaker, T. F.; Giordana, A.; Smith, J. D.; Miller, F. S.; Bohannan, E.; Powell, J.; Reich, M.; Jordan, J.; Venter, L.; Barletta, R. E.; Ramsey, A. A.; Maise, G. M.; Manowitz, B.; Steinberg, M.; Salzano, F.

2003-02-26T23:59:59.000Z

364

Radwaste Desk Reference: Volume 5: Transportation Update  

Science Conference Proceedings (OSTI)

This volume of the Radwaste Desk Reference contains fundamental practical and regulatory information on the transportation of radioactive waste. Because its information is based entirely on industry practice, the work can serve as an extensive "how-to" manual for both the newcomer and the experienced radwaste professional.

2000-03-10T23:59:59.000Z

365

INTERIM REPORT FOR HANFORD TANKS AY-102 & AP-101 EFFECT OF CHEMISTRY & OTHER VARIABLES ON CORROSION & STRESS CORROSION CRACKING  

SciTech Connect

The objective of this work is to determine the range of conditions where the tank steel is susceptible to localized corrosion and SCC in simulants for waste in tanks AY-102 and AP-101.

HARTY, W.M.

2007-05-05T23:59:59.000Z

366

Steady State Flammable Gas Release Rate Calculation & Lower Flammability Level Evaluation for Hanford Tank Waste [SEC 1 & 2  

DOE Green Energy (OSTI)

Assess the steady state level at normal & off-normal ventilation conditions. Hydrogen generation rate calculated for 177 tanks using rate equation model. Flammability calc. based on hydrogen, ammonia, & methane proformed for tanks at various scenarios.

HU, T.A.

2002-06-20T23:59:59.000Z

367

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SEISMIC ANALYSIS IN SUPPORT OF INCREASED LIQUID LEVEL IN 241-AP TANK FARMS  

Science Conference Proceedings (OSTI)

The essential difference between Revision 1 and the original issue of this report is in the spring constants used to model the anchor bolt response for the anchor bolts that tie the steel dome of the primary tank to the concrete tank dome. Consequently, focus was placed on the changes in the anchor bolt responses, and a full reevaluation of all tank components was judged to be unnecessary. To confirm this judgement, primary tank stresses from the revised analysis of the BES-BEC case are compared to the original analysis and it was verified that the changes are small, as expected.

TC MACKEY; FG ABATT; MW RINKER

2009-01-14T23:59:59.000Z

368

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

DOE Green Energy (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 5 is the annual update of the methodology and calculations of the flammable gas Waste Groups for DSTs and SSTs.

BARKER, S.A.

2006-07-27T23:59:59.000Z

369

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

DOE Green Energy (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water and organic compounds, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generates ammonia. Nonflammable gases, which act as dilutents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semi-volatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in the tank headspace as described in RPP-7771, Flammable Gas Safety Isme Resolution. Appendices A through I provide supporting information. The document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste and characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 6 is the annual update of the flammable gas Waste Groups for DSTs and SSTs.

TU, T.A.

2007-01-04T23:59:59.000Z

370

METHODOLOGY & CALCULATIONS FOR THE ASSIGNMENT OF WASTE FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT HANFORD SITE [SEC 1 & 2  

DOE Green Energy (OSTI)

Waste stored within tank farm double-shell tanks (DST) and single-shell tanks (SST) generates flammable gas (principally hydrogen) to varying degrees depending on the type, amount, geometry, and condition of the waste. The waste generates hydrogen through the radiolysis of water, thermolytic decomposition of organic compounds, and corrosion of a tank's carbon steel walls. Radiolysis and thermolytic decomposition also generate ammonia. Nonflammable gases, which act as diluents (such as nitrous oxide), are also produced. Additional flammable gases (e.g., methane) are generated by chemical reactions between various degradation products of organic chemicals present in the tanks. Volatile and semivolatile organic chemicals in tanks also produce organic vapors. The generated gases in tank waste are either released continuously to the tank headspace or are retained in the waste matrix. Retained gas may be released in a spontaneous or induced gas release event (GRE) that can significantly increase the flammable gas concentration in tank headspace as described in RPP-7771, Flammable Gas Safety Issue Resolution. Appendices A through L provide supporting information. This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste and characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event.

