34 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "21 Specific Nuclear Reactors And Associated Plants"  
Results: 1 - 24 next
open access

Test results on the dynamic testing of expansion type concrete anchors

Description: Tests were performed to determine the structural response of commercially available expansion type anchors for the FFTF when subjected to dynamic loadings similar to machine vibrations and earthquakes. The specimens were subjected to tension, shear, and combined shear-tension loads.
Date: December 1, 1974
Creator: Barron, B.; Rice, R. & Stephen, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Feasibility of leak-detection instrumentation for duplex-tube steam generator. [LMFBR]

Description: A literature search has been carried out to determine if current state-of-the-art for sodium vapor and water vapor detectors are feasible as leak detection instrumentation for the Westinghouse duplex-tube steam generator. A commercially available probe-type water vapor detector has been identified and a thermal ionization type sodium vapor detector, currently being developed by Westinghouse, has been selected as the reference sodium-vapor leak detector. Recommendations are made concerning the e… more
Date: January 1, 1974
Creator: Berkey, E. & Witkowski, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamic response of a linear elastic/linear strain-hardening thin ring. [LMFBR type reactors]

Description: In studying the dynamic response of fluid filled cylindrical shells to large internal pressure pulses, it would be advantageous to have a rapid method of computing the final deformed shape of the shell. In treating the dynamic response of liquid metal heat transport system to pressures generated by large sodium/water reactions, determinations of the structural response of various components is only a fraction of the information required to describe the entire event. The problem treated in this … more
Date: March 1, 1974
Creator: Carey, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of threshold velocities and correlation of high-frequency endurance limits for LMFBR heat-exchanger materials

Description: Jet impact erosion tests and high frequency fatigue tests were conducted for 2-1/4 Cr-1 Mo steel. Utilizing the relationship between the velocity of impact and number of impacts to produce visible erosion, the threshold velocities were determined as 220 and 140 fps at 10/sup 7/ and 10/sup 8/ cycles respectively. The relationship between the high frequency fatigue strength and the number of cycles to failure was determined at room temperature up to a maximum of 10/sup 9/ cycles. The high frequen… more
Date: February 1, 1974
Creator: Cavanaugh, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Wire-wrap bundle compression-characteristics study. Phase I. [LMFBR]

Description: An analytical computer comparison was made of the compression characteristics of proposed wire-wrap bundles. The study included analysis of 7- and 37-rod straight-start bundles (base configuration), and softened 37-rod configurations. The softened configurations analyzed were: straight-start with distributed wireless fuel rods, and the staggered wire-wrap start angles of 0/sup 0/-30/sup 0/-60/sup 0/ and 0/sup 0/-45/sup 0/-90/sup 0/. The compression of the bundle simulates the bundle-to-channel … more
Date: June 1, 1974
Creator: Chertock, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Permeability and solubility of gases for FFTF/CRBRP cover-gas-seal materials

Description: The permeability (anti P) and diffusion coefficient (D) of the gases H/sub 2/, Ar, Kr and Xe have been measured in certain elastomer materials of interest to the FFTF/CRBRP Cover Seal Program. These elastomers include Buna N, Buna S, Butyl Rubber, ethylene-propylene polyacrylic, polyurethane and silicone. Measurements were made over the temperature range 100 to 300/sup 0/F. Data for the permeability and diffusion coefficient for these gases in the above elastomer materials are given. The method… more
Date: January 1, 1974
Creator: Darnell, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LMFBR technology. FFTF cover-gas leakage calculation

Description: The FFTF LMFBR is intended to have a near zero release of radioactive gases during normal reactor operation with 1% failed fuel. This report presents calculations which provide an approximation of these cover gas leakages. Data from ongoing static and dynamic seal leak tests at AI are utilized. Leakage through both elastomeric and metallic seals in all sub-assemblies and penetrations comprising the reactor cover gas containment during reactor operation system are included.
Date: June 17, 1974
Creator: Deboi, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seal, dynamic inflatable, development test, installation and removal of

Description: This specification establishes the requirements and procedures (using epoxy adhesive) for the installation and removal of the dynamic inflatable test seal for the Fast Flux Test Facility (FFTF), In-Vessel Handling Machine (IVHM) Reactor Refueling Plug (RRP).
Date: June 10, 1974
Creator: Deboi, H.H. & Ferrante, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SIEX: a correlated code for the prediction of Liquid Metal Fast Breeder Reactor (LMFBR) fuel thermal performance

Description: The SIEX computer program is a steady state heat transfer code developed to provide thermal performance calculations for a mixed-oxide fuel element in a fast neutron environment. Fuel restructuring, fuel-cladding heat conduction and fission gas release are modeled to provide assessment of the temperatures. Modeling emphasis has been placed on correlations to measurable quantities from EBR-II irradiation tests and the inclusion of these correlations in a physically based computational scheme. SI… more
Date: January 1, 1974
Creator: Dutt, D.S. & Baker, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Superheater duplex tube steady-state analysis demonstrating 2-1/4 Cr-1Mo as an acceptable reference material

