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Research proposal for development of an electron stripper using a thin liquid lithium film for rare isotope accelerator.

Description: Hydrodynamic instability phenomena in a thin liquid lithium film, which has been proposed for the first stripper in the driver linac of Rare Isotope Accelerator (RIA), were discussed. Since it was considered that film instability could significantly impair the feasibility of the liquid lithium film stripper concept, potential issues and research tasks in the RIA project due to these instability phenomena were raised. In order to investigate these instability phenomena, a research proposal plan … more
Date: March 6, 2006
Creator: Momozaki, Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status report : guard containment CFD analysis.

Description: Under the auspices of the CEA Cadarache/ANL-US I-NERI project a comprehensive investigation has been made of improvements to the Gen-IV GFR safety case over that of the GCFR safety case twenty five years ago. In particular, it has been concluded and agreed upon [1] that the GFR safety approach for the passive removal of decay heat in a protected depressurization accident with total loss of electric power needs to be different from that taken for the HTRs. The HTR conduction cooldown to the vess… more
Date: March 3, 2006
Creator: Tzanos, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Report on Blending Strategies for Inert-Matrix Fuel Recycling in LWRs.

Description: Various recycle strategies have been proposed to manage the inventory of transuranics in commercial spent nuclear fuel (CSNF), with a particular goal of increasing the loading capacity of spent fuel and reprocessing wastes in the Yucca Mountain repository. Transuranic recycling in commercial LWRs can be seen as a viable means of slowing the accumulation of transuranics in the nationwide CSNF stockpile. Furthermore, this type of approach is an important first step in demonstrating the benefits o… more
Date: April 29, 2005
Creator: Hoffman, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Unified Monte Carlo Approach to Fast Neutron Cross Section Data Evaluation.

Description: A unified Monte Carlo (UMC) approach to fast neutron cross section data evaluation that incorporates both model-calculated and experimental information is described. The method is based on applications of Bayes Theorem and the Principle of Maximum Entropy as well as on fundamental definitions from probability theory. This report describes the formalism, discusses various practical considerations, and examines a few numerical examples in some detail.
Date: March 3, 2008
Creator: Smith, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fundamental Approach to TRIGA Steady-State Athermal-Hydraulic CHF Analysis.

Description: Methods are investigated for predicting the power at which critical heat flux (CHF) occurs in TRIGA reactors that rely on natural convection for primary flow. For a representative TRIGA reactor, two sets of functions are created. For the first set, the General Atomics STAT code and the more widely-used RELAP5-3D code are each employed to obtain reactor flow rate as a function of power. For the second set, the Bernath correlation, the 2006 Groeneveld table, the Hall and Mudawar outlet correlatio… more
Date: March 30, 2008
Creator: Feldman, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Alternate VHTR/HTE INterface for mitigating tritum.

Description: High temperature creep in structures at the interface between the nuclear plant and the hydrogen plant and the migration of tritium from the core through structures in the interface are two key challenges for the Very High Temperature Reactor (VHTR) coupled to the High Temperature Electrolysis (HTE) process. The severity of these challenges, however, can be reduced by lowering the temperature at which the interface operates. Preferably this should be accomplished in a way that does not reduce c… more
Date: February 25, 2009
Creator: Vilim, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly. Final CRADA Report.

Description: A direct numerical simulation capability for two-phase flows with heat transfer in complex geometries can considerably reduce the hardware development cycle, facilitate the optimization and reduce the costs of testing of various industrial facilities, such as nuclear power plants, steam generators, steam condensers, liquid cooling systems, heat exchangers, distillers, and boilers. Specifically, the phenomena occurring in a two-phase coolant flow in a BWR (Boiling Water Reactor) fuel assembly in… more
Date: October 13, 2009
Creator: Tentner, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluated Decay Data for 206TI.

