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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

Post-test examination observations for the W-2 SLSF experiment. [Sodium Loop Safety Facility]

Description: Gamma scanning measurements revealed that the axial power profile in these test trains was more peaked than expected based on pretest calculations and critical facility measurements. These results implied that the thermal flux incident on the test assembly was greater than expected, which was manifested in highly skewed and extensive fuel melting zones in the outer pin fuel pellets. Observations indicated that the extent of fuel melting near the midplane exceeded 90% of the pellet radius in som… more
Date: September 1, 1983
Creator: Pitner, A. L.; Smith, D. E. & Culley, G. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

VISA: a computer code for predicting the probability of reactor pressure-vessel failure. [PWR]

Description: The VISA (Vessel Integrity Simulation Analysis) code was developed as part of the NRC staff evaluation of pressurized thermal shock. VISA uses Monte Carlo simulation to evaluate the failure probability of a pressurized water reactor (PWR) pressure vessel subjected to a pressure and thermal transient specified by the user. Linear elastic fracture mechanics are used to model crack initiation and propagation. parameters for initial crack size, copper content, initial RT/sub NDT/, fluence, crack-in… more
Date: September 1, 1983
Creator: Stevens, D. L.; Simonen, F. A.; Strosnider, Jr., J.; Klecker, R. W.; Engel, D. W. & Johnson, K. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical discharge of initially subcooled water through slits. [PWR; BWR]

Description: This report describes an experimental investigation into the critical flow of initially subcooled water through rectangular slits. The study of such flows is relevant to the prediction of leak flow rates from cracks in piping, or pressure vessels, which contain sufficient enthalpy that vaporization will occur if they are allowed to expand to the ambient pressure. Two new analytical models, which allow for the generation of a metastable liquid phase, are developed. Experimental results are compa… more
Date: September 1, 1983
Creator: Amos, C N & Schrock, V E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear criticality safety training: guidelines for DOE contractors

Description: The DOE Order 5480.1A, Chapter V, Safety of Nuclear Facilities, establishes safety procedures and requirements for DOE nuclear facilities. This guide has been developed as an aid to implementing the Chapter V requirements pertaining to nuclear criticality safety training. The guide outlines relevant conceptual knowledge and demonstrated good practices in job performance. It addresses training program operations requirements in the areas of employee evaluations, employee training records, traini… more
Date: September 1, 1983
Creator: Crowell, M.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mechanistic prediction of fission product release under normal and accident conditions: key uncertainties that need better resolution

Description: A theoretical model has been used for predicting the behavior of fission gas and volatile fission products (VFPs) in UO/sub 2/-base fuels during steady-state and transient conditions. This model represents an attempt to develop an efficient predictive capability for the full range of possible reactor operating conditions. Fission products released from the fuel are assumed to reach the fuel surface by successively diffusing (via atomic and gas-bubble mobility) from the grains to grain faces and… more
Date: September 1, 1983
Creator: Rest, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Laboratory-scale sodium-carbonate aggregate concrete interactions. [LMFBR]

Description: A series of laboratory-scale experiments was made at 600/sup 0/C to identify the important heat-producing chemical reactions between sodium and carbonate aggregate concretes. Reactions between sodium and carbonate aggregate were found to be responsible for the bulk of heat production in sodium-concrete tests. Exothermic reactions were initiated at 580+-30/sup 0/C for limestone and dolostone aggregates as well as for hydrated limestone concrete, and at 540+-10/sup 0/C for dehydrated limestone co… more
Date: September 1, 1983
Creator: Westrich, H. R.; Stockman, H. W. & Suo-Anttila, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

Description: This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record … more
Date: September 1, 1983
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SP-100 Program: space reactor system and subsystem investigations

Description: For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. This report summarizes the nuclear safety review/approval process that will be required for a space reactor system. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the ty… more
Date: September 30, 1983
Creator: Harty, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamics of tubes in fluid with tube-baffle interaction

Description: Three series of tests are performed to evaluate the effects of tube to tube-support-plate (TSP) clearance on tube dynamic characteristics and instability phenomena for tube arrays in crossflow. Test results show that, for relatively large clearances, tubes may possess TSP-inactive modes in which the tubes rattle inside some of the tube-support-plate holes, and that the natural frequencies of TSP-inactive modes are lower than those of TSP-active modes, in which the support plates provide knife-e… more
Date: September 1, 1983
Creator: Chen, S.S.; Jendrzejczyk, J.A. & Wambsganss, M.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Intermediate-scale tests of sodium interactions with calcite and dolomite aggregate concretes. [LMFBR]

Description: Two intermediate-scale tests were performed to compare the behavior of calcite and dolomite aggregate concretes when attacked by molten sodium. The tests were performed as part of an interlaboratory comparison between Sandia National Laboratories and Hanford Engineering Development Laboratories. Results of the tests at Sandia National Laboratories are reported here. The results show that both concretes exhibit similar exothermic reactions with molten sodium. The large difference in reaction vig… more
Date: September 1, 1983
Creator: Randich, E. & Acton, R.U.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron and gamma-ray measurements on the LANL Little Boy Comet Assembly

Description: We measured the neutron and gamma-ray dose rates at various distances from the Little Boy Comet Assembly at Los Alamos National Laboratory (LANL), Los Alamos, New Mexico on April 28 and 29, 1983. The distances selected varied from 350 ft to 1860 ft from the assembly, with the latter point being located at the edge of the mesa overlooking Pajarito Canyon. We varied the power levels for the various runs but we have normalized all of them to a single power-level. We also made corrections for the v… more
Date: September 1, 1983
Creator: Hankins, D.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Data integrity review of Three Mile Island Unit 2. Hydrogen burn data. Volume 3

Description: About 10 hours after the March 28, 1979 loss-of-coolant accident began at Three Mile Island Unit 2 (TMI-2), a hydrogen burn occurred inside the Reactor Building. This report reviews and presents data from 16 channels of resistance temperature detectors (RTDs), 2 steam generator pressure transmitters, 16 Reactor Building pressure switches, 2 channels of Reactor Building pressure measurements, and measurements of Reactor Building hydrogen, oxygen, and nitrogen concentrations with regard to their … more
Date: September 1, 1983
Creator: Jacoby, J. K.; Nelson, R. A.; Nalezny, C. L. & Averill, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim report on the state-of-the-art of solid-state motor controllers. Part 4. Failure-rate and failure-mode data

Description: An assessment of the reliability of solid-state motor controllers for nuclear power plants is made. Available data on failure-rate and failure-mode data for solid-state motor controllers based on industrial operating experience is meager; the data are augmented by data on other solid-state power electronic devices that are shown to have components similar to those found in solid-state motor controllers. In addition to large nonnuclear solid-state adjustable-speed motor drives, the reliability o… more
Date: September 1, 1983
Creator: Jaross, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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