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Investigation of nuclide importance to functional requirements related to transport and long-term storage of LWR spent fuel

Description: This study investigates the relative importances of the various actinide, fission-product, and light-element isotopes associated with LWR spent fuel with respect to five analysis areas: criticality safety (absorption fractions), shielding (dose rate fractions), curies (fractional curies levels), decay heat (fraction of total watts), and radiological toxicity (fraction of potential committed effective dose equivalent). These rankings are presented for up to six different burnup/enrichment scenar… more
Date: June 1, 1995
Creator: Broadhead, B. L.; DeHart, M. D.; Ryman, J. C.; Tang, J. S. & Parks, C. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Assessment of the IVA3 code for multifield flow simulation. Formal report

Description: This report presents an assessment of the IVA3 computer code for multifield flow simulation, as applied to the premixing phase of a hypothetical steam explosion in a water-cooled power reactor. The first section of this report reviews the derivation of the basic partial differential equations of multifield modeling, with reference to standard practices in the multiphase flow literature. Basic underlying assumptions and approximations are highlighted, and comparison is made between IVA3 and othe… more
Date: July 1, 1995
Creator: Stewart, H. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heavy-Section Steel Irradiation Program. Volume 5, No. 2, Progress report, April 1994--September 1994.

Description: The Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being exami… more
Date: July 1, 1995
Creator: Corwin, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials

Description: The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effe… more
Date: July 1, 1995
Creator: Nanstad, R. K.; Corwin, W. R.; Alexander, D. J.; Haggag, F. M.; Iskander, S. K.; McCabe, D. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of LWR environments on fatigue life of carbon and low-alloy steels

Description: SME Boiler and Pressure Vessel Code provides construction of nuclear power plant components. Figure I-90 Appendix I to Section III of the Code specifies fatigue design curves for structural materials. While effects of environments are not explicitly addressed by the design curves, test data suggest that the Code fatigue curves may not always be adequate in coolant environments. This paper reports the results of recent fatigue tests that examine the effects of steel type, strain rate, dissolved … more
Date: March 1, 1995
Creator: Chopra, O. K. & Shack, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Developing and testing technologies for future remote monitoring systems

Description: Remote monitoring systems presently operating in facilities in a number of countries around the world are providing valuable information on the installation and operation of such systems. Results indicate they are performing reliably. While the technology for remote monitoring exists today, it may be some time before numerous constraints on implementation can be resolved. However, the constraints should not prevent the designing of systems that can be used for remote monitoring. Selection of th… more
Date: October 1, 1995
Creator: Johnson, C. S. & Dupree, S. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Implementation of safeguards and security for fissile materials disposition reactor alternative facilities

Description: A number of different disposition alternatives are being considered and include facilities which provide for long-ten-n and interim storage, convert and stabilize fissile materials for other disposition alternatives, immobilize fissile material in glass and/or ceramic material, fabricate fissile material into mixed oxide (MOX) fuel for reactors, use reactor based technologies to convert material into spent fuel, and dispose of fissile material using a number of geologic alternatives. Particular… more
Date: October 1, 1995
Creator: Jaeger, C.D.; Duggan, R.A. & Tolk, K.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Simulation-based diagnostics and control for nuclear power plants. Final report, April 15, 1992--April 14, 1995

Description: The objective of the project was to develop and test a simulation-based diagnostics and control guidance system that can be used to diagnose and manage off-normal transient events in nuclear power plants. The research has focused on developing two diagnostic approaches suitable for detection and identification of faults involving multiple components, subject to uncertainties in system modeling and observations. The first approach is based on a fuzzy logic framework that can diagnose binary fail… more
Date: July 1, 1995
Creator: Lee, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CONTAIN independent peer review

Description: The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code`s targeted applications include support for containment-related experimental programs, light wat… more
Date: January 1, 1995
Creator: Boyack, B. E.; Corradini, M. L.; Denning, R. S.; Khatib-Rahbar, M.; Loyalka, S. K. & Smith, P. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Simulation of NPLWR environment in the ATR Loop-1 test

