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in subjects: "Mockup"

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De-entrainment on vertical elements in air droplet cross flow. [PWR]

De-entrainment phenomena on vertical elements in air-water droplet cross flow are generated using a horizontal array of water spray nozzles and a draft-induced wind tunnel. These conditions are used to obtain experimental values of the de-entrainment efficiency of isolated elements (25.4-, 63.5-, and 101.6-mm-diam cylinders and a 76.2-mm-square tube), and of an array of 101.6-mm-diam cylinders. A flow model is developed that extrapolates the de-entrainment efficiency of isolated elements throug… more

Date: January 1, 1980

Creator: Dallman, J.C. & Kirchner, W.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Acoustic measurements of the boiling stability tests on THORS sodium loop. [LMFBR]

Acoustic data of boiling stability tests on the THORS (Thermal-Hydraulic Out-of-Reactor Safety) facility were obtained using three sodium-immersible high temperature microphones. The data was analyzed in both the time and frequency domains and provides the following information: (1) the acoustic signal due to sodium boiling was clearly observed; (2) the signal level and the repetition rate of boiling pulses are directly proportional to the applied heat flux; (3) a typical boiling pulse consists… more

Date: January 1, 1977

Creator: Sheen, S.H.; Bobis, J.P. & Carey, W.M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

PNL In Vivo Phantom Library Calibration Program

No Description Available.

Date: October 1, 1991

Creator: Olsen, P. C.; Nichols, L. L.; Sisk, D. R. (Pacific Northwest Lab., Richland, WA (United States)) & Loesch, R. M. (USDOE, Washington, DC (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Mark I 1/5-scale boiling water reactor pressure suppression experiment facility report

An accurate Mark I /sup 1///sub 5/-scale, boiling water reactor (BWR), pressure suppression facility was designed and constructed at Lawrence Livermore Laboratory (LLL) in 11 months. Twenty-seven air tests using the facility are described. Cost was minimized by utilizing equipment borrowed from other LLL programs. The total value of borrowed equipment exceeded the program's budget of $2,020,000. Substantial flexibility in the facility was used to permit independent variation in the drywell pres… more

Date: October 11, 1977

Creator: Altes, R.G.; Pitts, J.H.; Ingraham, R.F.; Collins, E.K. & McCauley, E.W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Experimental considerations for the calibration of personnel dosimeters with photons

The criteria for irradiating radiation dosimeters for test purposes are defined quite clearly in Draft ANSI Standard N13.11. In this Draft the use of phantoms, constructed of a near tissue equivalent material, is prescribed for backing the dosimeters while being irradiated, thus simulating a dosimeter being irradiated while attached to a person. When the phantom is placed in the photon beam it becomes a major source of scattered radiation. The scatter component into the dosimeter is a function … more

Date: unknown

Creator: Hooker, C.D.; Yoder, R.C. & Courtney, J.W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Radiation standards and calibrations. FY-1981 annual report

The research program encompasses: reviewing calibration standards, regulations, and handbooks; assuring that calibration procedures used are in agreement with technically accepted methods; maintaining basic radioactive sources and instruments that serve as radiological standards; and providing traceability to the National Bureau of Standards where possible. In addition, major efforts are being expended to upgrade the 318 calibration facility. This report focuses on major accomplishments during … more

Date: July 1, 1982

Creator: Roberson, P. L.; Yoder, R. C.; Fox, R. A.; Hooker, C. D.; Hogan, R. T.; Holbrook, K. L. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Results and predictions of scaled, nuclear large break loss-of-coolant experiments. [PWR]

Two 200% cold leg break loss-of-coolant experiments performed in the LOFT facility have exhibited early core-wide quenches which were not predicted by the RELAP4/MOD6 code. Posttest studies have shown that while the critical flow model used significantly affects the hydraulic calculation, the principal reason for not predicting the quench behavior lies in the area of post-CHF heat transfer. The ability of the code to calculate quenches using a modified heat transfer surface is demonstrated, the… more

Date: January 1, 1980

Creator: Grush, W. H.; Lin, J. C.; Linebarger, J. H. & Nelson, R. A. Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Test PCM-5 rod bowing and bow direction reversal. [PWR]