Description: Evaluated decay data for the {sup 206}Tl nuclide are presented, including recommended values for the half-life, {beta}- and {gamma}-ray emission energies and probabilities. Data on X-ray radiations, Auger and conversion electron energies and emission probabilities are also tabulated. Carefully evaluated data for radioactive nuclides refer to complex nuclear level schemes and tables of numerical values, which quantify fundamental nuclear structure information such as level energies and quantum n… more
Date: January 3, 2007
Creator: Kondev, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary report on safety and licensing strategy support for the ABR prototype.

Description: Argonne National Laboratory is providing support to the US Department of Energy in the Global Nuclear Energy Partnership (GNEP) in certification of an advanced, sodium-cooled fast reactor. The reactor is to be constructed as a prototype for future commercial power reactors that will produce electricity while consuming actinides recovered from light water reactor spent fuel. This prototype reactor has been called the Advanced Burner Reactor, or ABR, and is now often referred to as the advanced r… more
Date: September 18, 2007
Creator: Cahalan, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Remark On: The Neutron Spherical Optical-Model Absorption.

Description: The energy-dependent behavior of the absorption term of the spherical neutron optical potential for doubly magic {sup 208}Pb and the neighboring {sup 209}Bi is examined. These considerations suggest a phenomenological model that results in an intuitively attractive energy dependence of the imaginary potential that provides a good description of the observed neutron cross sections and that is qualitatively consistent with theoretical concepts. At the same time it provides an alternative to some … more
Date: June 30, 2007
Creator: Smith, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The REBUS-MCNP Linkage.

Description: The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup. REBUS-PC models the complete fuel cycle including shuffling capability. REBUS-PC evolved using the neutronic capabilities of multi-group diffusion theory code DIF3D 9.0, but was extended to apply the continuous … more
Date: April 24, 2009
Creator: Stevens, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NGNP/HTE Full-Power Operation at Reduced High-Temperature Heat Exchanger Temperatures.

Description: Operation of the Next Generation Nuclear Plant (NGNP) with reduced reactor outlet temperature at full power was investigated for the High Temperature Electrolysis (HTE) hydrogen-production application. The foremost challenge for operation at design temperature is achieving an acceptably long service life for heat exchangers. In both the Intermediate Heat Exchanger (IHX) and the Process Heat Exchanger (PHX) (referred to collectively as high temperature heat exchangers) a pressure differential of… more
Date: March 12, 2009
Creator: VIlim, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uncertainty in Unprotected Loss-Of-Heat-Sink, Loss-Of-Flow, and Transient-Overpower Accidents.

Description: The sensitivities of various output parameters to selected input parameters in unprotected combined loss of heat-sink and loss-of-flow (ULOHS), loss-of-flow (ULOF), and transient-overpower (UTOP) accidents are explored in this report. This line of investigation was suggested by R. A. Wigeland. For an initial examination of potential sensitivities, the MATWS computer program has been compiled as part of a dynamic link library (DLL) so that uncertain input parameters can be sampled from their pro… more
Date: October 8, 2007
Creator: Morris, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Supply of purified Th228 for Ra224 generators. Final CRADA Report .

Description: CRADA was terminated when it was determined that the Russians could not perform the terms of the subcontract. It became apparent that the Russians would not be a reliable source of Th228, as a precursor in the decay chain which leads to Ra224. Their government policies will prohibit the export of Th228 in quantities needed for commercial cancer therapy.
Date: October 2, 2009
Creator: Ehst, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Letter to Eduard Smetanin, Dated March 2, 2007: Final Crada Report.

Description: The IPP/DOE program office has finished its evaluation of the alpha-emitting isotope work with Kurchatov Institute and IPPE, and they have made an important decision about the future of this work. IPP/DOE has directed us to re-program the work and add more funds, so the emphasis will be on production of Th228. By making this re-direction of the isotope work, IPPE will see several important benefits: (a) the payments will be made faster to IPPE by using the ISTC Agreement; (b) a larger amount of… more
Date: March 2, 2007
Creator: Ehst, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Melt spreading code assessment, modifications, and application to the EPR core catcher design.