Description: An irradiation test of high-temperature, light water reactor, tritium targets was conducted in the ATR that simulated the neutronic, thermal-hydraulic and chemical conditions in an NPLWR for the production of tritium. Requirements for water chemistry, temperature, pressure, spectrum and fluence were met for essentially all of the 217 days of irradiation. The loop test facilities in the ATR provide excellent capabilities for conducting long term, well controlled, in situ tests to simulate degrad… more
Date: January 1, 1995
Creator: Hollenberg, G. W.; McKee, R. S.; O`Connor, R. R.; Thielges, J. R. & Spencer, D. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Core damage frequency observations and insights of LWRs based on the IPEs

Description: Seventy-eight plants are expected to submit Individual Plant Examinations (IPEs) for severe accident vulnerabilities to the U.S. Nuclear Regulatory Commission (NRC). The majority of the plants have elected to perform full Level 1 probabilistic risk assessments (PRAs) to meet the intent of the IPES. Because of this, it is possible to compare the results from the IPE submittals to determine general observations and {open_quotes}lessons learned{close_quotes} from the IPES. The IPE Insights Program… more
Date: January 1, 1995
Creator: Dingman, S. E.; Camp, A. L.; Drouin, M. T.; Kolaczkowski, A.; Darby, J.; LaChance, J. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

An Innovative Fuel Design Concept for Improved Light Water Reactor Performance and Safety. Final Technical Report

Description: Light water reactor (LWR) fuel performance is limited by thermal and mechanical constraints associated with the design, fabrication, and operation of fuel in a nuclear reactor. The purpose of this research was to explore a technique for extending fuel performance by thermally bonding LWR fuel with a non-alkaline liquid metal alloy. Current LWR fuel rod designs consist of enriched uranium oxide (UO{sub 2}) fuel pellets enclosed in a zirconium alloy cylindrical clad. The space between the pellets… more
Date: July 1, 1995
Creator: Tulenko, J. S. & Connell, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SCDAP/RELAP5/MOD 3.1 code manual: Interface theory. Volume 1

Description: The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, core, fission product released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of off-site power, loss of feedwater, and loss of flow. A generic modeling approach is … more
Date: June 1, 1995
Creator: Coryell, E. W.; Allison, C. M. & Berna, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MELCOR computer code manuals

Description: MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. Thes… more
Date: March 1, 1995
Creator: Summers, R. M.; Cole, R. K., Jr.; Smith, R. C.; Stuart, D. S.; Thompson, S. L.; Hodge, S. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of coupled SCALE4.2/GTRAN2 computational capability for advanced MOX fueled assembly designs

Description: An advanced assembly code system that can efficiently and accurately analyze various designs (current and advanced) proposed for plutonium disposition is being developed by {open_quotes}marrying{close_quotes} two existing state-of-the-art methodologies-GTRAN2 and SCALE 4.2. The resulting code system, GT-SCALE, posses several unique characteristics: exact 2D representation of a complete fuel assembly, while preserving the heterogeniety of each of its pin cells; flexibility in the energy group st… more
Date: May 1, 1995
Creator: Vujic, J.; Greenspan, E.; Slater, Postma, T.; Casher, G.; Soares, I. & Leal, L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Short cracks in piping and piping welds. Seventh program report, March 1993-December 1994. Volume 4, Number 1

Description: This is the seventh progress report of the U.S. Nuclear Regulatory Commission`s research program entitled {open_quotes}Short Cracks in Piping and Piping Welds{close_quotes}. The program objective is to verify and improve fracture analyses for circumferentially cracked large-diameter nuclear piping with crack sizes typically used in leak-before-break (LBB) analyses and in-service flaw evaluations. All work in the eight technical tasks have been completed. Ten topical reports are scheduled to be … more
Date: April 1995
Creator: Wilkowski, G. M.; Ghadiali, N.; Rudland, D.; Krishnaswamy, P.; Rahman, S. & Scott, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation-assisted stress corrosion cracking considerations at temperatures below 288{degree}C

