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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. Under these assumed conditions a set of functional requirements were developed for an EVCC and several concepts were evaluated. The studies were specifically directed toward the FFTF design considering the restraints imposed by the physical design and construction of the FFTF plant.
Date: June 14, 1974
Creator: Friedland, A.J. & Tilbrook, R.W.
Partner: UNT Libraries Government Documents Department

ZrH-reactor-technology program. Progress report, April-June 1974

Description: The report on the 2 kW(e) reactor-organic Rankine system was drafted. This report details the design parameters of a minimum weight, 2 kW(e) reactor-organic Rankine system. The system is designed for 5 years unattended life in space. The reactor produces 16.2 kW of thermal power with a NaK outlet temperature of 800/sup 0/F and a 200/sup 0/F ..delta..T. The reactor contains 19 fuel elements, 1.25'' in diameter by 10'' long, hydrided to an N/sub H/ of 6.35. The terrestrial applications effort was oriented towards the establishment of the feasibility of utilizing the zirconium hydride reactor technology in a subsea application for supplying electrical power to deep water, and other environmentally severe, oil well installations. The overall system concept is shown. The power system is composed of three basic modules (i.e., a reactor module, a generator module, and a heat rejection system) mounted on a barge. The barge is then towed to the installation site and submerged to mate with a previously installed seafloor foundation. An assembly/disassembly sequence was drafted detailing the steps required to assemble the reactor module and to disassemble it after 4 years of operations.
Date: July 12, 1974
Partner: UNT Libraries Government Documents Department

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 than radiation, and (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels.
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R.; Welch, T.S. & Shimazaki, T.
Partner: UNT Libraries Government Documents Department

Cold trap requirements for PHTS and IHTS sodium purification

Description: Cold trap requirements for the Primary Heat Transfer System (PHTS) and the Intermediate Heat Transfer System (IHTS) are defined. The bases for these requirements are (1) maintaining concentrations of oxygen and hydrogen within given limits, (2) controlling the transport of tritium by coprecipitating it in cold traps together with hydrogen, and (3) providing the necessary volume capacity for collecting impurities. It is concluded that the 60 gpm, FFTF Type I, NaK cooled, cold trap will satisfy the PHTS requirements. For each of the IHTS loops a single, 60 gpm, cold trap is required; and an aircooled trap similar to the FFTF Type I design except for a 3-foot longer crystallizer section has been chosen for this service.
Date: May 31, 1974
Creator: Sletten, H.L.
Partner: UNT Libraries Government Documents Department

Concept and preliminary design of double tubesheet connector region for design and steady-state conditions. [LMFBR]

Description: In this analysis the structural integrity of the double tubesheet connector for the LMFBR demonstration plant steam generator is investigated for design and steady state conditions. Although the evaporator and superheater are to be interchangeable, only the steam outlet end of the evaporator is investigated. This was selected because the mean temperature differences between the tubesheets, tubes and connector are largest here at steady state, thus yielding the highest thermal loads. Combined with the thermal loads are superheater pressures in order to also use the highest mechanical loads. Although this is a conservative approach for the evaporator, the superheater must be analyzed separately at a later date in order to assure interchangeability. Evaluation of the results is based upon ASME Code Case 1331-8.
Date: June 1, 1974
Creator: Rinne, W.A.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

1 - FFTF-LMFBR seal test program, July-Septeember 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 environmental conditions other than radiation, (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels, and (4) publish a Design Guide for reactor seals along with Ordering Data. Test results for the quarter are presented.
Date: January 1, 1974
Creator: Kurzeka, W. & Oliva, R.
Partner: UNT Libraries Government Documents Department

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 experimental studies required to adapt the selected instrumentation to steam-generator plant applications. Proposed future instrumentation development programs are also identified.
Date: January 1, 1974
Creator: Berkey, E. & Witkowski, R.E.
Partner: UNT Libraries Government Documents Department

