7 Matching Results

Search Results

Advanced search parameters have been applied.

2005 Update for Implementing Best Available Technology per DOE Order 5400.5

Description: The report addresses Best Available Technology per DOE Order 5400.5 in relation to wastewater discharges to the soil. In accordance with Contract Data Requirements List F.19, this report addresses the Best Available Technology requirements per Department of Energy (DOE) Order 5400.5, "Radiation Protection of the Public and the Environment", as they apply to radiological discharges to the soil for Calendar Year 2005. The report includes review of discharges for both, Battelle Energy Alliance, LLC and CH2M WG Idaho, LLC. The Best Available Technology selection process is applicable to wastewater discharges containing process derived radionuclides to surface waters, sanitary sewerages greater than five times the Derived Concentration Guideline (found in DOE Order 5400.5), and to the soil. Wastewater at the Idaho National Laboratory Site is not discharged to surface water (Big Lost River and Birch Creek) nor is it discharged to sanitary sewerages at activity levels greater than five times a Derived Concentration Guideline. Therefore, this report focuses on radiological discharges to the soil.
Date: September 1, 2006
Creator: INL
Partner: UNT Libraries Government Documents Department

Creep rupture testing of alloy 617 and A508/533 base metals and weldments.

Description: The NGNP, which is an advanced HTGR concept with emphasis on both electricity and hydrogen production, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 750-1000 C. Alloy 617 is a prime candidate for VHTR structural components such as reactor internals, piping, and heat exchangers in view of its resistance to oxidation and elevated temperature strength. However, lack of adequate data on the performance of the alloy in welded condition prompted to initiate a creep test program at Argonne National Laboratory. In addition, Testing has been initiated to evaluate the creep rupture properties of the pressure vessel steel A508/533 in air and in helium environments. The program, which began in December 2009, was certified for quality assurance NQA-1 requirements during January and February 2010. Specimens were designed and fabricated during March and the tests were initiated in April 2010. During the past year, several creep tests were conducted in air on Alloy 617 base metal and weldment specimens at temperatures of 750, 850, and 950 C. Idaho National Laboratory, using gas tungsten arc welding method with Alloy 617 weld wire, fabricated the weldment specimens. Eight tests were conducted on Alloy 617 base metal specimens and nine were on Alloy 617 weldments. The creep rupture times for the base alloy and weldment tests were up to {approx}3900 and {approx}4500 h, respectively. The results showed that the creep rupture lives of weld specimens are much longer than those for the base alloy, when tested under identical test conditions. The test results also showed that the creep strain at fracture is in the range of 7-18% for weldment samples and were much lower than those for the base alloy, under similar test conditions. In general, the weldment specimens showed more of ...
Date: January 17, 2012
Creator: Natesan, K.; Li, M.; Soppet, W.K. & Rink, D.L. (Nuclear Engineering Division)
Partner: UNT Libraries Government Documents Department

Idaho National Laboratory Cultural Resource Monitoring Report for FY 2010

Description: This report describes the cultural resource monitoring activities of the Idaho National Laboratory’s (INL) Cultural Resource Management (CRM) Office during fiscal year 2010 (FY 2010). Throughout the year, thirty-three cultural resource localities were revisited, including somethat were visited more than once, including: two locations with Native American human remains, one of which is a cave, two additional caves, twenty-six prehistoric archaeological sites, two historic stage stations, and Experimental Breeder Reactor-I, which is a designated National Historic Landmark. The resources that were monitored included seventeen that are routinely visited and sixteen that are located in INL project areas. Although impacts were documented at a few locations and one trespassing incident (albeit sans formal charges) was discovered, no significant adverse effects that would threaten the National Register eligibility of any resources were observed. Monitoring also demonstrated that several INL projects generally remain in compliance with recommendations to protect cultural resources.
Date: October 1, 2010
Creator: Office, INL Cultural Resource Management
Partner: UNT Libraries Government Documents Department

ZPPR-20 phase D : a cylindrical assembly of polyethylene moderated U metal reflected by beryllium oxide and polyethylene.