BARKER, S.A.; HEDENGREN, D.C.

2003-08-28T23:59:59.000Z

371

AX Tank Farm tank removal study  

Science Conference Proceedings (OSTI)

This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

SKELLY, W.A.

1999-02-24T23:59:59.000Z

372

Strontium and cesium release mechanisms during unsaturated flow through waste-weathered Hanford sediments  

E-Print Network (OSTI)

Plutonium from Simulated Hanford Tank-Waste Sludges. Separ.Containing Tank Waste at Hanford. Separ. Sci. Technol. 2005,T. B. , Sr/TRU Removal from Hanford High Level Waste. Separ.

Chang, H.

2013-01-01T23:59:59.000Z

373

Hanford Site | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Site Hanford Site Hanford Site Workers safely demolished a 175-foot-high exhaust stack at the Hanford Site in southeastern Washington state, a project supported by $420,000 in Recovery Act funds Workers safely demolished a 175-foot-high exhaust stack at the Hanford Site in southeastern Washington state, a project supported by $420,000 in Recovery Act funds Slurry pumps are used in the tank farms to pick up liquid and solid particle mixture, or slurry, and provide the force necessary to transport the waste from tank to tank during retrieval operations Slurry pumps are used in the tank farms to pick up liquid and solid particle mixture, or slurry, and provide the force necessary to transport the waste from tank to tank during retrieval operations The Pretreatment Facility control room building pad (foreground) and the Low-Activity Waste Facility (background)

374

RADIOACTIVE DEMONSTRATION OF MINERALIZED WASTE FORMS MADE FROM HANFORD LOW ACTIVITY WASTE (TANK FARM BLEND) BY FLUIDIZED BED STEAM REFORMATION (FBSR)  

SciTech Connect

The U.S. Department of Energys Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanfords tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Supplemental Treatment is likely to be required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTPs LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750C) continuous method by which LAW can be processed irrespective of whether the waste contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be comparable to LAW glass, i.e. leaches Tc-99, Re and Na at <2g/m2 during ASTM C1285 (Product Consistency) durability testing. Monolithing of the granular FBSR product was investigated to prevent dispersion during transport or burial/storage. Monolithing in an inorganic geopolymer binder, which is amorphous, macro-encapsulates the granules, and the monoliths pass ANSI/ANS 16.1 and ASTM C1308 durability testing with Re achieving a Leach Index (LI) of 9 (the Hanford Integrated Disposal Facility, IDF, criteria for Tc-99) after a few days and Na achieving an LI of >6 (the Hanford IDF criteria for Na) in the first few hours. The granular and monolithic waste forms also pass the EPA Toxicity Characteristic Leaching Procedure (TCLP) for all Resource Conservation and Recovery Act (RCRA) components at the Universal Treatment Standards (UTS). Two identical Benchscale Steam Reformers (BSR) were designed and constructed at SRNL, one to treat non-radioactive simulants and the other to treat actual radioactive wastes. The results from the non-radioactive BSR were used to determine the parameters needed to operate the radioactive BSR in order to confirm the findings of non-radioactive FBSR pilot scale and engineering scale tests and to qualify an FBSR LAW waste form for applications at Hanford. Radioactive testing commenced using SRS LAW from Tank 50 chemically trimmed to look like Hanfords blended LAW known as the Rassat simulant as this simulant composition had been tested in the non-radioactive BSR, the non-radioactive pilot scale FBSR at the Science Applications International Corporation-Science and Technology Applications Research (SAIC-STAR) facility in Idaho Falls, ID and in the TTT Engineering Scale Technology Demonstration (ESTD) at Hazen Research Inc. (HRI) in Denver, CO. This provided a tie back between radioactive BSR testing and non-radioactive BSR, pilot scale, and engineering scale testing. Approximately six hundred grams of non-radioactive and radioactive BSR product were made for extensive testing and comparison to the non-radioactive pilot scale tests performed in 2004 at SAIC-STAR and the engineering scale test performed in 2008 at HRI with the Rassat simulant. The same mineral phases and off-gas species were found in the radioactive and non-radioactive testing. The granular ESTD and BSR products (radioactive and non-radioactive) were analyzed for to

Jantzen, C. M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Hall, H. K.; Miller, D. H.; Missimer, D. M.; Nash, C. A.; Williams, M. F.

