The Offices of Science (SC) and Environmental Management (EM), U.S.
Department of Energy (DOE), hereby announce their interest in receiving proposals for
performance of innovative, fundamental research to support specific activities for high level
radioactive waste; which include, but are not limited to, characterization and safety, retrieval of
tank waste and tank closure, pretreatment, and waste immobilization and disposal.
SUPPLEMENTARY INFORMATION: The Office of Environmental Management, in
partnership with the Office of Science, sponsors the Environmental Management Science
Program (EMSP) to fulfill DOE's continuing commitment to the clean-up of DOE's
environmental legacy. The program was initiated in Fiscal Year 1996. Ideas for basic scientific
research are solicited which promote the broad national interest of a better understanding of the
fundamental characteristics of highly radioactive chemical wastes and their effects on the
environment.
The DOE Environmental Management program currently has ongoing applied research and
engineering efforts under its Technology Development Program. These efforts must be
supplemented with basic research to address long-term technical issues crucial to the EM
mission. Basic research can also provide EM with near-term fundamental data that may be
critical to the advancement of technologies that are under development but not yet at full scale
nor implemented. Proposed basic research under this Announcement should contribute to environmental
management activities that would decrease risk for the public and workers, provide opportunities
for major cost reductions, reduce time required to achieve EM's mission goals, and, in general,
should address problems that are considered intractable without new knowledge. This program
is designed to inspire "breakthroughs" in areas critical to the EM mission through basic research
and will be managed in partnership with SC. The Office of Science's well-established procedures,
as set forth in the Office of Science Merit Review System, available on the World
Wide Web at:
http://www.science.doe.gov/production/grants/merit.html will be used for
merit review of proposals submitted in response to this Announcement. Subsequent to the formal
scientific merit review, proposals that are judged to be scientifically meritorious, will be
evaluated by DOE for relevance to the objectives of the Environmental Management Science
Program and for relevance to the technical focus of this solicitation (see “Relevance to Mission”
section below). Additional information can be obtained at http://emsp.em.doe.gov.
Additional Announcements for the Environmental Management Science Program may be issued during Fiscal Year
2001 covering other areas within the scope of the EM program.
Purpose
The purpose of the EMSP is to foster basic research that will contribute to successful completion
of DOE's mission to clean-up the environmental contamination across the DOE complex.
The objectives of the Environmental Management Science Program are to:
Basic research is solicited in areas of science with the potential for addressing problems in the
clean-up of high level radioactive waste. Relevant scientific disciplines include, but are not
limited to, chemistry (including actinide chemistry, analytical chemistry and instrumentation,
interfacial chemistry, and separation science), computer and mathematical sciences, engineering
science (chemical and process engineering), materials science (degradation mechanisms,
modeling, corrosion, non-destructive evaluation, sensing of waste hosts, canisters), and physics
(fluid flow, aqueous-ionic solid interfacial properties underlying rheological processes).
Project Renewals
Lead Principal Investigators of record for Projects funded under Office of Science Notice 98-08,
Environmental Management Science Program: Research Related to High Level Radioactive
Waste, are eligible to submit renewal proposals under this solicitation.
DATES: The deadline for receipt of formal proposals is 4:30 p.m. E.S.T., March 8, 2001, in
order to be accepted for merit review and to permit timely consideration for award in Fiscal Year
2001.
ADDRESSES: Formal proposals referencing Program Announcement LAB 01-16 should be sent to: U.S.
Department of Energy, Office of Science, Medical Sciences Division, SC-73,
Office of Biological and Environmental Research, 19901
Germantown Road, Germantown, MD 20874-1290, ATTN: Program Announcement LAB 01-16. This address
must be used when submitting proposals by U.S. Postal Service Express, commercial mail
delivery service, or when hand carried by the proposer.
FOR FURTHER INFORMATION CONTACT: Dr. Roland F. Hirsch, SC-73, Mail Stop
F-237, Medical Sciences Division, Office of Biological and Environmental Research, Office of
Science, U.S. Department of Energy, 19901 Germantown Road, Germantown, MD 20874-1290,
telephone: (301) 903-9009, fax: (301) 903-0567, E-mail: roland.hirsch@science.doe.gov, or
Mr. Mark Gilbertson, Office of Basic and Applied Research, Office of Science and Technology,
Office of Environmental Management, 1000 Independence Avenue, SW, Washington, D.C.
20585, telephone: (202) 586-7150, E-mail: Mark.Gilbertson@em.doe.gov.
Program Funding
It is anticipated that up to a total of $4,000,000 of Fiscal Year 2001, Federal funds will be
available for new Environmental Management Science Program awards resulting from this
Announcement. Multiple-year funding of awards is anticipated, contingent upon the availability
of appropriated funds. Award sizes are expected to be on the order of $100,000-$300,000 per
year for total project costs for a typical three-year award. Collaborative projects involving
several research groups or more than one institution may receive larger awards if merited. The
program will be competitive and offered to investigators in universities or other institutions of
higher education, other non-profit or for-profit organizations, non-Federal agencies or entities, or
unaffiliated individuals. DOE is under no obligation to pay for any costs associated with the preparation or submission
of proposals if an award is not made. DOE reserves the right to fund in whole or part any or none of the
proposals received in response to this Announcement. All projects will be
evaluated using the same criteria, regardless of the submitting institution.
Collaboration and Training
Proposers to the EMSP are strongly encouraged to collaborate with researchers in other
institutions, such as universities, industry, non-profit organizations, federal laboratories and
Federally Funded Research and Development Centers (FFRDCs), including the DOE National
Laboratories, where appropriate, and to incorporate cost sharing and/or consortia wherever
feasible. Refer to
http://www.sc.doe.gov/production/grants/Colab.html for details.
Proposers are also encouraged to provide training opportunities, including student involvement,
in proposals submitted to the program.