Description: The Evolutionary Power Reactor (EPR) is under consideration by various utilities in the United States to provide base load electrical production, and as a result the design is undergoing a certification review by the U.S. Nuclear Regulatory Commission (NRC). The severe accident design philosophy for this reactor is based upon the fact that the projected power rating results in a narrow margin for in-vessel melt retention by external cooling of the reactor vessel. As a result, the design address… more
Date: March 30, 2009
Creator: Farmer, M. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production of ra225 Precursor for ac225/bi213 Generators. Final Crada Report.

Description: Russian subcontractors shipped two small deliveries of Ra225 to PNNL for evaluation. The activity was close to the requisite amount in the subcontract. The first labeled properly; the second did not. This showed that the Russians could supply Ra225 to the US; however they proved unable to meet future demands for larger amounts of activity. The US DOE attempts to get Ra225 from Russian should be terminated; the Russians, under Rosatom, are not interested in this business.
Date: October 2, 2009
Creator: Ehst, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Validation of the G-PASS code : status report.

Description: Validation is the process of determining whether the models in a computer code can describe the important phenomena in applications of interest. This report describes past work and proposed future work for validating the Gas Plant Analyzer and System Simulator (G-PASS) code. The G-PASS code was developed for simulating gas reactor and chemical plant system behavior during operational transients and upset events. Results are presented comparing code properties, individual component models, and i… more
Date: March 12, 2009
Creator: Vilim, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heat Exchanger Temperature Response for Duty-Cycle Transients in the NGNP/HTE.

Description: Control system studies were performed for the Next Generation Nuclear Plant (NGNP) interfaced to the High Temperature Electrolysis (HTE) plant. Temperature change and associated thermal stresses are important factors in determining plant lifetime. In the NGNP the design objective of a 40 year lifetime for the Intermediate Heat Exchanger (IHX) in particular is seen as a challenge. A control system was designed to minimize temperature changes in the IHX and more generally at all high-temperature … more
Date: March 12, 2009
Creator: Vilim, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Initial Assessment of the Operability of the Vhtr-Htse Nuclear Hydrogen Plant.

Description: The generation of hydrogen from nuclear power will need to compete on three fronts: production, operability, and safety to be viable in the energy marketplace of the future. This work addresses the operability of a coupled nuclear and hydrogen-generating plant while referring to other work for progress on production and safety. Operability is a measure of how well a plant can meet time-varying production demands while remaining within equipment limits. It can be characterized in terms of the ph… more
Date: November 1, 2007
Creator: Vilim, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim Progress Report on Safety and Licensing Strategy Support for the ABR Prototype.

Description: Argonne National Laboratory is providing support to the U.S. Department of Energy in the Global Nuclear Energy Partnership (GNEP) in certification of an advanced, sodium-cooled fast reactor. The reactor is to be constructed as a prototype for future commercial power reactors that will produce electricity while consuming actinides recovered from light water reactor spent fuel. This prototype reactor has been called the ABR, or Advanced Burner Reactor.
Date: June 26, 2007
Creator: Cahalan, J .E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluated Decay Data for {Sup 246}CM.

Description: The Nuclear Data and Measurement Series document results of studies in the field of microscopic nuclear data. The primary objective is the dissemination of information in the comprehensive form required for nuclear technology applications. This Series is devoted to: (a) measured microscopic nuclear parameters, (b) experimental techniques and facilities employed in measurements, (c) the analysis, correlation and interpretation of nuclear data, and (d) the compilation and evaluation of nuclear da… more
Date: February 26, 2007
Creator: Kondev, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uncertainty Quantification Approaches for Advanced Reactor Analyses.

Description: The original approach to nuclear reactor design or safety analyses was to make very conservative modeling assumptions so as to ensure meeting the required safety margins. Traditional regulation, as established by the U. S. Nuclear Regulatory Commission required conservatisms which have subsequently been shown to be excessive. The commission has therefore moved away from excessively conservative evaluations and has determined best-estimate calculations to be an acceptable alternative to conserva… more
Date: March 24, 2009
Creator: Briggs, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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