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BWR refill-reflood program: core spray distribution experimental task plan

Description: An experimental task plan for the BWR/4 core spray task of the Refill-Reflood Test Program is presented. The test program will provide core spray distribution data for a 30 degree sector of the BWR/4 and 5-218 design. This design uses different nozzle types and different sparger elevations than the BWR/6-218 design which was tested previously. Test parameter ranges are specified; individual tests are defined; and measurement and data utilization plans are defined.
Date: February 1, 1981
Creator: Eckert, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT emergency core coolant thermal analysis Class I review

Description: The LOFT Emergency Core Coolant Piping Thermal Analysis was checked to insure that the calculations made would conservatively satisfy the requirements in the LOFT technical specifications. Some of the boundary conditions used have not been shown to be conservative and require review and possible re-analysis. One of the thermal models used could not be clearly related to a specific part of the piping geometry and requires further explanation. The remainder of the models, the use of the SIMIR cod… more
Date: February 3, 1978
Creator: Kinnaman, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT blowdown loop piping thermal analysis Class I review

Description: In accordance with ASME Code, Section III requirements, all analyses of Class I components must be independently reviewed. Since the LOFT blowdown loop piping up through the blowdown valve is a Class I piping system, the thermal analyses are reviewed. The Thermal Analysis Branch comments to this review are also included. It is the opinion of the Thermal Analysis Branch that these comments satisfy all of the reviewers questions and that the analyses should stand as is, without additional conside… more
Date: February 14, 1978
Creator: Kinnaman, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Review of reports associated with systems of the K, P and L reactors at the Savannah River Site

Description: Six reports associated with the structural integrity of several systems of the Savannah River Site reactors are reviewed. The focus is on the materials-related aspects of the reports and no attempt is made to address the stress analysis-related issues.
Date: February 1, 1992
Creator: Cowgill, M. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Core-debris quenching-heat-transfer rates under top- and bottom-reflood conditions. [PWR; BWR]

Description: This paper presents recent experimental data for the quench-heat-transfer characteristics of superheated packed beds of spheres which were cooled, in separate experiments, by top- and bottom-flooding modes. Experiments were carried out with beds of 3-mm steel spheres of 330-mm height. The initial bed temperature was 810 K. The observed heat-transfer rates are strongly dependent on the mode of water injection. The results suggest that top-flood bed quench heat transfer is limited by the rate at … more
Date: February 1, 1983
Creator: Ginsberg, T.; Tutu, N.; Klages, J.; Schwarz, C. E. & Sanborn, Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Implications for accident management of adding water to a degrading reactor core

Description: This report evaluates both the positive and negative consequences of adding water to a degraded reactor core during a severe accident. The evaluation discusses the earliest possible stage at which an accident can be terminated and how plant personnel can best respond to undesired results. Specifically discussed are (a) the potential for plant personnel to add water for a range of severe accidents, (b) the time available for plant personnel to act, (c) possible plant responses to water added dur… more
Date: February 1, 1994
Creator: Kuan, P.; Hanson, D. J.; Pafford, D. J.; Quick, K. S. & Witt, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Review of reports associated with systems of the K, P and L reactors at the Savannah River Site

Description: Six reports associated with the structural integrity of several systems of the Savannah River Site reactors are reviewed. The focus is on the materials-related aspects of the reports and no attempt is made to address the stress analysis-related issues.
Date: February 1, 1992
Creator: Cowgill, M. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly technical report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, July--September 1975

Description: Light water reactor safety activities performed during July through September 1975 are summarized. The isothermal blowdown test series of the Semiscale Mod-1 test program has provided data for evaluation of break flow phenomena and analyses of piping flow regimes and pump performance. In the LOFT Program, measurement uncertainties were evaluated. The Thermal Fuels Behavior Program completed two power-cooling-mismatch tests on PWR-type fuel rods to investigate critical heat flux characteristics.… more
Date: February 1, 1976
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiment data report for Semiscale Mod-1 Test S-05-2 (alternate ECC injection test)