2013-08-21T23:59:59.000Z

375

RCRA Groundwater Monitoring Plan for Single-Shell Tank Waste Management Area C at the Hanford Site  

SciTech Connect

This document describes the groundwater monitoring plan for Waste Management Area C located in the 200 East Area of the DOE Hanford Site. This plan is required under Resource Conservation and Recovery Act of 1976 (RCRA).

Horton, Duane G.; Narbutovskih, Susan M.

2001-01-01T23:59:59.000Z

376

A Plan to Develop and Demonstrate Electrochemical Noise Based Corrosion Monitoring Systems in Hanford Site Waste Tanks  

SciTech Connect

This document describes changes that need to be made to the site's authorization basis and technical concerns that need to be resolved before proceduralized use of Electrochemical Noise based corrosion monitoring systems is fully possible at the Hanford Site.

NORMAN, E.C.

2000-08-28T23:59:59.000Z

377

Hanford Tank Integrity Project  

Jordan Follett DST Project Plan and SST Use jordan_r_follet@rl.gov Rick Rast Structural Lead richard_s_rast@rl.gov Ted Venetz SST Integrity Lead theodore_j_venetz@rl.gov

378

Radwaste Desk Reference: Volume 4: Mixed Waste  

Science Conference Proceedings (OSTI)

Mixed waste management has been a significant concern to nuclear utilities due to the lack of available treatment and disposal capacity. This volume of the Radwaste Desk Reference contains fundamental practical and regulatory information on the management of mixed low level waste. Because its information is based entirely on industry practice, the work can serve as an extensive "how-to" manual for both the newcomer and the experienced radwaste professional responsible for mixed waste.

1995-12-31T23:59:59.000Z

379

Hanford | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Hanford Hanford Hanford Hanford Tank Waste Treatment and Immobilization Plant | December 2009 Aerial View Hanford Tank Waste Treatment and Immobilization Plant | December 2009 Aerial View The Hanford Site mission focuses on environmental restoration, waste management, related scientific and environmental research and development of radioactive waste management technologies. Under the Tri-Party Agreement, lower-level hazardous wastes are buried in huge lined pits that will be sealed and monitored with sophisticated instruments for many years. Enforcement September 13, 2012 Enforcement Letter,CH2M HILL Plateau - NEL-2012-02 Issued to CH2M HILL Plateau Remediation Company related to Radiological Work Control Deficiencies at the Plutonium Finishing Plant and 105 K-East

380

EFFECTS OF CHEMISTRY AND OTHER VARIABLES ON CORROSION AND STRESS CORROSION CRACKING IN HANFORD DOUBLE SHELL TANKS  

SciTech Connect

Laboratory testing was performed to develop a comprehensive understanding of the corrosivity of the tank wastes stored in Double-Shell Tanks using simulants primarily from Tanks 241-AP-105, 241-SY-103 and 241-AW-105. Additional tests were conducted using simulants of the waste stored in 241-AZ-102, 241-SY-101, 241-AN-107, and 241-AY-101. This test program placed particular emphasis on defining the range of tank waste chemistries that do not induce the onset of localized forms of corrosion, particularly pitting and stress corrosion cracking. This document summarizes the key findings of the research program.