Description: The Zero Power Physics Reactor (ZPPR) fast critical facility was built at the Argonne National Laboratory-West (ANL-W) site in Idaho in 1969 to obtain neutron physics information necessary for the design of fast breeder reactors. The ZPPR-20D Benchmark Assembly was part of a series of cores built in Assembly 20 (References 1 through 3) of the ZPPR facility to provide data for developing a nuclear power source for space applications (SP-100). The assemblies were beryllium oxide reflected and had core fuel compositions containing enriched uranium fuel, niobium and rhenium. ZPPR-20 Phase C (HEU-MET-FAST-075) was built as the reference flight configuration. Two other configurations, Phases D and E, simulated accident scenarios. Phase D modeled the water immersion scenario during a launch accident, and Phase E (SUB-HEU-MET-FAST-001) modeled the earth burial scenario during a launch accident. Two configurations were recorded for the simulated water immersion accident scenario (Phase D); the critical configuration, documented here, and the subcritical configuration (SUB-HEU-MET-MIXED-001). Experiments in Assembly 20 Phases 20A through 20F were performed in 1988. The reference water immersion configuration for the ZPPR-20D assembly was obtained as reactor loading 129 on October 7, 1988 with a fissile mass of 167.477 kg and a reactivity of -4.626 {+-} 0.044{cents} (k {approx} 0.9997). The SP-100 core was to be constructed of highly enriched uranium nitride, niobium, rhenium and depleted lithium. The core design called for two enrichment zones with niobium-1% zirconium alloy fuel cladding and core structure. Rhenium was to be used as a fuel pin liner to provide shut down in the event of water immersion and flooding. The core coolant was to be depleted lithium metal ({sup 7}Li). The core was to be surrounded radially with a niobium reactor vessel and bypass which would carry the lithium coolant to the forward inlet plenum. Immediately inside the ...
Date: September 30, 2006
Creator: Lell, R.; Grimm, K.; McKnight, R.; Shaefer, R.; Division, Nuclear Engineering & INL
Partner: UNT Libraries Government Documents Department

Value Added Products from Hemicellulose Utilization in Dry Mill Ethanol Plants

Description: The Iowa Corn Promotion Board is the principal contracting entity for this grant funded by the US Department of Agriculture and managed by the US Department of Energy. The Iowa Corn Promotion Board subcontracted with New Jersey Institute of Technology, KiwiChem, Pacific Northwest National Lab and Idaho National Lab to conduct research for this project. KiwiChem conducted the economic engineering assessment of a dry-mill ethanol plant. New Jersey Institute of Technology conducted work on incorporating the organic acids into polymers. Pacific Northwest National Lab conducted work in hydrolysis of hemicellulose, fermentation and chemical catalysis of sugars to value-added chemicals. Idaho National Lab engineered an organism to ferment a specific organic acid. Dyadic, an enzme company, was a collaborator which provided in-kind support for the project. The Iowa Corn Promotion Board collaborated with the Ohio Corn Marketing Board and the Minnesota Corn Merchandising Council in providing cost share for the project. The purpose of this diverse collaboration was to integrate the hydrolysis, the conversion and the polymer applications into one project and increase the likelihood of success. This project had two primary goals: (1) to hydrolyze the hemicellulose fraction of the distillers grain (DG) coproduct coming from the dry-mill ethanol plants and (2) convert the sugars derived from the hemicellulose into value-added co-products via fermentation and chemical catalysis.
Date: March 30, 2007
Creator: Rodney Williamson, ICPB; John Magnuson, PNNL; David Reed, INL; Marco Baez, Dyadic & Marion Bradford, ICPB
Partner: UNT Libraries Government Documents Department

Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.

Description: An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.
Date: March 1, 2010
Creator: Tentner, A. M.; Parma, E.; Wei, T.; Wigeland, R.; Division, Nuclear Engineering; SNL et al.
Partner: UNT Libraries Government Documents Department

Status report on fast reactor recycle and impact on geologic disposal.

Description: The GNEP program envisions continuing the use of light-water reactors (LWRs), with the addition of processing the discharged, or spent, LWR fuel to recover actinide and fission product elements, and then recycling the actinide elements in sodium-cooled fast reactors. Previous work has established the relationship between the processing efficiencies of spent LWR fuel, as represented by spent PWR fuel, and the potential increase in repository utilization for the resulting processing waste. The purpose of this current study is to determine a similar relationship for the waste from processing spent fast reactor fuel, and then to examine the wastes from the combination of LWRs and fast reactors as would be deployed with the GNEP approach.
Date: October 30, 2007
Creator: Bauer, T. H.; Morris, E. E. & Wigeland, R. A.
Partner: UNT Libraries Government Documents Department