Description: Preliminary analysis of the proposed superheater duplex tube (2-1/4Cr-1Mo) has been performed for the steady state condition. All locations evaluated were found to satisfy the criteria set forth in Code Case 1331-8 Section 4.3 and 5.2b.
Date: June 1, 1974
Creator: Flury, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ex-vessel core catcher design requirements and preliminary concepts evaluation. [LMFBR]

Description: As part of the overall study of the consequences of a hypothetical failure to scram following loss of pumping power, design requirements and preliminary concepts evaluation of an ex-vessel core catcher (EVCC) were performed. EVCC is the term applied to a class of devices whose primary objective is to provide a stable subcritical and coolable configuration within containment following a postulated accident in which it is assumed that core debris has penetrated the Reactor Vessel and Guard Vessel… more
Date: June 14, 1974
Creator: Friedland, A.J. & Tilbrook, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium removal, storage, and requalification of components. [LMFBR]

Description: The objectives of this program are to devise, develop, test, and evaluate techniques for sodium removal and storage of test specimens and components, and to expand and refine, by test and analysis, the sodium removal and storage techniques and procedures for use in processing typical LMFBR components.
Date: January 1, 1974
Creator: Gallegos, A.; Shimazaki, T. & Oliva, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MSG test report: removal of residual sodium. [LMFBR]

Description: This report presents the results of cleaning activities performed to remove residual sodium from the AI Modular Steam Generator. A description of the cleaning loop, cleaning procedure, results, and visual inspection are included.
Date: March 8, 1974
Creator: Harty, R.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-fire control by space isolation with nitrogen flooding: FFTF proof test F2

Description: Sodium fire protection by space isolation with nitrogen flooding was evaluated by performing a large-scale sodium fire test within a mockup of an FFTF secondary sodium system pipeway. The full scale (3350 ft/sup 3/) mockup was initially filled with air and its leak tightness set to correspond to that expected in an actual FFTF pipeway. The basis for specifying the rate of nitrogen flood gas is discussed ad the experimental verification provided. Nitrogen flooding was activated 15 minutes after … more
Date: June 1, 1974
Creator: Hilliard, R.K. & Muhlestein, L.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel-transfer machine-component test. Progress report GFY 1974

Description: The objectives of this program are to conduct the development and testing necessary to produce reliable and adequate handling devices for core components for an LMFBR plant utilizing under-the-shield refueling and reactor vessel cover rotating plugs. Component performance in the following three specific areas of concern will be investigated: (1) a reliable rising stem, vertical motion, in-vessel transfer machine (IVTM) for use in an under-the-shield refueling system with multiple rotating react… more
Date: January 1, 1974
Creator: Kellogg, L. G.; Moody, E. & Jones, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plan for testing the IVHM inflatable seal to CRBRP conditions

Description: The FFTF-IVHM inflatable seal was tested, and met all requirements. The CRBRP inflatable seals are expected to operate at higher linear velocities and greater distortions, and accumulate more travel, than the IVHM installation. This document describes tests on the IVHM design to CRBRP conditions.
Date: January 1, 1974
Creator: Kurzeka, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

1 - FFTF-LMFBR seal test program, July-September 1974

Description: The objectives of the general seal test program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross-section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmenta… more
Date: January 1, 1974
Creator: Kurzeka, W. & Oliva, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium technology. 1 - FFTF support work: friction tests, January-March 1974

Description: The objective of this program is to conduct friction screening tests in an environment of high-temperature, high-purity liquid sodium or sodium vapor to: (1) develop backup materials, processes, and vendors for core component wear pads, (2) investigate material treatments and coatings for improvement of wear behavior of common LMFBR structural materials, (3) evaluate weld-deposited hardfacings and/or prefabricated bearing materials for use in long-term, high-temperature, high-fluence regions, (… more
Date: January 1, 1974
Creator: Kurzeka, W. J.; Oliva, R. M. & Horton, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cover gas seals. 11 - FFTF-LMFBR seal-test program, January-March 1974

Description: The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configuration provide acceptable fission product and cover gas retention capabilities at LMFBR Clinch River Plant operating environmental conditions other than radiation, a… more
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R. & Welch, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Task 11: FFTF-LMBBR seal test program

Description: The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment; (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions othe… more
Date: May 1, 1974
Creator: Kurzeka, W.; Oliva, R. & Welch, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cover gas seals: FFTF-LMFBR seal test program

Description: The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor-inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other … more
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R.; Welch, T.S. & Shimazaki, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium removal disassembly and examination of the Fermi secondary sodium pump

Description: The Fermi secondary pump is a centrifugal single stage design. The pump had been operated more than 42,000 hours between 450 and 800/sup 0/F. Sodium was drained from the pump in 1973 and the system was back filled with carbon dioxide. The pump was fabricated for 2.25 Cr-1 Mo Croloy steel. Prior to cleaning the pump was inerted and heated with 150/sup 0/F nitrogen using the pump casing as the containment vessel. The water-vapor-nitrogen process was used in three increasing stages of water concen… more
Date: August 1, 1974
Creator: Maffei, H. P.; Funk, C. W. & Ballif, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen