SPECIAL NOTICE
99 -- Request For Information (RFI) No. DE-RI52-08NA28733
- Notice Date
- 2/28/2008
- Notice Type
- Special Notice
- Contracting Office
- n/a n/a NM, 87185
- ZIP Code
- 87185
- Solicitation Number
- DOE-SNOTE-080228-001
- Archive Date
- 12/31/2010
- E-Mail Address
-
Email your questions to David Gallegos, Contract Officer
(dgallegos@doeal.gov)
- Description
- Program Manager: Parrish Staples, Reactor Conversions Program Manager, Global Threat Reduction Initiative NA-21, US DOE National Nuclear Security Administration Information Requested: Interest and Capability to produce very high density low-enriched uranium (LEU) fuel for use in high performance research and test reactors. The request is under the Fuel Fabrication Capability (FFC) Project for the Office of the U.S. Department of Energy???s National Nuclear Security Administration (NNSA) Global Threat Reduction Initiative (NNSA NA-21 Office). Purpose: The purpose of this Request for Information (RFI) is to identify options and capabilities within the nuclear sector that contribute to production-level fabrication of very-high density, low enriched uranium (LEU) research reactor fuel. This fuel is needed to support the reactor conversion mission of the Global Threat Reduction Initiative (GTRI) for the minimization of highly enriched uranium (HEU) in civilian applications. Description: The GTRI Reactor Conversion mission statement is to support the minimization and, to the extent possible, elimination of the use of HEU in civil nuclear applications. This is accomplished by working to convert research and test reactors and radioisotope production processes to the use of LEU fuel/LEU targets throughout the world. The GTRI Reactor Conversion Program, formerly known as the Reduced Enrichment for Research and Test Reactors (RERTR) Program, is one of GTRI???s three main technical pillars. The GTRI Reactor Conversion Program was initially formed in 1978 by the U.S. Department of Energy (DOE) to develop the technical means for the conversion of research reactors from weapons-grade HEU to LEU. The Program accomplishes this goal (1) by developing LEU fuels and targets necessary for conversion, (2) assisting operators in the conversion of existing research reactors and isotope production processes by helping prepare the regulatory approval for conversion while maintaining both the reactor performance and ability to achieve the facility???s mission. The GTRI initiative was announced in May 2004 by Former Secretary of Energy Spencer Abraham. Under GTRI, the U.S. DOE has established goals for the conversion of HEU-fueled research reactors. The goal includes the conversion of 129 research and test reactors to the use of LEU fuel by 2018, and to have those reactors that can convert with currently available LEU fuel or with LEU fuel currently under development in the GTRI Reactor Conversion program converted to such LEU fuels by 2014. The GTRI Conversion program is developing very high density fuel based on a Uranium-Molybdenum (U-Mo) alloy that, in foil form, can reach densities of up to 16 g/cc U. Among the reactors targeted for conversion with this fuel are six US high-performance (HP) research reactors, all using fuel assemblies based on plate-type fuels. These six reactors are committed to using this new LEU fuel to convert, provided that the fuel meets the reactor requirements for performance and does not significantly impact reactor operational capabilities. These six reactors include the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL), the Advanced Test Reactor and associated critical facility (ATR, ATR-C) at Idaho National Laboratory (INL), the National Bureau of Standards Reactor (NBSR) research reactor at the National Institute of Standards and Technology, the Missouri University Research Reactor (MURR) at the University of Missouri???Columbia, and the MITR-II reactor at the Massachusetts Institute of Technology (MIT). The capability to fabricate this new fuel and thus enable the conversion of these 6 US HP Reactor???s does not currently exist. As a result, NNSA is seeking (through issuance of this RFI) to identify commercially available options and capabilities to assist in the establishment of this capability. Although this request is focused on providing fabrication capability needed to supply the 6 US HP reactors identified above, it must be recognized that the potential exists for the use of the fabrication capability to supply additional reactors. Up to 5 HP reactors in Western Europe, with plate-based assemblies could also use the U-Mo fuel for conversion. Moreover, reactors currently operating with lower density LEU silicide plate-type fuel may be interested in switching to higher density U-Mo fuel if it is deemed advantageous for fuel lifecycle management. Very High-Density LEU Fuel: The six US reactors identified for conversion currently utilize traditional cermet dispersion-type fuels characterized by a finely dispersed fuel phase (U3O8, UAlx, U3Si2) in an aluminum matrix. The total uranium loading that can be achieved with this type of fuel is limited by the uranium density of the specific fuel phase and the allowable fuel phase volume fraction. Changing the fuel phase to a U-Mo based alloy increases the uranium density by 3 to 7 times more than that achievable in existing fuel materials. The volume fraction of fuel in the dispersion fuel meat is typically limited to a maximum of 55% by its fabrication behavior. The metallic nature of the U-Mo fuel allows the fuel meat to be replaced by a monolithic fuel core (i.e. the matrix material is eliminated) resulting in another doubling of the uranium loading. However, the monolithic fuel design requires the development of new fabrication techniques to generate U-Mo foils and then to bond aluminum cladding to these foils. The NNSA is leading an active fuel development program that is making rapid progress in two key areas, fuel performance and fabrication technology. Fuel performance testing is being performed to develop a detailed understanding of fuel behavior and to conduct the demonstration testing. The result of this effort will eventually constitute the basis for NRC qualification of the fuel and for reactor operators to request licenses to operate with the fuel. Completion of this testing is expected in 2010 and NRC qualification that will enable use of the fuel in the US HP reactors is anticipated in 2011. The development of fabrication technology is an integral component of the fuel performance testing. Due to large differences in mechanical properties