Test PCM-5 was the first bundle test in the PCM Test Series being conducted by the Thermal Fuels Behavior Program of EG and G Idaho, Inc. as part of the Nuclear Regulatory Commission's Fuel Behavior Program. The experiment was performed in the Power Burst Facility (PBF) reactor at the Idaho National Engineering Laboratory. The bundle consisted of nine previously unirradiated PWR-type fuel rods, arranged in a 3 x 3 array within a square cross section flow shroud, with rod-to-rod spacing typical … more

Date: January 1, 1980

Creator: Kerwin, D. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Contribution of secondary electrons to radiation fields produced by pion beams

In recent years many biological and therapeutic studies have been done with a variety of high-energy particles. Although the theoretical and experimental application of collision cross sections for low-energy particles (less than or equal to 20 MeV) to microsodimetry continues to be a major area of interest, relatively little effort has been devoted to the application of such cross sections to a description of the interaction of high-energy particles in tissue. This article presents an approach… more

Date: January 1, 1982

Creator: Dicello, J.F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

MLE (Maximum Likelihood Estimator) reconstruction of a brain phantom using a Monte Carlo transition matrix and a statistical stopping rule

In order to study properties of the Maximum Likelihood Estimator (MLE) algorithm for image reconstruction in Positron Emission Tomographyy (PET), the algorithm is applied to data obtained by the ECAT-III tomograph from a brain phantom. The procedure for subtracting accidental coincidences from the data stream generated by this physical phantom is such that he resultant data are not Poisson distributed. This makes the present investigation different from other investigations based on computer-si… more

Date: October 1, 1987

Creator: Veklerov, E.; Llacer, J. & Hoffman, E.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Estimating Adipose Tissue in the Chest Wall Using Ultrasonic and Alternate /sup 40/K and Biometric Measurements

The percentage of adipose (fat) tissue in the chest wall must be known to accurately measure Pu in the human lung. Correction factors of 100% or more in x-ray detection efficiency are common. Methods using simple /sup 40/K and biometric measurement techniques were investigated to determine the adipose content in the human chest wall. These methods predict adipose content to within 15% of the absolute ultrasonic value. These new methods are discussed and compared with conventional ultrasonic mea… more

Date: January 22, 1982

Creator: Anderson, A. L. & Campbell, G. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Effects of a hypothetical loss-of-coolant accident on a Mark I Boiling Water Reactor pressure-suppression system

A loss-of-coolant accident (LOCA) in a boiling-water-reactor (BWR) power plant has never occurred. However, because this type of accident could be particularly severe, it is used as a principal theoretical basis for design. A series of consistent, versatile, and accurate air-water tests that simulate LOCA conditions has been completed on a /sup 1///sub 5/-scale Mark I BWR pressure-suppression system. Results from these tests are used to quantify the vertical-loading function and to study the as… more

Date: December 22, 1977

Creator: Pitts, J.H. & McCauley, E.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Kilowatt Isotope Power System: Test Procedure for the EHSA Multifoil Insulation. 77-KIPS-109

The procedure is described for conducting the multifoil insulation meltdown test on the electrical heat source assembly (EHSA). The results of the tests will be used to verify the predicted sequence of events during multifoil insulation meltdown and to determine the ultimate steady-state temperatures of the various EHSA components.

Date: January 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Scaling neutron absorbed dose distributions from one medium to another

Central axis depth dose (CADD) and off-axis absorbed dose ratio (OAR) measurements were made in water, muscle and whole skeletal bone TE-solutions, mineral oil and glycerin with a clinical neutron therapy beam. These measurements show that, for a given neutron beam quality and field size, there is a universal CADD distribution at infinity if the depth in the phantom is expressed in terms of appropriate scaling lengths. These are essentially the kerma-weighted neutron mean free paths in the medi… more

Date: November 1, 1982

Creator: Awschalom, M.; Rosenberg, I. & Ten Haken, R.K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

First in-core molten fuel pool experiment. [LMFBR]

If during a LMFBR accident a fuel debris bed is not adequately cooled by overlying sodium and dryout occurs, then the fuel would heat up and melt. Molten fuel pools are of concern due to their potential for ablation of the supporting structure and possible penetration of the reactor vessel. The major goal of the molten fuel pool program has been to develop a versatile experiment in which heat flux and structural ablation could be studied using real materials under typical temperature and heatin… more

Date: January 1, 1977

Creator: Plein, H.G. & Carlson, G.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Ceramic processing of boron nitride insulators