Proposals
Proposers are expected to use the following format in addition to following instructions listed
later in this announcement in the Office of Science, Guide for Preparation of Scientific/Technical
Proposals to be Submitted by National Laboratories. Proposals must be written
in English, with all budgets in U.S. dollars.
In order to properly classify each proposal for evaluation and review, the proposal must
indicate the proposer's preferred scientific research field, selected from the following list.
Field of Scientific Research:
1. Actinide Chemistry
Proposal Evaluation and Selection
Relevance to Mission
Subsequent to the formal scientific merit review, proposals which are judged to be
scientifically meritorious will be evaluated by DOE for relevance to the objectives of the
Environmental Management Science Program and for relevance to the technical focus of the
solicitation (see section below).
"Researchers are encouraged to demonstrate a linkage between their research projects and
significant clean up related problems at DOE sites. Researchers could establish this linkage in a
variety of ways - for example, by elucidating the scientific problems to be addressed by the
proposed research and explaining how the solution of these problems could improve remediation
capabilities." (National Research Council, Board on Radioactive Waste Management, December
1998)
DOE shall also consider, as part of the evaluation, program policy factors such as an appropriate
balance among the program areas, including research already in progress. Research funded in the
Environmental Management Science Program in Fiscal Year 1996 through Fiscal Year 2001, can
be viewed at http://www.doe.gov/em52/science-grants.html.
Technical Focus of the Solicitation
This research announcement has been developed for Fiscal Year 2001, along with a development
process for a long-term program within Environmental Management, with the objective of
providing continuity in scientific knowledge that will revolutionize technologies and clean-up
approaches for solving DOE's most complex environmental problems. A general description of
the high level waste problem can be found in the Background section of this Announcement. Detailed
descriptions of the specific technical (science) needs and areas of emphasis associated with this
problem area are available on the Tanks Focus Area web site at
http://www.pnl.gov/tfa.
Long Term Research Agenda for High Level Radioactive Waste
The National Academy of Science’s National Research Council was requested to assist the DOE
in developing a long-range science plan for the management of radioactive high-level waste at
DOE sites. The Committee empanelled to study that issue determined that some High Level
Waste related problems will require further research and development to minimize risk and
program cost and to improve the effectiveness of clean-up. Their recommendations in four topic
areas are the focus of this solicitation and are described below. More detailed descriptions of the
specific technical (science) needs in these four topic areas are available on the Tanks Focus Area
web site at: http://www.pnl.gov/tfa.
1. Long-term issues related to tank closure:
An example of research activities to address this issue is innovative methods for in situ
characterization of the High Level Waste remaining in the tanks after retrieval to facilitate tank
closure.
2. High-efficiency, high-throughput separation methods that would reduce high-level
waste program costs over the next few decades including:
An example of a project addressing separation issues could be research on processes that remove
multiple radionuclides in a single step.
3. Robust, high loading, immobilization methods and materials that could provide
enhancements or alternatives to current immobilization strategies including:
4. Innovative methods to achieve real-time, and, when practical, in situ
characterization data for High Level Waste and process streams that would be
useful for all phases of the waste management program with emphasis on:
Attendant to paragraph 1. above, there was another area highlighted by the National Research
Council regarding long-term issues related to characterization of surrounding areas including
radionuclide and metal contamination problems in the near-field around the tanks, and
engineered surface or subsurface barriers. These topics will be a matter of a future solicitation
for research regarding subsurface contamination.
Specific High Level Waste Science Needs
Detailed information on the specific high level waste technical (science) needs within the general
topic areas of this solicitation are available from the Tanks Focus Area Home Page at:
http://www.pnl.gov/tfa. Relevance to mission reviews will
consider responsiveness to the four topic areas of this solicitation and these corresponding specific
technical needs. Additional general science research needs and information is also available at:
http://emsp.em.doe.gov/focus_area.htm.
The aforementioned areas of emphasis do not preclude, and DOE strongly encourages, any
innovative or creative ideas contributing to solving EM High Level Waste challenges mentioned
throughout this Announcement.
For further information regarding the Tanks Focus Area please contact: Mr. Theodore P. Pietrok,
Tanks Focus Area, U.S. Department of Energy, P.O. Box 550, Mail Stop K8-50, Richland, WA
99352, telephone: (509)372-4546, Fax: (509)372-4037, E-mail: Theodore_P_Pietrok@rl.gov.
Background
Environmental Management (EM) is responsible for the development, testing, evaluation, and
deployment of remediation technologies to characterize, retrieve, treat, concentrate, and dispose
of radioactive waste stored in the underground storage tanks at DOE facilities and ultimately
stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are
acceptable to both the public and regulators.
Radioactive high level waste is stored at four sites across the DOE complex:
1. Hanford Site near Richland, Washington
At these sites, 282 underground storage tanks have been used to process and store radioactive
and chemical mixed waste generated from weapon materials production and manufacturing.
Collectively, these tanks hold approximately 90 million gallons of high-level and low-level
radioactive liquid waste in sludge, saltcake, and as supernate and vapor.
Tanks vary in design from carbon or stainless steel to concrete, and concrete with carbon steel
liners. Two types of storage tanks are most prevalent: the single-shell and double-shell concrete
tanks with carbon steel liners. Capacities vary from 5,000 gallons (19m3) to 1,300,000 gallons
(4920m3). Most tanks are covered with a layer of soil ranging from approximately 3 to 10 feet
thick.
Most of the waste is alkaline and contains a diverse mixture of chemical constituents including
nitrate and nitrite salts (approximately half of the total waste), hydrated metal oxides, phosphate
precipitates, and ferrocyanides. The 784 MCi of radionuclides are distributed primarily among
the transuranic (TRU) elements and fission products, specifically strontium-90, cesium-137, and
their decay products yttrium-90 and barium-137. In-tank atmospheric conditions vary in severity
from near ambient to temperatures over 93? C. Radiation fields in the tank void space can be as
high as 10,000 rad/h.
Hanford has 177 tanks that contain approximately 53 million gallons of hazardous and
radioactive waste. There are 149 single-shell tanks that have exceeded their original design life.
Sixty-seven of these tanks have known or suspected leaks. Due to several changes in the
production processes since the early 1940s, some of the tanks contain incompatible waste
components, generating hydrogen gas and excess heat that further compromise tank integrity.
Radioactive waste at SRS consists of 33 million gallons of salt, salt solution, and sludge stored in
51 double-shell underground storage tanks, two of which have been closed (emptied of all waste
and filled with grout). Twenty-three tanks are being retired, because they do not have full
secondary containment. Nine tanks have leaked detectable quantities of waste from the primary
tank to secondary containment.
Unlike the other DOE sites, radioactive waste at INEEL was stored in acidic conditions in
stainless steel tanks rather than alkaline conditions. The 11 stainless steel tanks at INEEL store
approximately 1.2 million gallons of acidic radioactive liquids. Additionally, approximately
4000 m3 of calcined waste solids are stored in seven stainless steel bin sets enclosed in massive
underground concrete vaults.
At the West Valley Demonstration Project nearly all of the original 600,000 gallon of HLW has
been retrieved and vitrified. This site is now in the process of cleaning the storage tanks and
preparing for closure.
The general process for waste tank remediation involves a number of critical steps including:
Characterization and Safety
DOE, contractors, and stakeholders have committed to a safe and efficient remediation of HLW,
mixed waste, and hazardous waste stored in underground tanks across the DOE complex.
Currently, there are only limited fully developed or deployed in situ techniques to characterize
tank waste. In situ characterization can eliminate the time delay between sample removal and
sample analysis and aid in guiding the sampling process while decreasing the cost
(approximately $1 million is spent for one tank core extrusion) of waste analysis. Most
importantly, remote analysis eliminates sample handling and safety concerns due to worker
exposure. However, analysis of extruded tank samples allows a more complete chemical and
physical characterization of the waste when needed. Knowledge of the chemical and radioactive
composition and physical parameters of the waste is essential to safe and effective tank
remediation.
There are three primary drivers for the development of new chemical analysis methods to support
tank waste remediation: 1) provide analyses for which there are currently no reliable existing
methods, 2) replace current methods that require too much time and/or are too costly, and 3)
provide methods that evolve into on-line process analysis tools for use in waste processing
facilities.
Characterization of the elemental and isotopic chemical constituents in DOE tank waste is an
important function in support of DOE tank waste operation and remediation functions. Proper
waste characterization enables: safe operation of the tank farms; resolution of tank safety
questions; and development of processes and equipment for retrieval, pretreatment, and
immobilization of tank waste. All of these operations are dependent on the chemical analysis of
tank waste.
Current techniques of tank waste analysis involve the removal of core samples from tanks,
followed by costly and time consuming wet analytical laboratory testing. Savings in both cost
and time could be realized in techniques that involve in situ probes for direct analysis of tank
materials.
Leakage from the single shell tanks at Hanford is among the safety concerns. As indicated
earlier many of the 149 single shell tanks are known or suspected to leak. This presents a grave
problem for retrieval of waste from these tanks since the baseline method for retrieval is to sluice
thousands of gallons of water into the tank to dissolve and suspend the waste. HLW waste
leakage into the environment can threaten the ground water. There is a need to develop
instrumentation to determine the location of a leak, measure the amounts of contamination that
may have leaked, and assess the environmental impact.
Another safety concern is the long-term performance of waste forms. Performance assessments
of radionuclide containment rely primarily on the geologic barriers (e.g., long travel times in
hydrologic systems or sorption on mineral surfaces). The physical and chemical durability of the
waste form, however, can contribute greatly to the successful isolation of radionuclides; thus the
effects of radiation on physical properties and chemical durability of waste forms are of great
importance. The changes in chemical and physical properties occur over relatively long periods
of storage, up to a million years, and at temperatures that range from 100 to 300 degrees Celsius,
depending on waste loading, age of the waste, depth of burial, and the repository-specific
geothermal agent. Thus, a major challenge is to effectively simulate high-dose radiation effects
that will occur over relatively low-dose rates over long periods of time at elevated temperatures.
Similarly, there is a paramount need for improved understanding and modeling of the
degradation mechanisms and behavior of primary radioactive waste hosts and/or their
containment canisters, corrosion mechanisms and prevention in aqueous and/or alkali halide
containing environments, and remote sensing and non-destructive evaluation.
Examples of specific science research challenges include but are not limited to: basic
measurement science and sensor development required for remote detection of low
concentrations of hydrogen inside tanks and in containers; basic analytical studies needed to
develop new methods for chemical and physical characterization of solid and liquids in slurries
and for development of advanced processing methodologies; basic instrument development
needed to perform in situ radiological measurements and collect spatially resolved species and
concentration data; basic materials and engineering science needed to develop radiation hardened
instrumentation.
Retrieval of Tank Waste and Tank Closure
Underground tanks throughout the DOE complex have stored a diverse accumulation of wastes
during the past fifty years of weapons and fuel production. If these tanks were isolated in a
manner that would preclude the escape of radiation into the environment for thousands of years,
there would be no reason to disturb them. However, a number of the storage tanks are
approaching the end of their design life, and 90 tanks have either leaked or are suspecting of
having leaked waste into the soil and sediments near the tanks.
Recently, dewatering processes have removed much of the free liquid from the alkaline waste
tanks. The tanks now contain wastes ranging in consistency from remaining supernate and soft
sludge to concrete-like saltcake. Tanks also contain miscellaneous foreign objects such as
Portland cement, measuring tapes, samarium balls, and in-tank hardware such as cooling coils
and piping. Unlimited sluicing, adding large quantities of water to suspend solids, is the baseline
method for sludge removal from tanks. This process is not capable of retrieving all of the
material from tanks. Besides dealing with aging tanks and difficult wastes, retrieval also faces the
problem of the tank design itself. Retrieval tools must be able to enter the tanks, which are under
an average of 10 feet of soil, through small openings called risers in the tops of the tanks.
Retrieval of tank waste and tank closure requires tooling and process alternative enhancements to
mixing and mobilizing bulk waste as well as dislodging and conveying heels. Heel removal is
linked to tank closure. The working tools and removal devices being developed include suction
devices, rubblizing devices, water and air jets, waste conditioning devices, grit blasting devices,
transport and conveyance devices, cutting and extraction tools, monitoring devices, and various
mechanical devices for recovery or repair of waste dislodging and conveyance tools.
The areas directly below the access risers are often disturbed or contain a significant amount of
discarded debris. Therefore, evaluation of tank waste characteristics by measurements taken at
these locations may not be representative of the properties of the waste in other areas of the
tanks.
To monitor current conditions and plan for tank remediation, more information on the tank
conditions and their contents is required. Current methods used at DOE tank sites are limited to
positioning sensors, instruments, and devices to locations directly below access penetrations or
attached to a robotic arm for off-riser positioning. These systems can only deploy one type of
sensor, requiring multiple systems to perform more than one function in the tank.
Currently, decisions regarding necessary retrieval technologies, retrieval efficiencies, retrieval
durations, and costs are highly uncertain. Although tank closure has been completed on only two
HLW tanks (at Savannah River), the tank contents proved amenable to waste retrieval using
current technology. DOE has just begun to address the issue of how clean a tank must become
before it is closed. Continued demonstration that tank closure criteria can be developed and
implemented will provide substantial benefit to DOE.
A related problem that retrieval process development is examining the current lack of a retrieval
decision support tool for the end users. As development activities move forward toward
collection of retrieval performance and cost data, it has become very evident that the various sites
across the complex need to have a decision tool to assist end users with respect to waste retrieval
and tank closure. Tank closure is intimately tied to retrieval, and the sensitivity of closure
criteria to waste retrieval is expected to be very large.
All the existing processes and technologies that could be used as a baseline for tank remediation
have not yet been identified. Identifying these processes is one of EM's major issues in
addressing the tank problems. The overall purpose of retrieval enhancements is to continue to
lead the efforts in the basic understanding and development of retrieval processes in which waste
is mobilized sufficiently to be transferred out of tanks in a cost-effective and safe manner. From
that basic understanding, data are provided to end users to assist them in the retrieval decision-
making process. The overall purpose of retrieval enhancements is to identify processes that can
be used to reduce cost, improve efficiency, and reduce programmatic risk.
Basic engineering and separation science studies are needed to support tank remediation of
liquids, which contain high concentrations of solids.
Pretreatment and Separation Processes for Tank Waste
About 90 million gallons of HLW are stored in tanks at four primary sites within the DOE
complex. It is neither cost-effective nor practical to treat and dispose of all of the tank waste to
meet the requirements of the HLW repository program and the Nuclear Waste Policy Act. The
pretreatment area seeks to address multiple needs across the DOE complex. The primary
objectives are to reduce the volume of HLW, reduce hazards associated with treating LLW, and
minimize the generation of secondary waste.
The current baseline technology systems for waste pretreatment at DOE's tank waste sites are
expensive, and technology gaps exist. Large volumes of HLW will be generated, while there is
limited space in the planned Nuclear Waste Repository for HLW from DOE. Even if adequate
space were made available, treatment and disposal of HLW is still very expensive, estimated to
be about $1 million for each canister of vitrified HLW. Only a small fraction of the tank waste,
by weight, is made up of HLW radionuclides. The bulk of the waste is chemical constituents
intermingled with, and sometimes chemically bonded to, the radionuclides. The chemicals and
radionuclides can be separated into HLW and LLW fractions for less costly treatment and
disposal.
Most of the tank waste was generated as a result of nuclear fuel processing for weapons
production. In that process, irradiated fuel and its cladding were first dissolved, uranium and
plutonium were recovered as products, and the highly radioactive fission product wastes were
concentrated and sent to the tanks for long-term storage.
Fuel processing at SRS did not change substantially from the beginning of operations in about
1955 to the present. While these wastes are fairly uniform, they still require pretreatment to
separate the LLW from HLW prior to immobilization. Liquid waste at INEEL is stored under
acidic pH conditions in stainless steel tanks. The original liquid high level waste has been
calcined at high temperature to a dry powder. At Hanford, several processes were used over the
years (beginning in 1944), each with a different chemical process. This resulted in different
waste volumes and compositions. Wastes at Hanford and SRS are stored as highly alkaline
material so as not to corrode the carbon steel tanks. The process of converting the waste from
acid to alkaline resulted in the formation of different physical forms within the waste.
The primary forms of tank waste include sludge, saltcake, and liquid. The bulk of the
radioactivity is known to be in the sludge which makes it the largest source of HLW. Saltcake is
characteristic of the liquid waste with most of the water removed. Saltcake is found primarily in
older single-shell tanks at Hanford.
Saltcake and liquid waste contain mostly sodium nitrate and sodium hydroxide salts. They also
contain soluble radionuclides such as cesium. Strontium, technetium, and transuranics are also
present in varying concentrations. The radionuclides must be removed; leaving a large portion of
waste to be treated and disposed of as LLW and a very small portion that is combined with HLW
from sludge for subsequent treatment and disposition.
Over the years, tank waste has been blended and evaporated to conserve space. Although sludge
contains most of the radionuclides, the amount of HLW glass produced (vitrification is the
preferred treatment of HLW) could be very high without pretreatment of the sludge.
