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

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Treatment of measurement uncertainties at the power burst facility

Description: The treatment of measurement uncertainty at the Power Burst Facility provides a means of improving data integrity as well as meeting standard practice reporting requirements. This is accomplished by performing the uncertainty analysis in two parts, test independent uncertainty analysis and test dependent uncertainty analysis. The test independent uncertainty analysis is performed on instrumentation used repeatedly from one test to the next, and does not have to be repeated for each test except … more
Date: January 1, 1980
Creator: Meyer, L.C.
Partner: UNT Libraries Government Documents Department
open access

Inherently safe nuclear-driven internal combustion engines

Description: A family of nuclear driven engines is described in which nuclear energy released by fissioning of uranium or plutonium in a prompt critical assembly is used to heat a working gas. Engine performance is modeled using a code that calculates hydrodynamics, fission energy production, and neutron transport self-consistently. Results are given demonstrating a large negative temperature coefficient that produces self-shutoff of energy production. Reduced fission product inventory and the self-shutoff … more
Date: June 14, 1991
Creator: Alesso, P.; Chow, Tze-Show; Condit, R.; Heidrich, J.; Pettibone, J. & Streit, R.
Partner: UNT Libraries Government Documents Department
open access

D7 debris bed experiment - heat removal from a shallow, stratified UO/sub 2/-sodium particle bed. [In ACPR reactor]

Description: The D7 debris bed experiment is one in a series of experiments being conducted to investigate the coolability of fragmented reactor mterials. The D7 experiment is the second experiment which investigates heat removal from a stratified bed. The significance of particle stratification was demonstrated by the D6 experiment, which exhibited lower dryout powers of a factor of approximately two when compared to mixed beds. In addition to investigating a shallower bed as compared to the D6 experiment,… more
Date: January 1, 1982
Creator: Mitchell, G W
Partner: UNT Libraries Government Documents Department
open access

Recent operational history of the new Sandia Pulsed Reactor III (SPR III)

Description: The Sandia Pulsed Reactor III (SPR III) is a fast-pulse research reactor which was designed and built at Sandia Laboratories and achieved criticality in August 1975. The reactor is now characterized and is in an operational configuration. The core consists of 18 fuel plates (258 kg fuel mass) of fully enriched uranium alloyed with 10 wt.% molybdenum. It is arranged in an annular configuration with an inside diameter of 17.78 cm, an outside diameter of 29.72 cm, and a height of 35.9 cm. The reac… more
Date: January 1, 1977
Creator: Schmidt, T. R.; Estes, B. F. & Reuscher, J. A.
Partner: UNT Libraries Government Documents Department
open access

Dose levels and neutron reaction rates for HPRR and SHEBA

Description: The analysis shows good agreement between calculated and experimental values of the neutron doses at 6 meters, while the gamma-ray doses vary by 25%. For distances greater than 6 meters, there are larger differences between the calculated and experimental doses, which may be due to experimental uncertainties. The Henderson and ANSI-STD neutron and gamma-ray doses for the BARE-SHEBA, LS-HPRR and BARE-HPRR configurations are also displayed. At distances of 6 meters and greater, the neutron doses … more
Date: January 1, 1982
Creator: Renier, J. P.; Westfall, R. M. & Knight, J. R.
Partner: UNT Libraries Government Documents Department
open access

Measurement of the enthalpy and specific heat of a Be/sub 2/C-graphite-UC/sub 2/ reactor fuel material to 1980/sup 0/K

Description: The enthalpy and specific heat of a Be/sub 2/C-graphite-UC/sub 2/ composite nuclear fuel material were measured over the temperature range 300 to 1980/sup 0/K using differential scanning calorimetry and liquid argon vaporization calorimetry. The fuel material measured was developed at Sandia National Laboratories for use in pulsed test reactors. The material is a hot-pressed composite consisting of 40 vol % Be/sub 2/C, 49.5 vol % graphite, 3.5 vol % UC/sub 2/ and 7.0 vol % void. The specific he… more
Date: January 1, 1980
Creator: Roth, E.P.
Partner: UNT Libraries Government Documents Department
open access

Safety and licensing issues that are being addressed by the Power Burst Facility test programs. [PWR; BWR]

Description: This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant Accident tests, which comprised the original test program in the Power Burst Facility, are discussed. The resolution of these safety issues based on the results of the thirty-six tes… more
Date: January 1, 1980
Creator: McCardell, R. K. & MacDonald, P. E.
Partner: UNT Libraries Government Documents Department
open access

D5 debris bed experiment-extended post-dryout observations of a UO/sub 2/-sodium particle bed. [In ACPR reactor]