Fuel pin simulators (FPS) are the prime elements of several test facilities at the Oak Ridge National Laboratory (ORNL). These experimental facilities are used to conduct out-of-reactor thermal-hydraulic and mechanical interaction safety tests for both light-water and breeder reactor programs. The FPS units simulate the geometry, heat flux profiles, and operational capabilities of a reactor core element under steady-state and transient conditions. They are subjected to temperatures as high as 1… more

Date: January 1, 1977

Creator: Morgan, C.S. & McCulloch, R.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Preliminary characterization of the pressure suppression experiment load response and source analysis: air test series. [BWR]

Data from air tests conducted on the 1/5-Scale Model Mark I Pressure Suppression Facility at Lawrence Livermore Laboratory were analyzed for the purpose of determining the various sources of load signature characteristics. It was determined that hydrodynamic vertical loading function embodies effects from: (a) momentum flux associated with flow from the downcomers; (b) momentum rate associated with bulk pool motion; and (c) unbalanced internal pressure forces related to phenomena associated wit… more

Date: August 8, 1977

Creator: Davis, B. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Gas-Cooled Fast Reactor Program. Progress report, July 1, 1975--December 31, 1976

Progress in GCFR-related research is reported for the following: core flow test loop, GCFR irradiation experiments, pressure vessel and closure studies, shielding studies, and fuel recycle studies.

Date: December 1, 1977

Creator: Gat, U.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fire Protection Research Program at Sandia Laboratories. [BWR; PWR]

Sandia Laboratories is executing a program for the Nuclear Regulatory Commission to provide data needed for confirmation of the suitability of current design standards and regulatory guides for fire protection and control in water reactor power plants. This paper summarizes the activities of this ongoing program through December 1979. Characterization of electrically initiated fires revealed a margin of safety in the separation criteria of Regulatory Guide 1.75 for such fires in IEEE-383 qualif… more

Date: January 1, 1980

Creator: Klamerus, L.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

CRBRP design for maintainability

A one-half-inch-to-a-foot scale model of the plant is the central tool for assessing the maintainability of the design. As individual systems and components are placed on the model, an evaluation is made to optimize maintenance access. Later the model is reviewed on an area basis to insure that mutual access is afforded to all components located within each cell and that maintenance platform configurations and laydown are provided space for component disassembly. Maintenance access requirements… more

Date: January 1, 1982

Creator: Spear, R.; O'Bryant, W. J. & Perry, E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

SAS3D analysis of natural convection boiling behavior in the Sodium Boiling Test Facility

The objective of the initial phase of testing in the Sodium Boiling Test (SBT) Facility, at the Oak Ridge National Laboratory, was to determine the maximum power that could be transferred by a simulated breeder reactor coolant subchannel when the coolant flow is driven by natural convection. In order to aid in the evaluation of the experimental data and to help understand the flow regimes present at the various power levels examined during this test program, a SAS3D computer model of the SBT Fa… more

Date: January 1, 1979

Creator: Klein, G. & Dunn, F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Growth of molten core debris pools in concrete. Part II. A. Pool growth in composite beds; B. Effect of overlaying steel layers. Final report, March 1, 1978-September 30, 1979. [LMFBR]

The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool s… more

Date: December 26, 1979

Creator: Abdel-Khalik, S I

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Experiment data report for Semiscale Mod-1 Tests S-28-7, S-28-9, and S-28-12. [PWR]

Recorded test data are presented for Tests S-28-7, S-28-9, and S-28-12 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. Tests S-28-7, S-28-9, and S-28-12 were conducted from initial conditions of 15 736 kPa and 557 K, 15 754 kPa and 556 K, and 15 704 kPa and 559 K, … more

Date: February 1, 1978

Creator: Esparza, V.; Collins, B.L.; Sackett, K.E. & Coppin, C.E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Modeling a nuclear reactor for experimental purposes. [PWR]

The Loss-of-Fluid Test (LOFT) Facility is a scale model of a commercial PWR and is as fully functional and operational as the generic commercial counterpart. LOFT was designed and built for experimental purposes as part of the overall NRC reactor safety research program. The purpose of LOFT is to assess the capability of reactor safety systems to perform their intended functions during occurrences of off-normal conditions in a commercial nuclear reactor. Off-normal conditions arising from large… more

Date: January 1, 1980

Creator: Berta, V.T.

Item Type: Article

Partner: UNT Libraries Government Documents Department