Pretreatment of the sludge by washing with alkaline solution can remove certain nonradioactive
constituents and reduce the volume of HLW. Pretreatment can also remove constituents that
could degrade the stability of HLW glass. The pretreatment area seeks to address multiple needs
across the DOE complex. The primary objectives are to reduce the volume of HLW, reduce
hazards associated with treating LLW, and minimize the generation of secondary waste.
The concentration of certain chemical constituents such as phosphorus, sulfur, and chromium in
sludge can greatly increase the volume of HLW glass produced upon vitrification of the sludge.
These components have limited solubility in the molten glass at very low concentrations. Some
sludge has high concentrations of aluminum compounds, which can also be a controlling factor
in determining the volume of HLW glass produced. Aluminum above a threshold concentration
in the glass must be balanced with proportional amounts of other glass-forming constituents such
as silica. There are estimated to be 25 different types of sludge at Hanford distributed among
more than 100 tanks. Samples from 49 tanks would represent approximately 93 percent of the
sludge in Hanford tanks. Testing of enhanced sludge washing, the combination of caustic
leaching and water washing of sludge, on all of these samples is needed to determine whether
enhanced sludge washing will result in an acceptable volume of HLW glass destined for the
repository and will allow processing in existing carbon steel tanks at Hanford and SRS.
The efficiency of enhanced sludge washing is not completely understood. Inadequate removal of
key sludge components could result in production of an unacceptably large volume of HLW
glass. Improvements are needed to increase the separation of key sludge constituents from the
HLW.
Enhanced sludge washing is planned to be performed batch-wise in large double-shell tanks of
nominal one million gallon capacity. This will generate substantial volumes of waste solutions
that require treatment and disposal as LLW. Settling times for suspended solids may be
excessive and the possibility of colloid or gel formation could prohibit large-scale processing.
Alternatives are needed that will reduce the amount of chemical addition required and prevent
the possibility of colloid formation. Sludge at SRS and Hanford will be washed to remove
soluble components prior to vitrification. Removing suspended solids from the wash solutions is
inherently inefficient due to long intervals required for the solids to settle out.
Approximately 1.2 million gallons of acidic liquid waste are stored in single-shell, stainless steel,
underground storage tanks at INEEL. In 1992, a Notice of Noncompliance was filed by the State
of Idaho stating that the tanks did not meet secondary containment requirements of the Resource
Conservation and Recovery Act. Subsequently, an agreement was reached between DOE, the
Environmental Protection Agency, and the Idaho Department of Health and Welfare that
commits DOE to remove the liquid waste from all underground tanks by the year 2015. Recent
discussions with the state of Idaho have accelerated this date to 2012.
The baseline treatment for INEEL liquid and calcine waste was recently reviewed as part of the
site's Environmental Impact Statement process. The site is now developing a revised roadmap to
pursue direct vitrification of the liquid waste and determine the best path to treat the calcine.
The transuranic extraction process for removal of actinides, or transuranics, from acidic wastes
has been tested on actual Idaho waste in continuous countercurrent process equipment. The
strontium extraction process shows promise for co-extraction of strontium and technetium and
also has been demonstrated on Idaho waste in continuous countercurrent operation.
DOE's underground storage tanks at Hanford, SRS, and INEEL contain liquid wastes with high
concentrations of radioactive cesium. Cesium is the primary radioactive constituent found in
alkaline supernatant wastes. Since the primary chemical components of alkaline supernatants are
sodium nitrate and sodium hydroxide, the majority of the waste could be disposed of as LLW if
the radioactivity could be reduced below Nuclear Regulatory Commission limits. Processes have
been demonstrated that removed cesium from alkaline supernatants and concentrate it for
eventual treatment and disposal as HLW.
At Hanford, cesium must be removed to a very low level (3 Ci/m3) to allow supernatant waste to
be treated as LLW and disposed of in a near-surface disposal facility. The revised Hanford
Federal Facility Agreement and Consent Order, or Tri-Party Agreement (between DOE,
Environmental Protection Agency and the Washington State Department of Ecology) also
recommends treatment of LLW in a contact-maintained or minimally shielded vitrification
facility to speed remediation and reduce costs. Cesium removal performance data are needed to
estimate dose rates for this process and provide input to the design of an LLW pretreatment
facility for Hanford supernatants.
At SRS, cesium removal from saltcake waste was planned to be accomplished through use of an
in-tank precipitation process. Due to safety and technical challenges, that process was
abandoned. Three alternatives including alkaline solvent extraction, cesium ion exchange using
crystalline silicotitanate and small tank tetraphenylborate precipitation are currently being
evaluated for use in treating the SRS saltcake waste. Cesium removal may also be needed to
separate cesium from Defense Waste Processing Facility recycle, or offgas condensate, to greatly
reduce the amount of cesium that is routed back to the waste storage tanks.
Technetium (Tc)-99 has a long half-life (210,000 years) and is very mobile in the environment
when in the form of the pertechnetate ion. Removal of Tc from alkaline supernatants and sludge
washing liquids is expected to be required at Hanford to permit treatment and disposal of these
wastes as LLW. The disposal requirements are being determined by the long-term performance
assessment of the LLW waste form in the disposal site environment. It is also expected that Tc
removal will be required for at least some wastes to meet Nuclear Regulatory Commission LLW
criteria for radioactive content. To meet these expected requirements, there is a need to develop
technology that will separate this extremely long-lived radionuclide from the LLW stream and
concentrate it for feed to HLW vitrification.