BROWN MH

2008-11-13T23:59:59.000Z

Note: This page contains sample records for the topic "hanford tank radwaste" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Mechanisms of gas retention and release: Experimental results for Hanford single-shell waste tanks 241-A-101, 241-S-106, and 241-U-103  

Science Conference Proceedings (OSTI)

The 177 underground waste storage tanks at the Hanford Site contain millions of gallons of radioactive waste resulting from the purification of nuclear materials and related processes. Through various mechanisms, flammable gas mixtures of hydrogen, ammonia, methane, and nitrous oxide are generated and retained in significant quantities within the waste in many ({approximately}25) of these tanks. The potential for large releases of retained gas from these wastes creates a flammability hazard. It is a critical component of the effort to understand the flammability hazard and a primary goal of this laboratory investigation to establish an understanding of the mechanisms of gas retention and release in these wastes. The results of bubble retention experimental studies using waste samples from several waste tanks and a variety of waste types support resolution of the Flammable Gas Safety Issue. Gas bubble retention information gained in the pursuit of safe storage will, in turn, benefit future waste operations including salt-well pumping, waste transfers, and sluicing/retrieval.

Rassat, S.D.; Caley, S.M.; Bredt, P.R.; Gauglitz, P.A.; Rinehart, D.E.; Forbes, S.V.

1998-09-01T23:59:59.000Z

382

AX Tank Farm tank removal study  

SciTech Connect

This report considers the feasibility of exposing, demolishing, and removing underground storage tanks from the 241-AX Tank Farm at the Hanford Site. For the study, it was assumed that the tanks would each contain 360 ft{sup 3} of residual waste (corresponding to the one percent residual Inventory target cited in the Tri-Party Agreement) at the time of demolition. The 241-AX Tank Farm is being employed as a ''strawman'' in engineering studies evaluating clean and landfill closure options for Hanford single-shell tank farms. The report is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

SKELLY, W.A.

1998-10-14T23:59:59.000Z

383

Summary of the HANFORD SITE  

E-Print Network (OSTI)

milestones completed in 2003 were related to work on Hanford waste storage tanks. During 2003, there were 36Summary of the HANFORD SITE Environmental Report for Calendar Year 2003 EDITORS R.W. HANF L Northwest National Laboratory under contract DE-AC06-76RL01830, with contributions from Bechtel Hanford, Inc

384

Single-Pass Flow-Through Test Elucidation of Weathering Behavior and Evaluation of Contaminant Release Models for Hanford Tank Residual Radioactive Waste  

SciTech Connect

Contaminant release models are required to evaluate and predict long-term environmental impacts of even residual amounts of high-level radioactive waste after cleanup and closure of radioactively contaminated sites such as the DOEs Hanford Site. More realistic and representative models have been developed for release of uranium, technetium, and chromium from Hanford Site tanks C-202, C-203, and C-103 residual wastes using data collected with a single-pass flow-through test (SPFT) method. These revised models indicate that contaminant release concentrations from these residual wastes will be considerably lower than previous estimates based on batch experiments. For uranium, a thermodynamic solubility model provides an effective description of uranium release, which can account for differences in pore fluid chemistry contacting the waste that could occur through time and as a result of different closure scenarios. Under certain circumstances in the SPFT experiments various calcium rich precipitates (calcium phosphates and calcite) form on the surfaces of the waste particles, inhibiting dissolution of the underlying uranium phases in the waste. This behavior was not observed in previous batch experiments. For both technetium and chromium, empirical release models were developed. In the case of technetium, release from all three wastes was modeled using an equilibrium Kd model. For chromium release, a constant concentration model was applied for all three wastes.

Cantrell, Kirk J.; Carroll, Kenneth C.; Buck, Edgar C.; Neiner, Doinita; Geiszler, Keith N.

2013-01-01T23:59:59.000Z

385

RCRA Assessment Plan for Single-Shell Tank Waste Management Area TX-TY at the Hanford Site  

SciTech Connect

A groundwater quality assessment plan was prepared to investigate the rate and extent of aquifer contamination beneath Waste Management Area TX-TY on the Hanford Site in Washington State. This plan is an update of a draft plan issued in February 1999, which guided work performed in fiscal year 2000.

Hodges, Floyd N.; Chou, Charissa J.