Description: The D5 experiment is the sixth in a series of debris bed coolability experiments. The principal objective of the experiment is to investigate debris bed behavior, for various sodium subcoolings, at temperatures exceeding 2100/sup 0/K. The experiment is scheduled for early February 1982.
Date: January 1, 1982
Creator: Gronager, J E
Partner: UNT Libraries Government Documents Department
open access

Critical commentary on dose-rate evaluations

Description: Survivors of Hiroshima and Nagasaki present a unique problem in dosimetry: the effects of radiation exposure may be inferred although the exposure itself is unknown. Experience with a replica of Little Boy demonstrates the difficulties of measuring dose rates, the problems of comparing measurements with calculations, and the inadequacy of the conventional standards that are used to calibrate dosimeters.
Date: January 1, 1984
Creator: Dowdy, E.J.; Malenfant, R.E. & Plassmann, E.A.
Partner: UNT Libraries Government Documents Department
open access

Neutron personnel dosimetry intecomparison studies

Description: The Dosimetry Applications Research (DOSAR) Group at the Oak Ridge National Laboratory (ORNL) has conducted sixteen Neutron Personnel Dosimetry Intercomparison Studies (PDIS) since 1974. During these studies dosimeters are mailed to DOSAR, exposed to low-level (typically in the 0.3 -- 5.0 mSv range) neutron dose equivalents in a variety of mixed neutron-gamma radiation fields, and then returned to the participants for evaluation. The Health Physics Research Reactor (HPRR) was used as the primar… more
Date: January 1, 1991
Creator: Sims, C.S.
Partner: UNT Libraries Government Documents Department
open access

Operational performance of the three bean salad control algorithm on the ACRR (Annular Core Research Reactor)

Description: Experimental tests on the Annular Core Research Reactor have confirmed that the Three-Bean-Salad'' control algorithm based on the Pontryagin maximum principle can change the power of a nuclear reactor many decades with a very fast startup rate and minimal overshoot. The paper describes the results of simulations and operations up to 25 MW and 87 decades per minute. 3 refs., 4 figs., 1 tab.
Date: January 1, 1991
Creator: Ball, R. M.; Madaras, J. J.; Trowbridge, F. R., Jr.; Talley, D. G. & Parma, E. J., Jr.
Partner: UNT Libraries Government Documents Department
open access

Enriched vs non-enriched vs non-fissile targets for pulsed spallation neutron sources

Description: Numerous options exist among alternatives for target material and design of the neutron producing target in pulsed spallation neutron sources. This report surveys the advantages, disadvantages and limitations of some of the alternatives, including discussions of neutron yields, delayed neutron backgrounds, source pulse widths, source-to-moderator coupling, materials performance, fabrication problems, safeguards and security and hazards questions. 5 refs., 5 figs., 2 tabs.
Date: January 1, 1990
Creator: Carpenter, J.M.
Partner: UNT Libraries Government Documents Department
open access

Theory and application of the coded aperture fuel motion detection system

Description: A fuel motion detection system based on coded aperture imaging has been developed for the Annular Core Research Reactor. Its configuration evolved after investigations were carried out to determine the required system capabilities. The reactor environment, developments in the theory of coded apertures for nuclear radiations and compatibility with prototypical geometries were considered. The system was fabricated and inserted into the ACRR where it has recorded the fuel motion from a single pin … more
Date: January 1, 1979
Creator: Kelly, J.G.; Stalker, K.T.; McArthur, D.A.; Chu, K.W. & Powell, J.E.
Partner: UNT Libraries Government Documents Department
open access

MELCOR simulation of the PBF (Power Burst Facility) severe fuel damage test 1-1

Description: This paper describes a MELCOR version 1.7.1 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) 1-1 test. The input data for the simulation was obtained from the SFD 1-1 Test Results Report and from SCDAP input. Results are presented for the transient two-phase interface level in the core, fuel and clad temperatures at various elevations in the fuel bundle, clad oxidation, hydrogen generation, fission product release, and heat transfer to the surrounding structures. Comparison… more
Date: January 1, 1989
Creator: Madni, I.K.
Partner: UNT Libraries Government Documents Department
open access

Blowdown mass flow measurements during the Power Burst Facility LOC-11C test

Description: An interpretation and evaluation of the two-phase coolant mass flow measurements obtained during Test LOC-11C performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL) are presented. Although a density gradient existed within the pipe between 1 and 6 s, the homogeneous flow model used to calculate the coolant mass flow from the measured mixture density, momentum flux, and volumetric flow was found to be generally satisfactory. A cross-sectional average dens… more
Date: January 1, 1979
Creator: Broughton, J. M. & MacDonald, P. E.
Partner: UNT Libraries Government Documents Department
open access

Design and proposed utilization of the Sandia Annular Core Research Reactor (ACRR)

