11 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Safety 220900* -- Nuclear Reactor Technology-- Reactor Safety"  
Results: 1 - 11
open access

COBRA-WC: a version of COBRA for single-phase multiassembly thermal hydraulic transient analysis. [LMFBR]

Description: The objective of this report is to provide the user of the COBRA-WC (Whole Core) code a basic understanding of the code operation and capabilities. Included in this manual are the equations solved and the assumptions made in their derivations, a general description of the code capabilities, an explanation of the numerical algorithms used to solve the equations, and input instructions for using the code. Also, the auxiliary programs GEOM and SPECSET are described and input instructions for each … more
Date: July 1, 1980
Creator: George, T. L.; Basehore, K. L.; Wheeler, C. L.; Prather, W. A. & Masterson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Substitute safety rods: Physics design and NTG calibration

Description: Under certain assumed accident conditions, an SRS reactor may loose most of its bulk moderator while maintaining flow to fuel assemblies. If this occurs immediately after operation at power, components normally dependent on convective heat transfer to the moderator will heat up with the possibility of melting that component. One component at risk is the safety rod. Tests have shown that the current cadmium safety rod, which contains aluminum as well as cadmium, can fail at temperatures only sli… more
Date: July 1, 1991
Creator: Baumann, N.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R]

Description: The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 pa… more
Date: July 1, 1985
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fast reactor safety: proceedings of the international topical meeting. Volume 1

Description: The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 pa… more
Date: July 1, 1985
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Response of secondary containment to presence of sodium and hydrogen

Description: As part of an effort to demonstrate that the risk to the public from extremely low probability events in liquid metal fast breeder reactors is bound within an acceptable envelope, containment pressurization by sodium and hydrogen was evaluated. Temperature and pressure histories are presented for typical sodium spray and pool fires and sodium vapor reactions. A review of mechanisms for hydrogen generation and recombination as well as limit for flammability and autocatalytic recombination is pro… more
Date: July 1, 1979
Creator: Gleikler, E.L. & Huang, T.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Safety and licensing of MHTGR (Modular High Temperature Gas Cooled Reactor)

Description: The Modular High Temperature Gas Cooled Reactor (MHTGR) design meets stringent top-level regulatory and user safety requirements that require that the normal and off-normal operation of the plant not disturb the public's day-to-day activities. Quantitative, top-level regulatory criteria have been specified from US NRC and EPA sources to guide the design. The user/utility group has further specified that these criteria be met at the plant boundary. The focus of the safety approach has then been … more
Date: July 1, 1987
Creator: Silady, F.A.; Millunzi, A.C.; Kelley, A.P. Jr. & Cunliffe, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Modeling of fission product release from HTR (high temperature reactor) fuel for risk analyses

Description: The US and FRG have developed methodologies to determine the performance of and fission product release from TRISO-coated fuel particles under postulated accident conditions. The paper presents a qualitative and quantitative comparison of US and FRG models. The models are those used by General Atomics (GA) and by the German Nuclear Research Center at Juelich (KFA/ISF). A benchmark calculation was performed for fuel temperatures predicted for the US Department of Energy sponsored Modular High Te… more
Date: July 1, 1989
Creator: Bolin, J.; Verfondern, K.; Dunn, T. & Kania, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Countercurrent flow-limiting characteristics of a Savannah River Plant control rod septifoil

Description: Experiments were performed at the Idaho National Engineering Laboratory to investigate the counter-current flow limiting characteristics of a Savannah River Plant control rod septifoil assembly. These experiments were unheated, using air and water as the working fluids. Results are presented in terms of the Wallis flooding correlation for several different control rod configurations. Flooding was observed to occur in the vicinity of the inlet slots/holes of the septifoil, rather than within the… more
Date: July 1, 1992
Creator: Anderson, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LMFBR safety. 6. Review of current issues and bibliography of literature (1977)

Description: This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development. Selected bibliographic information on LMFBRs relative to the development and safety of the breeder reactor is presented for the year 1977. The bibliography consists of approximately 198 abstracts covering research and development, operating experience, and design practices. Keyword, author, and permuted-title indexes are included for completeness.
Date: July 13, 1978
Creator: Buchanan, J.R. & Keilholtz, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A simplified model for calculating early offsite consequences from nuclear reactor accidents

Description: A personal computer-based model, SMART, has been developed that uses an integral approach for calculating early offsite consequences from nuclear reactor accidents. The solution procedure uses simplified meteorology and involves direct analytic integration of air concentration equations over time and position. This is different from the discretization approach currently used in the CRAC2 and MACCS codes. The SMART code is fast-running, thereby providing a valuable tool for sensitivity and uncer… more
Date: July 1, 1988
Creator: Madni, I.K.; Cazzoli, E.G. & Khatib-Rahbar, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safety Requirements, Facility User Needs, and Reactor Concepts for a New Broad Application Test Reactor

Description: This report describes the EG G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definit… more
Date: July 1, 1992
Creator: Ryskamp, J. M., (ed.); Liebenthal, J. L.; Denison, A. B. & Fletcher, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen