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in subjects: "210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled"  
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Support of nuclear engineering education and research at the University of Michigan

Description: This report describes progress on four different projects in the fission reactor area that have been supported by the grant during the past year. These projects are: Accelerator transmutation of nuclear waste (Steve Pearson); neutronic analysis of the Ford Nuclear Reactor (Brent Renkema); developing Monte Carlo benchmarks for commercial LWR configurations (Jie Du); Monte Carlo depletion capability for massively parallel processors (Amit Majumdar); these tasks are briefly described and progress … more
Date: March 1, 1993
Creator: Martin, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A simplified model of aerosol removal by containment sprays

Description: Spray systems in nuclear reactor containments are described. The scrubbing of aerosols from containment atmospheres by spray droplets is discussed. Uncertainties are identified in the prediction of spray performance when the sprays are used as a means for decontaminating containment atmospheres. A mechanistic model based on current knowledge of the physical phenomena involved in spray performance is developed. With this model, a quantitative uncertainty analysis of spray performance is conducte… more
Date: June 1, 1993
Creator: Powers, D.A. (Sandia National Labs., Albuquerque, NM (United States)) & Burson, S.B. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Burnup credit validation of SCALE-4 using light water reactor criticals

Description: The ANSI/ANS 8.1 criticality safety standard recommends validation and benchmarking of the calculational methods used in evaluating criticality safety limits for away-from-reactor applications. The lack of critical experiments with burned light-water-reactor (LWR) fuel in racks or in casks necessitates the validation of burnup credit methods by comparison to LWR core criticals. These are relevant benchmarks because they test a methodology's ability to predict spent fuel isotopics and to evaluat… more
Date: January 1, 1993
Creator: Bowman, S. M.; Hermann, O. W. (Oak Ridge National Lab., TN (United States)) & Brady, M. C. (Sandia National Labs., Albuquerque, NM (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

SCDAP/RELAP5 independent peer review

Description: The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light-water-reactor coolant systems during severe accidents. The newest version of the code is SCDAP/RELAP5/MOD3. The US Nuclear Regulatory Commission (NRC) decided that there was a need for a broad technical review of the code by recognized experts to determine overall technical adequacy, even though the code is still under development. For this purpose, an eight-member SCDAP/RELAP5 Peer Review Committee was org… more
Date: January 1, 1993
Creator: Corradini, M.L. (Wisconsin Univ., Madison, WI (United States). Dept. of Nuclear Engineering); Dhir, V.K. (Dhir, (V.K.) Santa Monica, CA (United States)); Haste, T.J. (AEA Technology, Winfrith (United Kingdom)); Heames, T.J. (Science Applications, Inc., Albuquerque, NM (United States)); Jenks, R.P. (Los Alamos National Lab., NM (United States)) & Kelly, J.E. (Sandia National Labs., Albuquerque, NM
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A computer program for estimating decommissioning costs for light water reactors

Description: This report discusses a desk-top computer program has been developed for estimating the costs, waste volumes, and occupational radiation exposures associated with decommissioning light-water reactor power stations. Cost categories and cost algorithms used in the program are discussed and a brief description of the user interface is given.
Date: February 1, 1993
Creator: Bierschbach, M.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Feasibility study for improved steady-state initialization algorithms for the RELAP5 computer code

Description: A design for a new steady-state initialization method is presented that represents an improvement over the current method used in RELAP5. Current initialization methods for RELAP5 solve the transient fluidflow balance equations simulating a transient to achieve steady-state conditions. Because the transient solution is used, the initial conditions may change from the desired values requiring the use of controllers and long transient running times to obtain steady-state conditions for system pro… more
Date: April 1, 1993
Creator: Paulsen, M.P.; Peterson, C.E. & Katsma, K.R. (Computer Simulation and Analysis, Inc., Idaho Falls, ID (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ex-vessel melt-coolant interactions in deep water pool: Studies and accident management for Swedish BWRs

Description: In Swedish BWRs having an annular suppression pool, the lower drywell beneath the reactor vessel is flooded with water to mitigate against the effects of melt release into the drywell during a severe accident. The THIRMAL code has been used to analyze the effectiveness of the water pool to protect lower drywell penetrations by fragmenting and quenching the melt as it relocates downward through the water. Experiments have also been performed to investigate the benefits of adding surfactants to t… more
Date: January 1, 1993
Creator: Sienicki, J. J.; Chu, C. C.; Spencer, B. W. (Argonne National Lab., IL (United States)); Frid, W. (Swedish Nuclear Power Inspectorate, Stockholm (Sweden)) & Loewenhielm, G. (Vattenfall AB, Vaellingby (Sweden))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Mechanistic issues for modeling radiation-induced segregation

Description: Model calculations of radiation-induced chromium depletion and radiation-induced nickel enrichment at grain boundaries are compared to measured depletions and enrichments. The model is calibrated to fit chromium depletion in commercial purity 304 stainless steel irradiated in boiling water reactor (BWR) environments. Predicted chromium depletion profiles and the dose dependence of chromium concentration at grain boundaries are in accord with measured trends. Evaluation of chromium and nickel pr… more
Date: March 1, 1993
Creator: Simonen, E. P. & Bruemmer, S. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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