Description: The Sandia ACRR became operational in 1978 and currently serves as the major in-pile fast reactor safety test facility for the US Nuclear Regulatory Commission. The ACRR is an upgrade of the Annular Core Pulse Reactor (ACPR) with the installation of a new flexible control system and a core of uniquely designed BeO-UO/sub 2/ fuel elements for increasing the neutron fluence in the experiment cavity. The reactor is now capable of driving multi-pin advanced reactor test fuel into vapor with a pulse… more
Date: January 1, 1979
Creator: Walker, J.V.; Reuscher, J.A. & Pickard, P.S.
Partner: UNT Libraries Government Documents Department
open access

Overview of the PBF test results. [PWR; BWR]

Description: The Thermal Fuels Behavior Program (TFBP) of EG and G Idaho conducts fuel behavior research in the Power Burst Facility (PBF) at INEL and at the Halden Reactor in Norway. The fuels behavior research in the PBF is directed toward providing a detailed understanding of the response of light water reactor (LWR) nuclear fuel assemblies to off-normal and hypothesized accident conditions. Single fuel rods and clusters of highly instrumented fuel rods are installed within a central test space of the PB… more
Date: January 1, 1980
Creator: Zeile, H.J.
Partner: UNT Libraries Government Documents Department
open access

A comparative study of STCP and SCDAP simulation of PBF SFD Test 1-1

Description: This paper presents the results of a detailed comparison of the Source Term Code Package (STCP) and the SCDAP computer codes for simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) test 1-1. The SCDAP code is mechanistic, and has been benchmarked against a wide range of severe accident data. The SFD 1-1 test was designed to simulate the heatup and resulting fuel damage in the upper half of a 3000-Mw(t) PWR core approximately 2 to 3 hours after initiation of a small break accid… more
Date: January 1, 1987
Creator: Yang, J. W. & Khatib-Rahbar, M.
Partner: UNT Libraries Government Documents Department
open access

PBF experimental program

Description: The fuels behavior research in PBF is directed towards providing a detailed understanding of the response of nuclear fuel assemblies to off-normal and hypothetical accident conditions. Single fuel rods and clusters of highly instrumented fuel rods are installed within a central test space of the PBF core for testing. The core can be operated in various modes to provide test conditions typical of accidents and off-normal conditions such as: (1) Power-Cooling-Mismatch (PCM) accidents; (2) Loss-of… more
Date: January 1, 1979
Creator: MacDonald, P. E. & Zeile, H. J.
Partner: UNT Libraries Government Documents Department
open access

New neutron simulation capabilities provided by the Sandia Pulse Reactor (SPR-III) and the Upgraded Annular Core Pulse Reactor (ACPR)

Description: The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on nuclear weapon systems and components. As such, the reactors are available to DOE and DOD agencies and their contractors responsible for the ra… more
Date: July 1, 1978
Creator: Choate, L.M. & Schmidt, T.R.
Partner: UNT Libraries Government Documents Department
open access

Rod bundle critical heat flux at low pressure

Description: A study of critical heat flux (CHF) in a close-packed bundle of electrically heated rods which simulated the closely spaced nuclear fuel rods of the Power Burst Facility (PBF) was performed. The study examined the effects that close rod spacing and rod bowing would have on CHF at low, near-atmospheric, pressure conditions similar to PBF conditions. The PBF nuclear reactor, which is used in the Nuclear Regulatory Thermal Fuels Behavior Program, has an open vessel and a driver core with forced up… more
Date: January 1, 1978
Creator: Wadkins, R. P.; Ambrosek, R. G. & Young, M. W.
Partner: UNT Libraries Government Documents Department
open access

Assessment of the influence of surface thermocouples on the behavior of nuclear fuel rods during a large break LOCA

Description: A second series of thermocouple effects tests (TC-3) is being conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). These tests are designed to evaluate the influence of external surface thermocouples on the behavior of nuclear fuel rods during a large break loss-of-coolant accident (LOCA) experiment, which includes partial or total rod rewet during blowdown. Questions have been raised with regard to possible effects of surface thermocouples on the the… more
Date: January 1, 1980
Creator: Yackle, T. R.
Partner: UNT Libraries Government Documents Department
open access

Film boiling behavior in a nine rod cluster

Description: Film boiling in a cluster geometry was investigated during a recent test conducted in the Power Burst Facility. Cluster information is necessary to assess the applicability of single rod experimental data used in developing light water reactor fuel rod behavior models. The nine-rod test, part of the Power-Cooling-Mismatch (PCM) Test Series, was designed to investigate the film boiling behavior of a central fuel rod surrounded by fuel rods that were also in the film boiling heat transfer regime.… more
Date: January 1, 1978
Creator: Sparks, D. T.; Stanley, C. J. & McCardell, R. K.
Partner: UNT Libraries Government Documents Department
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