2001-02-23T23:59:59.000Z

386

Development and Deployment of the Extended Reach Sluicing System (ERSS) for Retrieval of Hanford Single Shell Tank Waste - 14206 (DRAFT)  

SciTech Connect

A history of the evolution and the design development of Extended Reach Sluicer System (ERSS) is presented. Several challenges are described that had to be overcome to create a machine that went beyond the capabilities of prior generation sluicers to mobilize waste in Single Shell Tanks for pumping into Double Shell Tank receiver tanks. Off-the-shelf technology and traditional hydraulic fluid power systems were combined with the custom-engineered components to create the additional functionality of the ERSS, while still enabling it to fit within very tight entry envelope into the SST. Problems and challenges inevitably were encountered and overcome in ways that enhance the state of the art of fluid power applications in such constrained environments. Future enhancements to the ERSS design are explored for retrieval of tanks with different dimensions and internal obstacles.

Bauer, Roger E.; Figley, Reed R.; Innes, A. G.

2013-11-11T23:59:59.000Z

387

SURFACE GEOPHYSICAL EXPLORATION OF SX TANK FARM AT THE HANFORD SITE RESULTS OF BACKGROUND CHARACTERIZATION WITH MAGNETICS AND ELECTROMAGNETICS  

SciTech Connect

This report presents the results of the background characterization of the cribs and trenches surrounding the SX tank farm prepared by HydroGEOPHYSICS Inc, Columbia Energy & Environmental Services Inc and Washington River Protection Solutions.

MYERS DA; RUCKER D; LEVIT M; CUBBAGE B; HENDERSON C

2009-09-24T23:59:59.000Z

388

Implementation of Recommendations from the One System Comparative Evaluation of the Hanford Tank Farms and Waste Treatment Plant Safety Bases - 14137  

SciTech Connect

A Comparative Evaluation was conducted for One System Integrated Project Team to compare the safety bases for the Hanford Waste Treatment and Immobilization Plant Project (WTP) and Tank Operations Contract (TOC) (i.e., Tank Fanns) by an Expert Review Team. The evaluation had an overarching purpose to facilitate effective integration between WTP and TOC safety bases. It was to provide One System management with an objective evaluation of identified differences in safety basis process requirements, guidance, direction, procedures, and products (including safety controls, key safety basis inputs and assumptions, and consequence calculation methodologies) between WTP and TOC. The evaluation identified 25 recommendations (Opportunities for Integration). The resolution of these recommendations resulted in 16 implementation plans. The completion of these implementation plans will help ensure consistent safety bases for WTP and TOC along with consistent safety basis processes. procedures, and analyses. and should increase the likelihood of a successful startup of the WTP. This early integration will result in long-term cost savings and significant operational improvements. In addition, the implementation plans lead to the development of eight new safety analysis methodologies that can be used at other U.S. Department of Energy (US DOE) complex sites where URS Corporation is involved.

Garrett, Richard L.; Niemi, Belinda J.; Paik, Ingle K.; Buczek, Jeffrey A.; Lietzow, J.; McCoy, F.; Beranek, F.; Gupta, M.