of aluminum and U-Mo, traditional compacting and rolling techniques are not adequate to fabricate the U-Mo monolithic fuel. Processes to fabricate thin U-Mo foils by casting and rolling have been developed and will be demonstrated on a scale suitable for commercial supply. Processes to apply cladding by friction bonding and hot isostatic pressing have been demonstrated and are being refined prior to demonstration at a scale suitable for commercial implementation. The remaining aspects of fuel assembly fabrication should remain identical to those currently in place. It is anticipated that commercially viable fabrication techniques will be demonstrated in concert with the fuel qualification effort. The US reactors will not be converted simultaneously and the current fuel fabrication capability must be maintained as all US reactors achieve full conversion. This will also allow the fuel fabrication capability to be phased in gradually for each unique reactor assembly. A more extensive discussion of the anticipated facility throughput and fabrication process is provided in the Conceptual Process Description for the Manufacture of Low-Enriched Uranium-Molybdenum Fuel, INL/EXT-08-13840, Rev 0, which is available at the following web site (http://www.rertr.anl.gov). The web site also contains numerous background papers on the fuel development and performance which can be found under the annual RERTR International Meeting Proceedings. Papers on the studies to convert the U.S. HP reactors are also found in the last three RERTR International Meetings and can be consulted to gain a better understanding of the fuel assembly designs for these reactors. Request for Information on Fabrication Capability: NNSA is requesting that interested parties provide the following information to assist in determining the most economical and effective approaches to meeting the LEU U-Mo monolithic fuel production necessary to support the HPR conversions and continued operations. Please provide information in the following areas: Fuel Fabrication Experience 1. Summarize your experience fabricating fuel and/or handling nuclear material. Response should include the type of fuel fabricated, relevant fabrication processes applied, type of nuclear material handled, etc. 2. Describe any special expertise or capabilities you have that may contribute to the successful production of LEU U-Mo fuel within the 2014 timeline projected for the program to accomplish the mission? 3. Are you currently NQA1 certified to fabricate nuclear fuels? Facility Licensing 1. Do you currently operate any NRC licensed facilities? If so, please list. 2. Would fabricating the LEU U-Mo fuel at your site require a new NRC license or a revision to an existing one? 3. Describe your experience related to Safeguards and Security of fissile materials, including Material Control and Accountability requirements. Production Considerations 1. Which of the proposed fuel fabrication capability business models listed below would you consider participating in? Are there alternate business models you would propose? Include the proposed location for the fuel fabrication capability in the business model response. Also, please describe the pricing model you would employ to recoup capital and operation costs for each business model of interest. a. The technical knowledge needed to implement the fabrication technology developed for monolithic U-Mo fuel is provided by the GTRI Reactor Conversion program. The fabrication capability owner (fuel supplier) would provide a facility and the equipment necessary to fabricate the required HP Research Reactor???s fuel. The GTRI Fuel Development program would work with the fuel supplier to transfer the relevant fabrication technology (developed by the program) to the fuel supplier. The document entitled ???Conceptual Process Description For The Manufacture Of Low-Enriched Uranium-Molybdenum Fuel??? provides a brief reference description of the fabrication process and technologies, and is located the File Attachments section below. b. The technical knowledge needed to implement the fabrication technology developed for monolithic U-Mo fuel and the equipment necessary to fabricate the fuel is provided by the GTRI Reactor Conversion program. As in business model a., the GTRI Fuel Development program will transfer the relevant technology necessary to fabricate the fuel to the fuel supplier. The program will also populate a facility provided by the fuel supplier with the equipment necessary to fabricate the fuel. c. The GTRI Reactor Conversion program supplies the technical knowledge needed to implement the fabrication technology, the fabrication equipment, and the fabrication facility necessary to fabricate monolithic U-Mo fuel. All fabrication technology and capital will be provided by the GTRI program and the fuel supplier would operate the facility on DOE???s behalf. Responses may include mixed business models for different aspects of fuel fabrication (i.e. foil fabrication, plate assembly, element assembly, etc.). Responses may also include business models which address only that capacity of fuel fabrication capability desired for participation (i.e. foil fabrication supply only, or to receive foils and fabricate plates and elements only, etc.). 2. Other considerations and comments. RFI Response Submission Instructions: Disclaimer: This RFI is issued solely for information and planning purposes and does not constitute a solicitation. In accordance with FAR 15.201 (e), responses to this notice are not offers and cannot be accepted by the Government to form a binding contract. Respondents are solely responsible for all expenses associated with responding to this RFI and responses to this RFI will not be returned. The purpose of this RFI is solely to solicit input for NNSA consideration in determining the most beneficial and efficient way for allowing the US to meet its commitment of conversion of all civilian research reactors to LEU fuel by 2014 for which LEU fuel exists or is currently under development. Responses to this RFI should be prepared in MS Word or PDF format, and e-mailed to Parrish Staples, NNSA Reactor Conversions Program Manager, parrish.stables@nnsa.doe.gov by Tuesday, April 15, 2008. The Department thanks you for your assistance and input.
- Web Link
-
Click here for further details regarding this notice.
(http://e-center.doe.gov/doebiz.nsf/UNID/DAC65793B94A4CA3852573FD006553C3?OpenDocument)
- Record
- SN01519412-W 20080301/080228223840 (fbodaily.com)
- Source
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