Description: Irradiation-assisted stress corrosion cracking (IASCC) occurs above a critical neutron fluence in light-water reactor (LWR) water environments at 288 C, but very little information exists to indicate susceptibility as temperatures are reduced. Potential low-temperature behavior is assessed based on the temperature dependencies of intergranular (IG) SCC in the absence of irradiation, radiation-induced segregation (RIS) at grain boundaries and micromechanical deformation mechanisms. IGSCC of sens… more
Date: March 1, 1995
Creator: Simonen, E. P.; Jones, R. H. & Bruemmer, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress in MELCOR development and assessment

Description: MELCOR models the progression of severe accidents in light water reactor nuclear power plants. Recent efforts in MELCOR development to incorporate CORCON-Mod3 models for core-concrete interactions, new models for advanced reactors, and improvements to several other existing models have resulted in release of MELCOR 1.8.3. In addition, continuing efforts to expand the code assessment database have filled in many of the gaps in phenomenological coverage. Efforts are now under way to develop model… more
Date: April 1, 1995
Creator: Summers, R. M.; Kmetyk, L. N.; Cole, R. K., Jr.; Smith, R. C.; Elsbernd, A. E.; Stuart, D. S. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

IPE results as compared with NUREG-1150

Description: In 1990, the NRC published NUREG-1150 which assessed the risks for five U.S. nuclear power plants. This paper provides a comparison of the results and perspectives obtained from the NUREG-1150 study to those obtained form the Individual Plant Examination (IPE) program. Specifically, results and perspectives on core damage frequency and containment performance are compared.
Date: December 31, 1995
Creator: Pratt, W.T.; Lehner, J.; Camp, A. & Chow, E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A compilation of reports of the Advisory Committee on Reactor Safeguards. 1994 annual. Volume 16

Description: This compilation contains 30 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1994. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the U.S. Library of Congress. The reports are categorized by the most appropriate generic subject area and by chronological order within subject area.
Date: April 1, 1995
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Study on hydrodynamically induced dryout and post dryout important to heavy water reactors

Description: Recently, the safety of low pressure liquid cooled nuclear reactors has become a very important issue with reference to the operation of the heavy water reactors at Savannah River Plant. Under accident conditions such as loss-of-flow or loss-of-coolant, these reactors typically encounter unstable two-phase flow which may lead to the occurrence of dryout and subsequent fuel failure. An analytical study using the one-dimensional drift flux model was carried out to investigate the two-phase flow i… more
Date: January 1, 1995
Creator: Ishii, M.; Revankar, S.T.; Nair, S.; Lele, S.; Eberle, C.S. & Babelli, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A two-dimensional, semi-analytic expansion method for nodal calculations

Description: Most modern nodal methods used today are based upon the transverse integration procedure in which the multi-dimensional flux shape is integrated over the transverse directions in order to produce a set of coupled one-dimensional flux shapes. The one-dimensional flux shapes are then solved either analytically or by representing the flux shape by a finite polynomial expansion. While these methods have been verified for most light-water reactor applications, they have been found to have difficulty… more
Date: August 1, 1995
Creator: Palmtag, S.P.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

Heavy-section steel irradiation program. Semiannual progress report, September 1993--March 1994

Description: Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only component in the primary pressure boundary for which, if it should rupture, the engineering safety systems cannot assure protection from core damage. It is therefore imperative to understand and be able to predict the capabilities and limitations of the int… more
Date: April 1995
Creator: Corwin, W.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrogen detonation and detonation transition data from the High-Temperature Combustion Facility

Description: The BNL High-Temperature Combustion Facility (HTCF) is an experimental research tool capable of investigating the effects of initial thermodynamic state on the high-speed combustion characteristic of reactive gas mixtures. The overall experimental program has been designed to provide data to help characterize the influence of elevated gas-mixture temperature (and pressure) on the inherent sensitivity of hydrogen-air-steam mixtures to undergo detonation, on the potential for flames accelerating … more
Date: December 31, 1995
Creator: Ciccarelli, G.; Boccio, J.L.; Ginsberg, T.; Finfrock, C.; Gerlach, L.; Tagawa, H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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