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Environmental monitoring at major U. S. Energy Research and Development Administration contractor sites: calendar year 1976. Volume 2

Description: The purpose of this compilation is to present, in a central reference document, all of the individual annual reports summarizing the results of the environmental monitoring programs conducted at each of the Energy Research and Development Administration (ERDA) sites having a potential for environmental impact or which release a significant quantity of radioactivity or nonradioactive pollutants. Data on the levels of radioactivity and nonradioactive pollutants in effluents and the environs at ea… more
Date: August 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Argonne Code Center: benchmark problem book

Description: This report is a supplement to the original report, published in 1968, as revised. The Benchmark Problem Book is intended to serve as a source book of solutions to mathematically well-defined problems for which either analytical or very accurate approximate solutions are known. This supplement contains problems in eight new areas: two-dimensional (R-z) reactor model; multidimensional (Hex-z) HTGR model; PWR thermal hydraulics--flow between two channels with different heat fluxes; multidimension… more
Date: June 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT Steam Generator thermal analysis Class I review

Description: A Class 1 review of the thermal analysis of the LOFT Steam Generator and of the transient thermal analysis of LOFT steam generator thermal well was made to confirm compliance of the analyses with the LOFT Technical Specifications, with the LOFT integral test system - preliminary component design description for the steam generator, and with Appendix C of ANC Specification 60139. Included in this review is an examination of the thermal transients and conditions to insure adequate conservatism in… more
Date: October 6, 1977
Creator: Kinnaman, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Finite-difference methods in multi-dimensional two-phase flow. [BWR; PWR; LMFBR]

Description: In the summer of 1974, the Theoretical Division of the Los Alamos Scientific Laboratory began several research programs in the area of reactor safety for the United States Nuclear Regulatory Commission. Research efforts were started in the Liquid Metal Fast Breeder (LMFBR) and the Light Water Reactor (LWR) safety programs. The character of the Theoretical Division was to develop computer codes for the safety analysis of these reactor systems. The question of whether or not, during the course of… more
Date: January 1, 1977
Creator: Travis, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Assessment of a small pressurized water reactor for industrial energy

Description: An evaluation of several recent ERDA/ORNL sponsored studies on the application of a small, 365 MW(t) pressurized water reactor for industrial energy is presented. Preliminary studies have investigated technical and reliability requirements; costs for nuclear and fossil based steam were compared, including consideration of economic inflation and financing methods. For base-load industrial steam production, small reactors appear economically attractive relative to coal fired boilers that use coal… more
Date: October 4, 1977
Creator: Klepper, O. H.; Fuller, L. C. & Myers, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary report on Battelle Northwest Liquid Level Probes (LLP)

Description: The Battelle Northwest Liquid Level Probe was evaluated for possible use in the LOFT Blowdown Suppression Tank. The results from the test indicate that the probe will measure the liquid level to +-/sup 1///sub 4/ inch, over a range of 50 inches. The next step is to test the functionability of the probe under simulated LOFT-Blowdown Suppression Tank operating conditions.
Date: November 11, 1977
Creator: Coffin, G.R. & Ford, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT three-beam densitometer data interpretation

Description: A calculation procedure has been devised to fit the best of several density distribution models, or a default model, to chordal average fluid density measurements from the LOFT gamma densitometer to obtain an estimate of the coolant density profile and the average density. The models used are homogeneous, continuous and discontinuous stratified, and continuous and discontinuous annular. The default model is a beam length weighted average for an estimate of the average density. A computer progra… more
Date: October 1, 1977
Creator: Lassahn, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plant systems/components modularization study. Final report. [PWR]

Description: The final results are summarized of a Plant Systems/Components Modularization Study based on Stone and Webster's Pressurized Water Reactor Reference Design. The program has been modified to include evaluation of the most promising areas for modular consideration based on the level of the Sundesert Project engineering design completion and the feasibility of their incorporation into the plant construction effort.
Date: July 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT differential pressure uncertainty analysis

Description: A performance analysis of the LOFT differential pressure (..delta..P) measurement is presented. Along with completed descriptions of test programs and theoretical studies that have been conducted on the ..delta..P, specific sources of measurement uncertainty are identified, quantified, and combined to provide an assessment of the ability of this measurement to satisfy the SDD 1.4.1C (June 1975) requirement of measurement of differential pressure.
Date: March 1, 1977
Creator: Evans, R.P.; Biladeau, G.L. & Quinn, P.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Posttest REALP4 analysis of LOFT experiment L1-3A

Description: This report presents selected results of posttest RELAP4 modeling of LOFT loss-of-coolant experiment L1-3A, a double-ended isothermal cold leg break with lower plenum emergency core coolant injection. Comparisons are presented between the pretest prediction, the posttest analysis, and the experimental data. It is concluded that pressurizer modeling is important for accurately predicting system behavior during the initial portion of saturated blowdown. Using measured initial conditions rather th… more
Date: October 1, 1977
Creator: White, J.R. & Holmstrom, H.L.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PWR blowdown heat transfer separate-effects program data evaluation report: system response for thermal-hydraulic test facility test series 100

Description: Selected reduced instrument responses and analyses of the indicated phenomena are presented for Thermal-Hydraulic Test Facility (THTF) test series 100, which is part of the PWR Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomena that govern the energy transfer and transport processes occurring during a postulated loss-of-coolant accident in a pressurized-water reactor system. Comparisons are made between the trends indi… more
Date: October 21, 1977
Creator: Hedrick, R. A.; Craddick, W. G.; Turnage, K. G. & Hyman, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Research, engineering, and construction report, Engineering Analysis Division. Thermal analysis: LOFT primary coolant pump inlet nozzle, thermal analysis Class 1 review

Description: A review of the LOFT Primary Coolant Pump Inlet Nozzle Thermal Analysis was conducted to satisfy the ASME code requirement that all analyses of Class I components be independently reviewed.
Date: August 11, 1977
Creator: Kettenacker, W.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uranium production in thorium/denatured uranium fueled PWRs

Description: Uranium-232 buildup in a thorium/denatured uranium fueled pressurized water reactor, PWR(Th), was studied using a modified version of the spectrum-dependent zero dimensional depletion code, LEOPARD. The generic Combustion Engineering System 80 reactor design was selected as the reactor model for the calculations. Reactors fueled with either enriched natural uranium and self-generated recycled uranium or uranium from a thorium breeder and self-generated recycled uranium were considered. For enri… more
Date: October 18, 1977
Creator: Arthur, W.B.
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-28-4 (steam generator tube rupture test)

Description: Recorded test data are presented for Test S-28-4 of the Semiscale Mod-1 steam generator tube rupture 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-28-4 was conducted from initial conditions of 15 646 kPa and 557 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood tr… more
Date: October 1, 1977
Creator: Esparza, V. & Sackett, K.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cladding creepdown under compression. [BWR; PWR]

Description: Light-water power reactors use Zircaloy tubing as cladding to contain the UO/sub 2/ fuel pellets. In-service operating conditions impose an external hydrostatic force on the cladding, causing it to creep down into eventual contact with the fuel. Knowledge of the rate of such creepdown is of great importance to modelers of fuel element performance. An experimental system was devised for studying creepdown that meets several severe requirements by providing (1) correct stress state, (2) multiple … more
Date: November 9, 1977
Creator: Hobson, D.O.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Main steam vent line piping and valve support reanalysis

Description: A new support configuration for the one-inch Schedule 80 main steam vent line has been developed at the request of the LOFT Plant Systems Branch. This configuration will adequately support valves CV-P4-58 and CV-P4-59 without requiring supports at the centers of gravity of these valves as previously recommended. Dead weight, thermal expansion, seismic, LOCE and LOCA loading conditions were considered. Results indicate that the main steam vent piping will meet criteria specified in the ASME Code… more
Date: December 1, 1977
Creator: Nitzel, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT suppression tank spray system piping: heat exchanger BS-H-31 piping modifications

Description: A stress analysis of the piping modification, resulting from relocation of heat exchanger BS-H-31 of the LOFT Blowdown Suppressing Tank Spray System, was performed. The piping, fittings, and supports were found to comply with the criteria of Section III of the ASME Boiler and Pressure Vessel Code, 1974.
Date: November 7, 1977
Creator: Blandford, R.K.
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-28-1 (steam generator tube rupture test series)

Description: Recorded test data are presented for Test S-28-1 of the Semiscale Mod-1 steam generator tube rupture 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-28-1 was conducted from initial conditions of 15 767 kPa and 557 K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood tr… more
Date: October 1, 1977
Creator: Collins, B.L.; Coppin, C.E. & Sackett, K.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Allowable outage analysis for the LOFT CIS and reflood assist bypass valves

Description: To determine the outage time allowable for a typical 1 of 2 redundant valve configuration, a Markov model was created to analyze the various operating states for the valves. Since no performance criteria have been specified, an availability model was constructed with regard to the valve outage.
Date: June 1, 1977
Creator: Trainer, J.E. & Matthews, S.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Non-equilibrium aspects of water reactor safety

Description: A critical review of the thermal non-equilibrium phase change models applicable to the water reactor safety calculations is presented. Four specific areas are discussed: (1) rapid depressurization (flashing), (2) post-dryout heat transfer, (3) direct contact condensation, and (4) sub-cooled boiling. The models have been judged from a mechanistic viewpoint, and the areas where further work is needed have been pointed out. It is suggested that when a phase change occurs due to a difference in the… more
Date: July 1, 1977
Creator: Jones, O.C. Jr. & Saha, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of the ballooning deformation of an internally pressurized thin-wall tube during fast thermal transients

Description: A large-strain time-dependent thermoplastic analysis has been developed for the ballooning deformation of a thin-wall tube subjected to internal pressure, axial loading, and fast thermal transients. This deformation initiates with the onset of plastic instability in the material, the onset being determined by a plastic-instability criterion for strain-rate sensitive materials. The interaction among the local ballooning geometry, the state of stress, and the plastic flow process was considered, … more
Date: January 1, 1977
Creator: Lin, E.I.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fuel performance improvement program. Quarterly/annual progress report, April--September 1977. [BWR; PWR]

Description: The Fuel Performance Improvement Program has as its objective the identification and demonstration of fuel concepts with improved power ramp performance. The program contains a combination of out-of-reactor studies, in-reactor experiments and in-reactor demonstrations. Fuel concepts initially being considered include annular pellets, cladding internally coated with graphite and packed-particle fuels. The performance capability of each concept will be compared to a reference fuel of contemporary… more
Date: November 1, 1977
Creator: Crouthamel, C.E. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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