A number of liquid streams encountered in tank waste pretreatment contain fine particulate
suspended solids. These streams may include tank waste supernatant, waste retrieval sluicing
water, and sludge wash solutions. Other process streams with potential for suspended solids
include evaporator products and ion exchange feed and product streams. Suspended solids will
foul process equipment such as ion exchangers. Radioactive solids will carry over into liquid
streams destined for LLW treatment, increasing waste volume for disposal and increasing the
need for shielding of process equipment. Streams with solid/liquid separation needs exist at all
of the DOE tank waste sites.
Some examples of specific science research challenges include but are not limited to:
fundamental analytical chemical studies needed for improvement of separation processes;
materials science of waste forms germane to their performance; elucidation of technetium
chemistry; basic engineering and separation science studies required to support pretreatment
activities and the development of solid/liquid separations; fundamental separations chemistry of
precipitating agent and ion exchange media needed to support the development of improved
methods for decontamination of HLW; fundamental physical chemistry studies of sodium
nitrate/nitrite needed for HLW processing; basic materials science studies concerned with the
dissolution of mixed oxide materials characteristic of calcine waste needed to design improved
pretreatment processes; basic chemistry of sodium when mixed with rare earth oxides needed for
the development of alternative HLW forms.
Waste Immobilization and Disposal
Waste immobilization processes convert radioactive waste into solid waste forms that will last in
natural environments for thousands of years. DOE tank wastes requiring immobilization include
LLW such as the pretreated liquid tank waste and HLW such as the tank sludge. There are also a
number of secondary wastes requiring immobilization that result from tank waste remediation
operations, such as resins from cesium and technetium removal operations.
The baseline technologies to immobilize radioactive wastes from underground storage tanks at
DOE sites include converting LLW to either grout or glass and converting HLW to borosilicate
glass. Grout is a cement-based waste form that is produced in a mixer tank and then poured into
canisters or pumped into vaults. Glass waste forms are created in a ceramic-lined metal furnace
called a melter. Tank waste and dry materials used to form glass are mixed and heated in the
melter to temperatures ranging from 1,800 F to 2,200 F. The molten mixture is then poured into
log-shaped canisters for storage and disposal. The working assumption is that the LLW will be
disposed of on site, or at the Waste Isolation Pilot Plant if transuranic elements are present. The
HLW will be shipped for off-site disposal in a licensed HLW repository, such as the one
proposed at Yucca Mountain, Nevada.
Methods are needed to immobilize the LLW fraction resulting from the separation of
radionuclides from the liquid and high-level calcine wastes at INEEL. LLW is to be mixed with
grout, poured into steel drums, and transferred to an interim storage facility, but alternatives are
being considered. Tests must be conducted with surrogate and actual wastes to support selection
of a final waste form. SRS has selected saltstone grout (pumped to above ground concrete vaults
and solidified) as the final waste form for LLW.
DOE sites at Hanford, SRS, and INEEL will remove cesium from the hazardous radioactive
liquid waste in the underground storage tanks. If cesium is removed, it costs less to treat the rest
of the waste. However, cesium removal from tank waste, while cost-effective, creates a
significant volume of solid waste that must be turned into a final waste form for ultimate
disposal. The plan is to separate cesium from the liquid waste using ion exchange or other
separations media, treat the cesium-loaded separations media to prepare it for vitrification, and
convert the cesium product into a glass waste form suitable for final disposal. Personnel
exposures during processing and the amount of hazardous species in the offgases must be kept
within safe limits at all times.
The effectiveness of advanced oxidation technology for treating organic cesium-loaded
separations media prior to vitrification is not proven. After a suitable melter feed is obtained,
vitrification of the cesium-loaded media must be demonstrated. Technology development is
needed because: 1) Compounds are in the separation media that must be destroyed or they will
cause flammability problems in the melter and decrease the durability and waste loading of the
final waste form; 2) High beta/gamma dose rates are associated with handling cesium-containing
waste; and 3) Cesium volatizes in the melter and becomes a highly radioactive offgas problem.
Confidence and assurance that long-term immobilization will be successful in borosilicate glass
warrants research and improved understanding of the structural and thermodynamic properties of
glass (including the structure and energetics of stable and metastable phases), systematic
irradiation studies that will simulate long term self-irradiation doses and spectra, (including
archived glasses containing Pu or Cm, and over the widest range of dose, dose rate and
temperature) and predictive theory and modeling based on computer simulations (including ab
initio, Monte Carlo, and other methods).
Some examples of specific science research challenges include but are not limited to:
fundamental chemical studies needed to determine species concentrations above molten glass
solutions containing heavy metals, cesium, strontium, lanthanides, actinides, with and without a
cold cap composed of unmelted material; materials science studies of molten materials that
simulate conditions anticipated during vitrification and storage in vitrified form of HLW needed
to develop improved processes and formulations; fundamental physical chemistry studies of
sodium nitrate/nitrite mixtures needed for HLW stabilization.
References for Background Information
Note: World Wide Web locations of these documents are provided where possible. For those
without access to the World Wide Web, hard copies of these references may be obtained by
writing Mark A. Gilbertson at the address listed in the FOR FURTHER INFORMATION
CONTACT section of this Announcement.
DOE. 2000. DOE's Research and Development Portfolio for FY 2001.
http://www.osti.gov/portfolio/
DOE. 2000. Paths to Closure - A collection of documents on accelerating clean-up
http://www.em.doe.gov/closure/
DOE. 2000. Tanks Focus Area References and Bibliography
http://www.pnl.gov/tfa/back/reference.stm
DOE. 2000. Environmental Management Dynamic Organization Chart.
http://www.em.doe.gov/orgchart.html
DOE. 2000. Environmental Management Science Program.
http://www.em.doe.gov/
DOE. 2000. Office of Science and Technology (EM-50).
http://ost.em.doe.gov/
NRC. 2000. Long-Term Research Needs for High-Level Waste at Department of Energy Sites:
Interim Report. http://www.nap.edu/catalog/9992.html
NRC. 2000. Alternatives for High-Level Waste Salt Processing at the Savannah River Site.
http://www.nap.edu/books/0309071941/html/
NRC. 1999. Disposition of High-Level Radioactive Waste Through Geological Isolation:
Development, Current Status, and Technical and Policy Challenges.
http://books.nap.edu/books/0309067782/html/1.html
NRC. 1999. Interim Report -- Committee on Cesium Processing Alternatives for High-Level
Waste at the Savannah River Site.
http://books.nap.edu/books/NI000350/html/index.html
NRC. 1999. Alternative High-Level Waste Treatments at the Idaho National Engineering and
Environmental Laboratory.
http://books.nap.edu/books/030906628X/html/129.html
The instructions and format described below should be followed. Reference Program Announcement
LAB 01-16 on all submissions and inquiries about this program.