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 frequency endurance limit at room temperature was determined to be approximately 32,000 psi for 10/sup 8/ cycles. In addition, the ratio of high frequency fatigue strength to water hammer stress for erosion inception was also obtained as 2.75. 5 figures.
Date: February 1, 1974
Creator: Cavanaugh, J.
Partner: UNT Libraries Government Documents Department

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 interference at end-of-life conditions at which high differential swelling between the channel and bundle has been predicted. The computer results do not include the so-called dispersion effects. The effects of other variables such as pitch length, creep, axial variations in swelling, and degree of swelling were not studied. These analytic studies give an indication of trends only. No credence should be given to specific quantitative load or deflection results quoted in this report.
Date: June 1, 1974
Creator: Chertock, A.J.
Partner: UNT Libraries Government Documents Department

Preliminary thermal/hydraulic sizing calculations for duplex tube evaporator/superheater (interchangeable units). Revision 1

Description: This is a preliminry thermal/hydraulic report reflecting work under Subtask 6.2 of Ref. 1.1. This report is an extension of the previous thermal/hydraulic design report. Parts of this report have been transmitted to GE. The detailed design basis, listed by source, is given. Additional details are discussed.
Date: June 1, 1974
Creator: Waszink, R.P.; Hwang, J.Y. & Efferding, L.E.
Partner: UNT Libraries Government Documents Department

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. SIEX is completely modular in construction allowing the user options for material properties and correlated models. Required code input is limited to geometric and environmental parameters, with a ``consistant`` set of material properties and correlated models provided by the code. The development of physically based correlations to model certain of the phenomana has resulted in a computer program which provides reliable estimates of thermal performance characteristics, yet requires a small amount of core storage and computer running time.
Date: January 1, 1974
Creator: Dutt, D.S. & Baker, R.B.
Partner: UNT Libraries Government Documents Department

Once-through steam generator (OTSG) materials and water chemistry. [PWR]

Description: Materials and water chemistry research results associated with the development of the Oconee-1 Reactor steam generator are presented. A summary of water chemistry data acquired during preoperational testing and power operation to date is also included. These data confirm the operational practicality of the nuclear once-through concept using volatile water treatment and high purity condensate demineralized feedwater.
Date: January 1, 1974
Creator: Pocock, F.J. & Levstek, D.F.
Partner: UNT Libraries Government Documents Department

Sodium technology: 1-FFTF support work, friction tests

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, (4) evaluate bearing materials with a low potential for change in surface composition due to corrosion or mass transfer effects, and (5) develop statistical confidence in friction values for selected material combinations.
Date: January 1, 1974
Creator: Oliva, R.M. & Horton, P.
Partner: UNT Libraries Government Documents Department

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, (4) evaluate bearing materials with a low potential for change in surface composition due to corrosion or mass transfer effects, and (5) develop statistical confidence in friction values for selected material combinations.
Date: January 1, 1974
Creator: Kurzeka, W.J.; Oliva, R.M. & Horton, P.
Partner: UNT Libraries Government Documents Department

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 other than radiation; and (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels.
Date: May 1, 1974
Creator: Kurzeka, W.; Oliva, R. & Welch, F.
Partner: UNT Libraries Government Documents Department

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. The AI program in FY 1974 has concentrated on three major tasks: (1) Sodium Removal and Storage, (2) Bag Handling, and (3) Sodium Removal Process Development.
Date: May 1, 1974
Creator: Oliva, R.M. & Welch, F.H.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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, and (3) develop improved seals and seal technology for the LMFBR Clinch River Plant to support the national objective to reduce all atmospheric contaminations to low levels.
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R. & Welch, F.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

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 reactor vessel covers, (2) and ex-vessel transfer machine (EVTM) for off-line removal of fuel from the reactor in-vessel storage, and (3) ancillary fuel handling equipment, such as auxiliary handling machines (AHM), floor valves, and core component service equipment.
Date: January 1, 1974
Creator: Kellogg, L. G.; Moody, E. & Jones, C. E.
Partner: UNT Libraries Government Documents Department