53 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Breeder Reactors"  
Results: 1 - 24 next
open access

Operating and test experience of EBR-II

Description: EBR-2 has operated for 27 years, the longest for any Liquid Metal Reactor (LMR) power plant. During that time, much has been learned about successful LMR operation and design. The basic lesson is that conversatism in design can pay significant dividends in operating reliability. Furthermore, such conservatism need not mean high cost. The EBR-2 system emphasizes simplicity, minimizing the number of valves in the heat transport system, for example, and simplifying the primary heat-transport-syste… more
Date: January 1, 1991
Creator: Sackett, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

PRISM reactor system design and analysis of postulated unscrammed events

Description: Key safety characteristics of the PRISM reactor system include the passive reactor shutdown characteristics and the passive shutdown heat removal system, RVACS. While these characteristics are simple in principle, the physical processes are fairly complex, particularly for the passive reactor shutdown. It has been possible to adapt independent safety analysis codes originally developed for the Clinch River Breeder Reactor review, although some limitations remain. In this paper, the analyses of … more
Date: January 1, 1991
Creator: Van Tuyle, G.J.; Slovik, G.C. (Brookhaven National Lab., Upton, NY (United States)); Rosztoczy, Z. & Lane, J. (Nuclear Regulatory Commission, Washington, DC (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Code validation with EBR-II test data

Description: An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experiment Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental programs in EBR-2, and are also valuable tools for the analysis of innovative reactor des… more
Date: January 1, 1991
Creator: Herzog, J.P.; Chang, L.K.; Dean, E.M.; Feldman, E.E.; Hill, D.J.; Mohr, D. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Prism reactor system design and analysis of postulated unscrammed events

Description: Key safety characteristics of the PRISM reactor system include the passive reactor shutdown characteristic and the passive shutdown heat removal system, RVACS. While these characteristics are simple in principle, the physical processes are fairly complex, particularly for the passive reactor shutdown. It has been possible to adapt independent safety analysis codes originally developed for the Clinch River Breeder Reactor review, although some limitations remain. In this paper, the analyses of p… more
Date: August 1, 1991
Creator: Van Tuyle, G.J. & Slovik, G.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Comparative sodium void effects for different advanced liquid metal reactor fuel and core designs

Description: An analysis of metal-, oxide, and nitride-fueled advanced liquid metal reactor cores was performed to investigate the calculated differences in sodium void reactivity, and to determine the relationship between sodium void reactivity and burnup reactivity swing using the three fuel types. The results of this analysis indicate that nitride fuel has the least positive sodium void reactivity for any given burnup reactivity swing. Thus, it appears that a good design compromise between transient over… more
Date: July 1, 1991
Creator: Dobbin, K. D.; Kessler, S. F.; Nelson, J. V.; Gedeon, S. R. & Omberg, R. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

Description: Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides int… more
Date: April 1, 1991
Creator: Koch, M. & Kazimi, M.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of RBCB testing of LMR oxide fuel in EBR-II

Description: The status is given of the the American-Japanese collaborative program in Experimental Breeder Reactor 2 to determine the run-beyond-cladding-breach performance of (UPu)O{sub 2} fuel pins for liquid-metal cooled reactors. Phase 1 of the collaboration involved eighteen irradiation tests over 1981--86 with 5.84-mm pins in 316 or D9 stainless steel. Emphasis in Phase 2 tests from 1989 onwards is with larger diameter (7.5mm) pins in advanced claddings. Results include delayed neutron and fission ga… more
Date: January 1, 1991
Creator: Strain, R.V.; Bottcher, J.H.; Gross, K.C.; Lambert, J.D.B. (Argonne National Lab., IL (United States)); Ukai, S.; Nomura, S. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Advancing liquid metal reactor technology with nitride fuels

Description: A review of the use of nitride fuels in liquid metal fast reactors is presented. Past studies indicate that both uranium nitride and uranium/plutonium nitride possess characteristics that may offer enhanced performance, particularly in the area of passive safety. To further quantify these effects, the analysis of a mixed-nitride fuel system utilizing the geometry and power level of the US Advanced Liquid Metal Reactor as a reference is described. 18 refs., 2 figs., 2 tabs.
Date: August 1, 1991
Creator: Lyon, W.F.; Baker, R.B.; Leggett, R.D. (Westinghouse Hanford Co., Richland, WA (United States)) & Matthews, R.B. (Los Alamos National Lab., NM (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