Description: Recorded test data are presented for Test S-05-2 of the Semiscale Mod-1 alternate emergency core coolant (ECC) injection test series. This test is one of several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-05-2 was conducted from an initial cold leg fluid temperature of 545/sup 0/F and an initial pressure of 2263 psia. A simulated double-ended off… more
Date: February 1, 1977
Creator: Feldman, E. M.; Collins, B. L. & Sackett, K. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiment data report for Semiscale Mod-1 Test S-05-1 (alternate ECC injection test)

Description: Recorded test data are presented for Test S-05-1 of the Semiscale Mod-1 alternate ECC injection test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-05-1 was conducted from initial conditions of 2263 psia and 544/sup 0/F to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood tr… more
Date: February 1977
Creator: Feldman, Edgar M.; Patton, Morris L., Jr. & Sackett, Kenneth E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uninstrumented assembly airflow testing in the Annular Flow Distribution facility

Description: During the Emergency Cooling System phase of a postulated large-break loss of coolant accident (ECS-LOCA), air enters the primary loop and is pumped down the reactor assemblies. One of the experiments performed to support the analysis of this accident was the Annular Flow Distribution (AFD) experiment, conducted in a facility built for this purpose at Babcock and Wilcox Alliance Research Center in Alliance, Ohio. As part of this experiment, a large body of airflow data were acquired in a protot… more
Date: February 1, 1992
Creator: Kielpinski, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project

Description: This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency c… more
Date: February 27, 2007
Creator: Williams, Brian G.; Liou, Jim C. P.; Kadakia, Hiral; Phoenix, Bill & Schultz, Richard R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

1-1/2-Loop Semiscale Isothermal Test Program: Program and System Description in Support of Experiment Data Reports.

Description: The isothermal test series is part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project conducted by Aerojet Nuclear Company for the U. S. Atomic Energy Commission. The test series consisted of ten blowdown tests and five hot-wall tests with emphasis on emergency core coolant delivery. The blowdown tests were conducted to investigate the effects of lower plenum geometry, heat transfer configuration, ECC injection location, downcomer gap size, and break size.
Date: February 1, 1974
Creator: Aerojet Nuclear Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of pipe whip impacts on neighboring piping and walls of the Ignalina nuclear power plant.

Description: Presented in this paper is the transient analysis of a Group Distribution Header (GDH) following a guillotine break at the end of the header. The GDH is the most important component of reactor safety in case of accidents. Emergency Core Cooling System (ECCS) piping is connected to the GDH piping such that, during an accident, coolant passes from the GDH into the ECCS. The GDH that is propelled into motion after a guillotine break can impact neighboring GDH pipes or the nearest wall of the compa… more
Date: February 26, 2002
Creator: Dundulis, G.; Kulak, R.F.; Marchertas, A.; Narvydas, E.; Petri, M.C. & Uspusas, E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Experimental study of head loss and filtration for LOCA debris

Description: A series of controlled experiments were conducted to obtain head loss and filtration characteristics of debris beds formed of NUKON{trademark} fibrous fragments, and obtain data to validate the semi-theoretical head loss model developed in NUREG/CR-6224. A thermally insulated closed-loop test set-up was used to conduct experiments using beds formed of fibers only and fibers intermixed with particulate debris. A total of three particulate mixes were used to simulate the particulate debris. The h… more
Date: February 1, 1996
Creator: Rao, D.V. & Souto, F.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Estimated net value and uncertainty for automating ECCS switchover at PWRs

Description: Question for resolution of Generic Safety Issue No. 24 is whether or not PWRs that currently rely on a manual system for ECCS switchover to recirculation should be required to install an automatic system. Risk estimates are obtained by reevaluating the contributions to core damage frequencies (CDFs) associated with failures of manual and semiautomatic switchover at a representative PWR. This study considers each separate instruction of the corresponding emergency operating procedures (EOPs), th… more
Date: February 1, 1996
Creator: Walsh, B.; Brideau, J.; Comes, L.; Darby, J.; Guttmann, H.; Sciacca, F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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