1. Provide scientific knowledge that will revolutionize technologies and clean-up approaches to
significantly reduce future costs, schedules, and risks;
Representative Research Areas
2. "Bridge the gap" between broad fundamental research that has wide-ranging applicability
such as that performed in DOE's Office of Science and needs-driven applied technology
development that is conducted in EM's Office of Science and Technology; and
3. Focus the Nation's science infrastructure on critical DOE environmental management
problems.
Proposal Categories
2. Analytical Chemistry and Instrumentation
3. Separations Chemistry
4. Engineering Sciences
5. Geochemistry
6. Geophysics
7. Hydrogeology
8. Interfacial Chemistry
9. Materials Science
10. Other
a. High-efficiency separation, and
Proposals on separation sciences addressing these two areas are encouraged. The projects
should address all types of separations: solids from liquids from gases, High Level Waste from
low level waste, and radionuclides from organic compounds.
b. Minimization of the volume of secondary waste.
a. Alternatives to borosilicate glasses using slurry-fed electric (Joule) melter as an
immobilization matrix, and
As an example, a research project might study alternative immobilization matrixes, tailored to
either High Level Waste or low level waste, such as cement or crystalline ceramics. Proposals
to conduct research on alternative melter techniques that would increase the processes available
to address different waste streams leading to more efficient immobilization results are
encouraged.
b. Alternatives melter techniques.
a. Characterization of the waste after retrieval, for instance in process streams and melter
feeds.
Proposals aimed at developing techniques to achieve shorter turn-around times for the
analytical results, which in turn would allow better control of High Level Waste processing are
encouraged. An example of such a project is research on fiber-optical interrogation to
characterize process streams.
2. Savannah River Site (SRS) near Aiken, South Carolina
3. Idaho National Engineering and Environmental Laboratory (INEEL) near Idaho Falls, Idaho
4. West Valley Demonstration Project (WVDP) in West Valley, New York
Tank remediation problems within these critical process steps are described below. Several
process steps are combined for the purpose of describing related technical issues
Proposals from National Laboratories submitted to the Office of Science (SC) as a result of this program announcement will follow the Department of Energy Field Work Proposal process with additional information requested to allow for scientific/technical merit review. The following guidelines for content and format are intended to facilitate an understanding of the requirements necessary for SC to conduct a merit review of a proposal. Please follow the guidelines carefully, as deviations could be cause for declination of a proposal without merit review.
1. Evaluation Criteria
Proposals will be subjected to formal merit review (peer review) and will be evaluated against the following criteria which are listed in descending order of importance:
Appropriateness of the proposed method or approach
Competency of the personnel and adequacy of the proposed resources
Reasonableness and appropriateness of the proposed budget
2. Summary of Proposal Contents
An original and seven copies of the formal proposal/FWP must be submitted.
3. Detailed Contents of the Proposal
Proposals must be readily legible, when photocopied, and must conform to the following three requirements: the height of the letters must be no smaller than 10 point with at least 2 points of spacing between lines (leading); the type density must average no more than 17 characters per inch; the margins must be at least one-half inch on all sides. Figures, charts, tables, figure legends, etc., may include type smaller than these requirements so long as they are still fully legible.
3.1 Field Work Proposal Format (Reference DOE Order 5700.7C)
(DOE ONLY)
The Field Work Proposal (FWP) is to be prepared and submitted consistent with policies of the investigator's laboratory and the local DOE Operations Office. Additional information is also requested to allow for scientific/technical merit review.
Laboratories may submit proposals directly to the SC Program office listed above. A copy should also be provided to the appropriate DOE operations office.
3.2 Proposal Cover Page
The following proposal cover page information may be placed on plain paper. No form is required.
*The signature certifies that personnel and facilities are available as stated in the proposal, if the project is funded.
Provide the initial page number for each of the sections of the proposal. Number pages consecutively at the bottom of each page throughout the proposal. Start each major section at the top of a new page. Do not use unnumbered pages and do not use suffices, such as 5a, 5b.
3.4 Abstract
Provide an abstract of no more than 250 words. Give the broad, long-term objectives and what the specific research proposed is intended to accomplish. State the hypotheses to be tested. Indicate how the proposed research addresses the SC scientific/technical area specifically described in this announcement.
3.5 Narrative
The narrative comprises the research plan for the project and is limited to 25 pages. It should contain the following subsections:
Background and Significance: Briefly sketch the background leading to the present proposal, critically evaluate existing knowledge, and specifically identify the gaps which the project is intended to fill. State concisely the importance of the research described in the proposal. Explain the relevance of the project to the research needs identified by the Office of Science. Include references to relevant published literature, both to work of the investigators and to work done by other researchers.
Preliminary Studies: Use this section to provide an account of any preliminary studies that may be pertinent to the proposal. Include any other information that will help to establish the experience and competence of the investigators to pursue the proposed project. References to appropriate publications and manuscripts submitted or accepted for publication may be included.
Research Design and Methods: Describe the research design and the procedures to be used to accomplish the specific aims of the project. Describe new techniques and methodologies and explain the advantages over existing techniques and methodologies. As part of this section, provide a tentative sequence or timetable for the project.
Subcontract or Consortium Arrangements: If any portion of the project described under "Research Design and Methods" is to be done in collaboration with another institution, provide information on the institution and why it is to do the specific component of the project. Further information on any such arrangements is to be given in the sections "Budget and Budget Explanation", "Biographical Sketches", and "Description of Facilities and Resources".
3.6 Literature Cited
List all references cited in the narrative. Limit citations to current literature relevant to the proposed research. Information about each reference should be sufficient for it to be located by a reviewer of the proposal.
3.7 Budget and Budget Explanation
A detailed budget is required for the entire project period, which normally will be three years, and for each fiscal year. It is preferred that DOE's budget page, Form 4620.1 be used for providing budget information*. Modifications of categories are permissible to comply with institutional practices, for example with regard to overhead costs.
A written justification of each budget item is to follow the budget pages. For personnel this should take the form of a one-sentence statement of the role of the person in the project. Provide a detailed justification of the need for each item of permanent equipment. Explain each of the other direct costs in sufficient detail for reviewers to be able to judge the appropriateness of the amount requested.
Further instructions regarding the budget are given in section 4 of this guide.
* Form 4620.1 is available at web site: http://www.sc.doe.gov/production/grants/forms.html
3.8 Other Support of Investigators
Other support is defined as all financial resources, whether Federal, non-Federal, commercial or institutional, available in direct support of an individual's research endeavors. Information on active and pending other support is required for all senior personnel, including investigators at collaborating institutions to be funded by a subcontract. For each item of other support, give the organization or agency, inclusive dates of the project or proposed project, annual funding, and level of effort devoted to the project.
3.9 Biographical Sketches
This information is required for senior personnel at the laboratory submitting the proposal and at all subcontracting institutions. The biographical sketch is limited to a maximum of two pages for each investigator.
3.10 Description of Facilities and Resources
Describe briefly the facilities to be used for the conduct of the proposed research. Indicate the performance sites and describe pertinent capabilities, including support facilities (such as machine shops) that will be used during the project. List the most important equipment items already available for the project and their pertinent capabilities. Include this information for each subcontracting institution, if any.
3.11 Appendix
Include collated sets of all appendix materials with each copy of the proposal. Do not use the appendix to circumvent the page limitations of the proposal. Information should be included that may not be easily accessible to a reviewer.
Reviewers are not required to consider information in the Appendix, only that in the body of the proposal. Reviewers may not have time to read extensive appendix materials with the same care as they will read the proposal proper.
The appendix may contain the following items: up to five publications, manuscripts (accepted for publication), abstracts, patents, or other printed materials directly relevant to this project, but not generally available to the scientific community; and letters from investigators at other institutions stating their agreement to participate in the project (do not include letters of endorsement of the project).
4. Detailed Instructions for the Budget
(DOE Form 4620.1 "Budget Page" may be used)
4.1 Salaries and Wages
List the names of the principal investigator and other key personnel and the estimated number of person-months for which DOE funding is requested. Proposers should list the number of postdoctoral associates and other professional positions included in the proposal and indicate the number of full-time-equivalent (FTE) person-months and rate of pay (hourly, monthly or annually). For graduate and undergraduate students and all other personnel categories such as secretarial, clerical, technical, etc., show the total number of people needed in each job title and total salaries needed. Salaries requested must be consistent with the institution's regular practices. The budget explanation should define concisely the role of each position in the overall project.
4.2 Equipment
DOE defines equipment as "an item of tangible personal property that has a useful life of more than two years and an acquisition cost of $25,000 or more." Special purpose equipment means equipment which is used only for research, scientific or other technical activities. Items of needed equipment should be individually listed by description and estimated cost, including tax, and adequately justified. Allowable items ordinarily will be limited to scientific equipment that is not already available for the conduct of the work. General purpose office equipment normally will not be considered eligible for support.
4.3 Domestic Travel
The type and extent of travel and its relation to the research should be specified. Funds may be requested for attendance at meetings and conferences, other travel associated with the work and subsistence. In order to qualify for support, attendance at meetings or conferences must enhance the investigator's capability to perform the research, plan extensions of it, or disseminate its results. Consultant's travel costs also may be requested.
4.4 Foreign Travel
Foreign travel is any travel outside Canada and the United States and its territories and possessions. Foreign travel may be approved only if it is directly related to project objectives.
4.5 Other Direct Costs
The budget should itemize other anticipated direct costs not included under the headings above, including materials and supplies, publication costs, computer services, and consultant services (which are discussed below). Other examples are: aircraft rental, space rental at research establishments away from the institution, minor building alterations, service charges, and fabrication of equipment or systems not available off-the-shelf. Reference books and periodicals may be charged to the project only if they are specifically related to the research.
a. Materials and Supplies
The budget should indicate in general terms the type of required expendable materials and supplies with their estimated costs. The breakdown should be more detailed when the cost is substantial.
b. Publication Costs/Page Charges
The budget may request funds for the costs of preparing and publishing the results of research, including costs of reports, reprints page charges, or other journal costs (except costs for prior or early publication), and necessary illustrations.
c. Consultant Services
Anticipated consultant services should be justified and information furnished on each individual's expertise, primary organizational affiliation, daily compensation rate and number of days expected service. Consultant's travel costs should be listed separately under travel in the budget.
d. Computer Services
The cost of computer services, including computer-based retrieval of scientific and technical information, may be requested. A justification based on the established computer service rates should be included.
e. Subcontracts
Subcontracts should be listed so that they can be properly evaluated. There should be an anticipated cost and an explanation of that cost for each subcontract. The total amount of each subcontract should also appear as a budget item.
4.6 Indirect Costs
Explain the basis for each overhead and indirect cost. Include the current rates.