2013-11-07T23:59:59.000Z

389

SOLIDIFICATION OF THE HANFORD LAW WASTE STREAM PRODUCED AS A RESULT OF NEAR-TANK CONTINUOUS SLUDGE LEACHING AND SODIUM HYDROXIDE RECOVERY  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE), Office of River Protection (ORP), is responsible for the remediation and stabilization of the Hanford Site tank farms, including 53 million gallons of highly radioactive mixed wasted waste contained in 177 underground tanks. The plan calls for all waste retrieved from the tanks to be transferred to the Waste Treatment Plant (WTP). The WTP will consist of three primary facilities including pretreatment facilities for Low Activity Waste (LAW) to remove aluminum, chromium and other solids and radioisotopes that are undesirable in the High Level Waste (HLW) stream. Removal of aluminum from HLW sludge can be accomplished through continuous sludge leaching of the aluminum from the HLW sludge as sodium aluminate; however, this process will introduce a significant amount of sodium hydroxide into the waste stream and consequently will increase the volume of waste to be dispositioned. A sodium recovery process is needed to remove the sodium hydroxide and recycle it back to the aluminum dissolution process. The resulting LAW waste stream has a high concentration of aluminum and sodium and will require alternative immobilization methods. Five waste forms were evaluated for immobilization of LAW at Hanford after the sodium recovery process. The waste forms considered for these two waste streams include low temperature processes (Saltstone/Cast stone and geopolymers), intermediate temperature processes (steam reforming and phosphate glasses) and high temperature processes (vitrification). These immobilization methods and the waste forms produced were evaluated for (1) compliance with the Performance Assessment (PA) requirements for disposal at the IDF, (2) waste form volume (waste loading), and (3) compatibility with the tank farms and systems. The iron phosphate glasses tested using the product consistency test had normalized release rates lower than the waste form requirements although the CCC glasses had higher release rates than the quenched glasses. However, the waste form failed to meet the vapor hydration test criteria listed in the WTP contract. In addition, the waste loading in the phosphate glasses were not as high as other candidate waste forms. Vitrification of HLW waste as borosilicate glass is a proven process; however the HLW and LAW streams at Hanford can vary significantly from waste currently being immobilized. The ccc glasses show lower release rates for B and Na than the quenched glasses and all glasses meet the acceptance criterion of < 4 g/L. Glass samples spiked with Re{sub 2}O{sub 7} also passed the PCT test. However, further vapor hydration testing must be performed since all the samples cracked and the test could not be performed. The waste loading of the iron phosphate and borosilicate glasses are approximately 20 and 25% respectively. The steam reforming process produced the predicted waste form for both the high and low aluminate waste streams. The predicted waste loadings for the monolithic samples is approximately 39%, which is higher than the glass waste forms; however, at the time of this report, no monolithic samples were made and therefore compliance with the PA cannot be determined. The waste loading in the geopolymer is approximately 40% but can vary with the sodium hydroxide content in the waste stream. Initial geopolymer mixes revealed compressive strengths that are greater than 500 psi for the low aluminate mixes and less than 500 psi for the high aluminate mixes. Further work testing needs to be performed to formulate a geopolymer waste form made using a high aluminate salt solution. A cementitious waste form has the advantage that the process is performed at ambient conditions and is a proven process currently in use for LAW disposal. The Saltstone/Cast Stone formulated using low and high aluminate salt solutions retained at least 97% of the Re that was added to the mix as a dopant. While this data is promising, additional leaching testing must be performed to show compliance with the PA. Compressive strength tests must also be performed on the Cast Ston

Reigel, M.; Johnson, F.; Crawford, C.; Jantzen, C.

2011-09-20T23:59:59.000Z

390

Continued Evaluation of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations  

Science Conference Proceedings (OSTI)

Laboratory (PNNL) conducted an extensive evaluation of the ability of three ultrasonic instruments to detect critical velocity for a broad range of simulated Hanford nuclear waste streams containing particles with mean particle sizes of >50 microns. Evaluations were perform using the pipe loop at the Process Development Laboratory East (PDL-E) at PNNL that was designed and built to evaluate the pipeline plugging issue during slurry transfer operations at the Hanford Waste Treatment Plant. In 2011 the ability of the ultrasonic PulseEcho system to detect critical velocity continued to be evaluated using the PDL-E flow loop and new simulants containing high-density particles with a mean particle size of < 15 microns. The PDL-E flow loop was modified for the 2011 testing to include a new test section that contained 5-MHz and 10-MHz ultrasonic transducers non-invasively mounted to schedule 40 pipe. The test section also contained reference instrumentation to facilitate direct comparison of the real-time PulseEcho transducer responses with experimentally observed critical velocities. This paper presents the results from the 2011 PulseEcho evaluation using a variety of simulated Hanford nuclear waste streams that were selected to encompass the expected high-level waste feed properties.

Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.; Jenks, Jeromy WJ; Burns, Carolyn A.; Schonewill, Philip P.; Hopkins, Derek F.; Thien, Michael G.; Wooley, Theodore A.

2012-04-01T23:59:59.000Z

391