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open access

SCRAM: a fast computational model for the optical performance of point fucus solar central receiver systems

Description: Because of the complexities of heliostat shadowing and blocking calculations, computational models for the optical performance of point focus central receiver (PFCR) systems tend to be too slow for many important applications, such as optimization studies based on performance with realistic weather data. In this paper, a mathematical approximation procedure, designated Sandia Central Receiver Approximation Model (SCRAM) will be described. Rather than simulating the system components from first … more
Date: April 1, 1980
Creator: Bergeron, K. D. & Chiang, C. J.
Partner: UNT Libraries Government Documents Department
open access

Cleaning strategies for parabolic-trough solar-collector fields; guidelines for decisions

Description: This report is intended to assist the owner or operator of a parabolic trough solar collector system to decide on a cleaning strategy (equipment, materials, procedures, and schedules). The guidelines are based on information obtained in past research studies, as well as interviews with vendors and users of cleaning and water treatment equipment. The basic procedure recommended utilizes high pressure portable washing equipment. However, since the cleaning problem is so site-specific, no single, … more
Date: June 1, 1981
Creator: Bergeron, K. D. & Freese, J. M.
Partner: UNT Libraries Government Documents Department
open access

Line-focus solar thermal energy technology development. FY 79 annual report for Department 4720

Description: The primary role of the Solar Energy Projects Department II (4720) is the development, evaluation, and testing of line-focus solar thermal technology. This report of FY 79 progress and accomplishments is divided into two parts: (1) Component and Subsystem Development including the design and analysis of collector modules, their components, and associated materials and processes, and (2) Systems and Applications Development, involving larger configurations of solar thermal line-focus systems. Th… more
Date: April 1, 1980
Creator: Bergeron, K D; Champion, R L & Hunke, R W
Partner: UNT Libraries Government Documents Department
open access

CONTAIN 2.0 code release and the transition to licensing

Description: CONTAIN is a reactor accident simulation code developed by Sandia National Laboratories under US Nuclear Regulatory Commission (USNRC) sponsorship to provide integrated analysis of containment phenomena, including those related to nuclear reactor containment loads and radiological source terms. The recently released CONTAIN 2.0 code version represents a significant advance in CONTAIN modeling capabilities over the last major code release (CONTAIN 1.12V). The new modeling capabilities are discus… more
Date: October 1, 1997
Creator: Murata, K. K.; Griffith, R. O.; Bergeron, K. D. & Tills, J.
Partner: UNT Libraries Government Documents Department
open access

SCOPE safety-controls optimization by performance evaluation: A systematic approach for safety-related decisions at the Hanford Tank Remediation System. Phase 1, final report

Description: The Department of Energy`s Hanford Tank Waste Remediation system poses a significant challenge for hazard management because of the uncertainty that surrounds many of the variables that must be considered in decisions on safety and control strategies. As a result, site managers must often operate under excessively conservative and expensive assumptions. This report describes a systematic approach to quantifying the uncertainties surrounding the critical parameters in control decisions (e.g., co… more
Date: December 1, 1996
Creator: Bergeron, K. D.; Williams, D. C.; Slezak, S. E. & Young, M. L.
Partner: UNT Libraries Government Documents Department
open access

A direct comparison of MELCOR 1.8.3 and MAAP4 results for several PWR & BWR accident sequences

Description: This paper presents a comparison of calculations of severe accident progression for several postulated accident sequences for representative Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) nuclear power plants performed with the MELCOR 1.8.3 and the MAAP4 computer codes. The PWR system examined in this study is a 1100 MWe system similar in design to a Westinghouse 3-loop plant with a large dry containment; the BWR is a 1100 MWe system similar in design to General Electric BWR/… more
Date: August 1, 1996
Creator: Leonard, M.T.; Ashbaugh, S.G.; Cole, R.K.; Bergeron, K.D. & Nagashima, K.
Partner: UNT Libraries Government Documents Department
open access

Large-scale testing of in-vessel debris cooling through external flooding of the reactor pressure vessel in the CYBL facility

Description: The possibility of achieving in-vessel core retention by flooding the reactor cavity, or the ``flooded cavity``, is an accident management concept currently under consideration for advanced light water reactors (ALWR), as well as for existing light water reactors (LWR). The CYBL (CYlindrical BoiLing) facility is a facility specifically designed to perform large-scale confirmatory testing of the flooded cavity concept. CYBL has a tank-within-a-tank design; the inner 3.7 m diameter tank simulates… more
Date: April 1, 1994
Creator: Chu, T. Y.; Bentz, J. H.; Bergeron, K. D.; Slezak, S. E. & Simpson, R. B.
Partner: UNT Libraries Government Documents Department
open access

EnviroTRADE: An International Environmental Restoration and Waste Management Information System

Description: The US Department of Energy (DOE) has collected, and will continue to collect, large amounts of information on its environmental waste sites and associated technology development efforts. This information is being gathered in a variety of formats for various purposes. Integration and delivery of this information WW benefit decision makers, waste site managers, technology developers, regulators, and the private sector. No computer system currently exists that acts as an easy-to-use computer umbr… more
Date: December 31, 1993
Creator: Johnson, S. W.; Harlan, C. P.; Harrington, M. W.; Bergeron, K. D. & Rehorn, A. S.
Partner: UNT Libraries Government Documents Department
open access

The probability of containment failure by direct containment heating in surry

Description: In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure pressure. A failure in the bottom head of the RPV, followed by melt expulsion and blowdown of the RCS, will entrain molten core debris in the high-velocity steam blowdown gas. This chain of events is called a high-pressure melt ejection (HPME). … more
Date: May 1995
Creator: Pilch, M. M.; Allen, M. D.; Bergeron, K. D.; Tadios, E. L.; Stamps, D. W.; Spencer, B. W. et al.
Partner: UNT Libraries Government Documents Department
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