2005 Update for Implementing Best Available Technology per DOE Order 5400.5

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

Analysis of DOE Spent Nuclear Fuels for Repository Disposal

Abstract -U.S. Department of Energy (DOE) spent nuclear fuel (SNF) consists of hundreds of different fuel types in various conditions . In order to analyze and model the DOE SNF for its suitability for repository disposal, several generalizations and simplifications were necessary. This paper describes the methodology used to arrive at a suitable DOE SNF surrogate and summarizes the proposed analysis of this DOE SNF surrogate for its appropriateness as a representative SNF. I. INTRODUCTION fuel parameters. These parameters were determined based on properties that affect three major areas of licensing During the last four decades, the U.S. Department of analysis: criticality, design basis events, and performance Energy (DOE) and its preceding agencies generated assessment. The parameters used to group the DOE SNFs approximately 250 varieties of spent nuclear fuel (SNF) are shown i

ZPPR-20 Phase D : A Cylindrical Assembly of Polyethylene Moderated U Metal Reflected by Beryllium Oxide and Polyethylene.

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 reactor vessel was a rhenium baffle which would act as a neutron curtain in the event of water immersion. A fission gas plenum and coolant inlet plenum were located axially forward of the core. Some material substitutions had to be made in mocking up the SP-100 design. The ZPPR-20 critical assemblies were fueled by 93% enriched uranium metal because uranium nitride, which was the SP-100 fuel type, was not available. ZPPR Assembly 20D was designed to simulate a water immersion accident. The water was simulated by polyethylene (CH{sub 2}), which contains a similar amount of hydrogen and has a similar density. A very accurate transformation to a simplified model is needed to make any of the ZPPR assemblies a practical criticality-safety benchmark. There is simply too much geometric detail in an exact model of a ZPPR assembly, particularly as complicated an assembly as ZPPR-20D. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must do this without increasing the total uncertainty far beyond that of the original experiment. Such a transformation will be described in a later section. First, Assembly 20D was modeled in full detail--every plate, drawer, matrix tube, and air gap was modeled explicitly. Then the regionwise compositions and volumes from this model were converted to an RZ model. ZPPR Assembly 20D has been determined to be an acceptable criticality-safety benchmark experiment

Value Added Products from Hemicellulose Utilization in Dry Mill Ethanol Plants

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

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

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

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

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

Generalising KAT to Verify Weighted Computations

Kleene algebra with tests (KAT) was introduced as an algebraic structure to model and reason about classic imperative programs, i.e. sequences of discrete transitions guarded by Boolean tests. This paper introduces two generalisations of this structure able to express programs as weighted transitions and tests with outcomes in non necessarily bivalent truth spaces: graded Kleene algebra with tests (GKAT) and a variant where tests are also idempotent (I-GKAT). In this context, and in analogy to Kozen's encoding of Propositional Hoare Logic (PHL) in KAT we discuss the encoding of a graded PHL in I-GKAT and of its while-free fragment in GKAT. Moreover, to establish semantics for these structures four new algebras are defined: FSET(T), FREL(K,T) and FLANG(K,T) over complete residuated lattices K and T, and M (n, A) over a GKAT or I-GKAT A. As a final exercise, the paper discusses some program equivalence proofs in a graded context