635 Matching Results

Search Results

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

Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

Description: This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - … more
Date: September 1, 1985
Creator: Owen, P. T.; Michelson, D. C. & Knox, N. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Configuration Management Program Plan

Description: Westinghouse Savannah River Company (WSRC) has established a configuration management (CM) plan to execute the SRS CM Policy and the requirements of the DOE Order 4700.1. The Reactor Restart Division (RRD) has developed its CM Plan under the SRS CM Program and is implementing it via the RRD CM Program Plan and the Integrated Action Plan. The purpose of the RRD CM program is to improve those processes which are essential to the safe and efficient operation of SRS production reactors. This docume… more
Date: September 25, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SACRD: a data base for fast reactor safety computer codes, operational procedures

Description: SACRD (Safety Analysis Computerized Reactor Data) is a data base of nondesign-related information used in computer codes for fast reactor safety analyses. This document reports the procedures used in SACRD to help assure a reasonable level of integrity of the material contained in the data base. It also serves to document much of the computer software used with the data base.
Date: September 1, 1980
Creator: Forsberg, V. M.; Arwood, J. W.; Greene, N. M. & Raiford, G. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Development Program Progress Report, August 1961

Description: Progress is reviewed on the following reactors: EBWR; Borax-V; ZPR-III- ZPR-VI; ZPR-IX; EBR-I; and EBR-II. An outline of fast and slow reactor safety studies in TREAT is presented. Progress is also reported in applied nuclear and reactor physics; development of reactor fuels, materials, and components; heat engineering technology; separation processes; and advanced reactor concepts. (T.F.H.)
Date: September 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Linear accelerator driven (LADR) and regenerative reactors (LARR) for nuclear non-proliferation

Description: Linear accelerator breeders (LAB) could be used to produce fissile fuel in two modes, either with fuel reprocessing or without fuel reprocessing. With fuel reprocessing, the fissile material would be separated from the target and refabricated into a fuel element for use in a burner power reactor. Without reprocessing, the fissile material would be produced in-situ, either in a fresh fuel element or in a depleted or burned element after use in a power reactor. In the latter mode the fissile mate… more
Date: September 1, 1977
Creator: Steinberg, M.; Takahashi, H.; Powell, J. R. & Kouts, H. J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of TRAC and RELAP5 reactor system calculations for a DEGB LOCA in K-14. 1

Description: A comparison of TRAC and RELAP5 predictions of steady-state and DEGB LOCA results (FI phase) for K-14.1 has been made. Both codes had been previously benchmarked against 1985 L Reactor AC Flow data and were under configuration control. The purpose of the code-to-code comparison is to provide insight on the transient uncertainty in TRAC plenum and tank bottom plenum pressures. The comparisons focus on LOCA results between 0.5 and 2.0 s, which is the primary period of interest for Flow Instabilit… more
Date: September 1, 1990
Creator: Griggs, D.P. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Liebmann, M.L. (Wais and Associates (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seismic hazard evaluation for the high-flux isotope reactor (HFIR) Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: This study investigates the probabilistic hazard of earthquake-induced ground shaking at the HFIR facility, Oak Ridge, Tennessee. These results will be used to calculate plant response and potential effects in a Probabilistic Risk Assessment (PRA). For this purpose, several guidelines apply to this work. First, both the frequency of exceedance and the uncertainty in frequency of exceedance of various ground motion levels must be represented. These are required by the PRA so that the frequency a… more
Date: September 1, 1991
Creator: McGuire, R.K. & Toro, G.R. (Risk Engineering, Inc., Golden, CO (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Description: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during-a loss of flow acident, ART-02, a onedimensional code, was used. This analysis indicated the SM-2 core is safe from burnout under steady state operation at design power level (28 Mw(t)) because no nucleate boiling exists, and the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of … more
Date: September 1, 1961
Creator: Segalman, I. & Bradley, P. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Status Report on LAMPRE Porgram for Period Ending August 20, 1962

Description: Operation of the Lampre I during the report period is described and data on the operating history of this reactor are summarized. Other work is reported on core calculations, fuel and container development, and compatibility of Pu-Co- Ce alloys with Ta. Studies of the physical properties of Pu alloys with C, ln, Si, and rare earths are described. Data on the room temperature densities in the Pu-Ce-Co alloy system are presented. Solvent extraction studies concerning separation of Pu are included… more
Date: September 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Resource book: Decommissioning of contaminated facilities at Hanford

Description: In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-lev… more
Date: September 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seismic analysis of reactor exhaust air filter compartment