On reactor type comparisons for the next generation of reactors

Description: In this paper, we present a broad comparison of studies for a selected set of parameters for different nuclear reactor types including the next generation. This serves as an overview of key parameters which provide a semi-quantitative decision basis for selecting nuclear strategies. Out of a number of advanced reactor designs of the LWR type, gas cooled type, and FBR type, currently on the drawing board, the Advanced Light Water Reactors (ALWR) seem to have some edge over other types of the nex… more
Date: August 22, 1991
Creator: Alesso, H.P. & Majumdar, K.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Reliability of fast reactor mixed-oxide fuel during operational transients

Description: Results are presented from the cooperative DOE and PNC Phase 1 and 2 operational transient testing programs conducted in the EBR-2 reactor. The program includes second (D9 and PNC 316 cladding) and third (FSM, AST and ODS cladding) generation mixed-oxide fuel pins. The irradiation tests include duty cycle operation and extended overpower tests. the results demonstrate the capability of second generation fuel pins to survive a wide range of duty cycle and extended overpower events. 15 refs., 9 f… more
Date: July 1, 1991
Creator: Boltax, A.; Neimark, L.A.; Tsai, Hanchung (Argonne National Lab., IL (United States)); Katsuragawa, M. & Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fabrication of oxide dispersion strengthened ferritic clad fuel pins

Description: A resistance butt welding procedure was developed and qualified for joining ferritic fuel pin cladding to end caps. The cladding are INCO MA957 and PNC ODS lots 63DSA and 1DK1, ferritic stainless steels strengthened by oxide dispersion, while the end caps are HT9 a martensitic stainless steel. With adequate parameter control the weld is formed without a residual melt phase and its strength approaches that of the cladding. This welding process required a new design for fuel pin end cap and weld … more
Date: January 1, 1991
Creator: Zirker, L.R. (Argonne National Lab., Idaho Falls, ID (United States)); Bottcher, J.H. (Argonne National Lab., IL (United States)); Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Oarai (Japan)); Tsai, C.L. (Ohio State Univ., Columbus, OH (United States). Dept. of Welding Engineering) & Hamilton, M.L. (Pacific Northwest Lab., Richland, WA (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Status of Rankine-cycle technology for space nuclear power applications

Description: A substantial effort on the development of the liquid metal Rankine cycle space nuclear power system was carried out in programs jointly sponsored by the National Aeronautics and Space Administration (NASA) and the Atomic Energy Commission (AEC) during the period of 1960--1972. Component tests were conducted which have established a considerable technology base for the concept. The development effort and technology status of each component are presented. The key technology issues remaining for … more
Date: January 1, 1991
Creator: Holcomb, R.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The advanced liquid metal reactor: Towards component protection based automatic control

Description: As advanced computing technology becomes part of the control system for power plants, the opportunity arises to address the real goals of plant control. Digital control systems are able to monitor more information and to accomplish more simultaneous tasks than human operators. In future nuclear plants, intelligent supervisory control systems should be responsible for maneuvering the plant in a fashion to minimize the component stress damage. The control system should generate strategies based o… more
Date: January 1, 1991
Creator: Otaduy, P. J.; Brittain, C. R. & Rovere, L. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Safety and licensing analysis of 471 MWt PRISM reactor module

Description: Independent analyses of unscrammed events postulated for the 471 MW PRISM reactor module, as performed by Brookhaven National Laboratory for the US Nuclear Regulatory Commission, are discussed. Peak fuel, cladding, and sodium temperatures for several postulated events were compared against current temperatures limits. For the postulated unscrammed loss of flow (ULOF) events, the newly added Gas Expansion Modules (GEMs), have improved the passive shutdown response. For the unscrammed transient o… more
Date: January 1, 1991
Creator: Van Tuyle, G.J.; Slovik, G.C. (Brookhaven National Lab., Upton, NY (United States)); Throm, E.D. & Sands, S.P. (Nuclear Regulatory Commission, Washington, DC (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Performance of fast reactor mixed-oxide fuels pins during extended overpower transients

Description: The Operational Reliability Testing (ORT) program, a collaborative effort between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corp. (PNC) of Japan, was initiated in 1982 to investigate the behavior of mixed-oxide fuel pin under various slow-ramp transient and duty-cycle conditions. In the first phase of the program, a series of four extended overpower transient tests, with severity sufficient to challenge the pin cladding integrity, was conducted. The objectiv… more
Date: February 1, 1991
Creator: Tsai, H.; Neimark, L.A. (Argonne National Lab., IL (USA)); Asaga, T. & Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A worldwide perspective on actinide burning

Description: Worldwide interest has been evident over the past few years in reexamining the merits of recovering the actinides from spent light-water reactor (LWR) fuel and transmuting them in fast reactors to reduce hazards in geologic repositories. This paper will summarize some of the recent activities in this field. Several countries are embarked on programs of reprocessing and vitrification of present wastes, from which removal of the actinides is largely precluded. The United States is assessing the i… more
Date: January 1, 1991
Creator: Burch, W.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of postulated events for the revised ALMR/PRISM design

Description: The Nuclear Regulatory Commission (NRC) is continuing a pre-application review of the 471 MWt, Liquid Metal Reactor, PRISM by General Electric, with Brookhaven National Laboratory providing technical support. The revised design has been evaluated, using the SSC code, for an unscrammed loss of heat sink (ULOHS), an unscrammed loss of flow (ULOF) with and without the Gas Expansion Modules (GEMs), and a 40{cents} unscrammed transient overpower (UTOP) event. The feedback effects for U-27Pu-10Zr met… more
Date: January 1, 1991
Creator: Slovik, G.C. & Van Tuyle, G.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Recycle of LWR (Light Water Reactor) actinides to an IFR (Integral Fast Reactor)

Description: A large quantity of actinide elements is present in irradiated Light Water Reactor (LWR) fuel that is stored throughout the world. Because of the high fission-to-capture ratio for the transuranium (TRU) elements with the high-energy neutrons in the metal-fueled Integral Fast Reactor (IFR), that reactor can consume these elements effectively. The stored fuel represents a valuable resource for an expanding application of fast power reactors. In addition, removal of the TRU elements from the spent… more
Date: January 1, 1991
Creator: Pierce, R. D.; Ackerman, J. P.; Johnson, G. K.; Mulcahey, T. P. & Poa, D. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Actinide consumption: Nuclear resource conservation without breeding

Description: A new approach to the nuclear power issue based on a metallic fast reactor fuel and pyrometallurgical processing of spent fuel is showing great potential and is approaching a critical demonstration phase. If successful, this approach will complement and validate the LWR reactor systems and the attendant infrastructure (including repository development) and will alleviate the dominant concerns over the acceptability of nuclear power. The Integral Fast Reactor (IFR) concept is a metal-fueled, sod… more
Date: January 1, 1991
Creator: Hannum, W. H.; Battles, J. E.; Johnson, T. R. & McPheeters, C. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Behavior of low-burnup metallic fuels for the integral fast reactor at elevated temperatures in ex-reactor tests

Description: A series of ex-reactor heating tests on low burnup U-26wt.%Pu-10wt.%Zr metallic fuel for the PRISM reactor was conducted to evaluate fuel/cladding metallurgical interaction and its effect on cladding integrity at elevated temperatures. The reaction between the fuel and cladding caused liquid-phase formation and dissolution of the inner surface of the cladding. The rate of cladding penetration was below the existing design correlation, which provides a conservative margin to cladding failure. In… more
Date: July 1, 1991
Creator: Tsai, Hanchung; Liu, Yung Y.; Wang, Da-Yung & Kramer, J. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Pressure-surge mitigation methods in fluid-conveying piping

Description: Pressure surges in the heat transport system of nuclear reactor plants can affect the safety and reliability of the plants. Hence the pressure surges must be considered in the design, operation, and maintenance of the plants in order to minimize their occurrence and impacts. The objectives of this paper are to review various methods to control or mitigate the pressure surges, to analyze these methods to gain understanding of the mitigation mechanisms, and examine applicability of the methods to… more
Date: January 1, 1991
Creator: Shin, Y.W.; Youngdahl, C.K. (Argonne National Lab., IL (USA)) & Wiedermann, A.H. (IIT Research Inst., Chicago, IL (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear Reactors and Technology; (USA)

Description: Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also … more
Date: January 1, 1991
Creator: Cason, D.L. & Hicks, S.C. (eds.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

IFR Fuel Cycle Demonstration in the EBR-II Fuel Cycle Facility

Description: The next major milestone of the IFR program is engineering-scale demonstration of the pyroprocess fuel cycle. The EBR-II Fuel Cycle Facility has just entered a startup phase which includes completion of facility modifications, and installation and cold checkout of process equipment. This paper reviews the design and construction of the facility, the design and fabrication of the process equipment, and the schedule and initial plan for its operation. 5 refs., 4 figs.
Date: January 1, 1991
Creator: Lineberry, M. J.; Phipps, R. D.; Rigg, R. H.; Benedict, R. W.; Carnes, M. D.; Herceg, J. E. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Improvements in EBR-2 core depletion calculations

Description: The need for accurate core depletion calculations in Experimental Breeder Reactor No. 2 (EBR-2) is discussed. Because of the unique physics characteristics of EBR-2, it is difficult to obtain accurate and computationally efficient multigroup flux predictions. This paper describes the effect of various conventional and higher order schemes for group constant generation and for flux computations; results indicate that higher-order methods are required, particularly in the outer regions (i.e. the … more
Date: January 1, 1991
Creator: Finck, P.J.; Hill, R.N. & Sakamoto, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
Back to Top of Screen