Description: The Filter Compartment (FC) in this analysis is a generic reactor airborne activity confinement filter compartment which possesses all the essential physical and mechanical properties of the Savannah River Site (SRS) confinement filters of Reactor Buildings K, L, and P. The filters belong to the Airborne Activity Confinement System (AACS). These filters absorb a significant amount of radioactive effluents from the exhausting air. The seismic excitation is input indirectly from the output of the… more
Date: September 24, 1990
Creator: Gong, Chung; Funderburk, E.L. & Jerrell, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MULTIGROUP CALCULATIONS OF EFFECTIVE NEUTRON FRACTION $beta$eff' PROMPT NEUTRON LIFETIME lp' AND RELATED KINETICS PARAMETERS FOR LARGE, FAST, PLUTONIUM-FUELED REACTORS

Description: Large, plutonium-fueled, fast reactors will have a different kinetic behavior than fast reactors fueled with U/sup 235/, due to the much smaller delayed-neutron fraction emitted in the fissioning of plutonium. The fissioning of Pu/sup 240/, Pu/sup 241/, Pu/sup 242/, and especially U/sup 238/, which emit mor e delayed neutrons per fission than Pu/sup 239/, introduces a considerable increase in BETA /sub eff/ over that for a hypothetical pure Pu/sup 239/ reactor. The cases considered are 800-, 15… more
Date: September 1, 1961
Creator: Sandmeier, H.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced thermohydraulic simulation code for pool-type LMFBRs (SSC-P code)

Description: Models for components and processes that are needed for simulation of thermohydraulic transient in a pool-type liquid metal fast breeder reactor (LMFBR) plant are described in this report. A computer code, SSC-P, has been developed as a part of the Super System Code (SSC) development project. A user's manual is being prepared as a separate document. 27 refs., 26 figs., 1 tab.
Date: September 1, 1980
Creator: Madni, I. K. & Cazzoli, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Small Power Reactor Projects of the United States Atomic Energy Commission

Description: Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date: September 28, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Status Report on LAMPRE Program for Period Ending August 20, 1961

Description: BS>All basic experiments planned for the LAMPRE I startup program were completed. The tests included operation at 100 and 200 kw utilizing both normal and half coolant flow, and full flow operation at 400 kw. At each power level, transfer function measurements were made, and a continuous run of approximately 60 hr duration was carried out to determine the characteristics of the reactivity loss first observed at 50 kw. Various power demand tests were made. Fuel and container development was cont… more
Date: September 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Modified Purification System Performance Test. Core I, Seed 2. Test Results (T-641124). Section 1

Description: An investigation was conducted to establish an operating procedure for flushing water through a purification system demineralizer which was out of service for an extended period, and to determine the demineralizer serviceability. (J.R.D.)
Date: September 14, 1960
Creator: Duquesne Light Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Identification and assessment of containment and release management strategies for a BWR Mark I containment

Description: This report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark 1 type of containment. Based on information available from probabilistic risk assessments and other existing severe accident research, and using simplified containment and release event trees, the report identifies the challenges a Mark 1 containment could face during t… more
Date: September 1, 1991
Creator: Lin, C. C. & Lehner, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Soil-Structure Interaction Methods, SIM Code. Volume III

Description: The Structure In Media (SIM) Code determines the response of a structure, embedded in soil/rock media, to a specified dynamic disturbance in the media. The structure is modeled as a series of lumped mass, elastic beams which may be interconnected with elastic springs. The disturbance in the free field is specified in terms of an accelerogram, the scale of which may vary with depth. Soil/structure interaction is treated in two parts. The first determines the interaction forces developed at the b… more
Date: September 1, 1979
Creator: Miller, C. A. & Costantino, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparative analysis of internal fuel motion in annular fuel designs

Description: In this paper, the whole-core reactivity consequences of internal fuel motion in three annular fuel designs during a hypothetical 3 dollars/s transient overpower (TOP) accident are compared to determine the effect of geometric design variations. The PINEX-2 and PINEX-3 experiments were performed in the TREAT reactor using annular fuel pins irradiated in GETR. This paper investigates three combinations of solid and annular axial blankets and fission gas plena: top annular blanket and plenum, bot… more
Date: September 16, 1983
Creator: Smith, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Standard interface files and procedures for reactor physics codes. Version IV

Description: Standards, procedures, and recommendations of the Committee on Computer Code Coordination for promoting the exchange of reactor physics codes are updated to Version IV status. Standards and procedures covering general programming, program structure, standard interface files, and file management and handling subroutines are included.
Date: September 1, 1977
Creator: O'Dell, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Review of physics methodology of ATR safety analysis

Description: At the request of EG G Idaho, the Pacific Northwest Laboratory (PNL) performed a brief review of the physics methods employed in the safety analyses for the Advanced Test Reactor. PNL determined that the general approach used by EG G was sound. Comparisons were made between the EG G results and a simplified PBL model. These demonstrated good agreement. However, the lack of spacial treatment of the moderator density reactivity coefficient and exclusion of the test loops from the reactivity model… more
Date: September 1, 1991
Creator: Little, W.W. & Heaberlin, S.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Resource book: Decommissioning of contaminated facilities at Hanford

Description: In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-lev… more
Date: September 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen