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in subjects: "Vapor Generators 210500* -- Power Reactors, Breeding"

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CRBRP flow induced vibration program

The program to assure the structural adequacy of CRBRP components during its planned 30 years of operation is described. The program includes (1) an assessment of reactor components relative to their susceptibility to FIV, (2) designing to minimize component excitation due to FIV, (3) scale model tests to measure structural response during simulated operating conditions and (4) preoperational tests. An overview of the CRBRP test program is described. Additionally, details of scale model testing… more

Date: January 1, 1977

Creator: Novendstern, E H; Grochowski, F A; Yang, T M; Ryan, J A & Mulcahy, T M

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Dynamic inelastic response of thick shells using endochronic theory and the method of nearcharacteristics. [LMFBR]

The endochronic theory of plasticity originated by Valanis has been applied to study the axially symmetric motion of circular cylindrical thick shells subjected to an arbitrary pressure transient applied at its inner surface. The constitutive equations for the thick shells have been obtained. The governing equations are then solved by means of the near-characteristics method.

Date: August 1, 1976

Creator: Lin, H. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Test of the second model of the GCFR steam generator cavity closure plug

As part of its participation in the program to develop a 300 MW(e) gas-cooled fast reactor (GCFR) demonstration power plant, the Oak Ridge National Laboratory (ORNL) is conducting a series of structural model tests. One of the tasks of the ORNL effort provides for the design, analysis and/or testing of small-scale models of the PCRV penetration closure plugs. The principal objectives are to determine structural response of the plugs to normal operating pressures and to substantial overpressuriz… more

Date: January 1, 1979

Creator: Callahan, J. P.; Robinson, G. C. & Dodge, W. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

GCFR steam generator conceptual design

The gas-cooled fast reactor (GCFR) steam generators are large once-through heat exchangers with helically coiled tube bundles. In the GCFR demonstration plant, hot helium from the reactor core is passed through these units to produce superheated steam, which is used by the turbine generators to produce electrical power. The paper describes the conceptual design of the steam generator. The major components and functions of the design are addressed. The topics discussed are the configuration, ope… more

Date: January 1, 1980

Creator: Holm, R. A. & Elliott, J. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Vibration tests of a full scale water model of a Clinch River steam generator module

Cross and parallel flow induced vibrations were measured in a shortened full scale model of the CRBRP steam generators using water as the working fluid. M easurements were made on five selected tubes, some of which fit through oversize tube support holes. Power spectral density plots were made of vibration parameters at selected locations. Maximum displacement was about 3 mils and occurred at the lower frequencies. The maximum vibrational stress was calculated to be 2000 psi. Measurements of vo… more

Date: unknown

Creator: Durand, R. E.; Gabler, M. J.; Weinberg, L. & Yang, T. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

SCTI chemical leak detection test plan

Tests will be conducted on the CRBRP prototype steam generator at SCTI to determine the effects of steam generator geometry on the response of the CRBRP chemical leak detection system to small water-to-sodium leaks in various regions of the steam generator. Specifically, small injections of hydrogen gas (simulating water leaks) will be made near the two tubesheets, and the effective transport times to the main stream exit and vent line hydrogen meters will be measured. The magnitude and time ch… more

Date: October 12, 1981

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Leak location in a double wall tube steam generator. [LMFBR]

An experimental and analytical study was made of an acoustic location system for use with double wall tube steam generators. A conceptual design of an acoustic leak location system was developed. This system has the potential for detecting the third fluid gas escaping from the annulus between the double walled tubes into the sodium. The acoustic system uses an array of accelerometers mounted onto the outside of the steam generator vessel. Electronic circuitry selects a number of accelerometers,… more

Date: January 1, 1980

Creator: Greene, D. A.; McMurtrie, K. R. & Gaubatz, D. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Steam generator model for real-time analysis

Plant safety as well as plant availability can significantly be improved if functions such as data validation, plant state verification and fault identification are automated. This can be achieved if computers are utilized, with plant models that run in real-time, for continuous on-line plant information processing and analysis. Such models can also be used in plant simulators for operator training. This paper presents a model for real-time analysis of a once-through liquid-metal fast breeder r… more

Date: January 1, 1985

Creator: Tzanos, C.P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

PCRV design and pressure limits for GCFR

This paper presents a review of PCRV design with special emphasis on pressure limitations for large GCFRs. Discussion on major factors affecting PCRV design includes tendon layout requirements; location and arrangement of major components, especially the steam generators, auxiliary heat exchangers, and main and auxiliary circulators; and the balance-of-plant interface requirements. Joint PCRV and containment design efforts are required to evaluate the impact of the horizontal circulator cavity … more

Date: July 1, 1979

Creator: Chow, G.S. & Koopman, D.C.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

CRBRP modular steam generator tube-to-tubesheet and shell-closure welding

The original Modular Steam Generator (MSG), whiand inh was designed, built, and tested by the Energy Systems Group (ESG) of Rockwell International, was a departure from conventional boilers or heat exchangers. The design was a hockeystick concept - the upper section of the generator is curved 90/sup 0/. Factors affecting operating parameters were considered and incorporated in the original MSG design. The MSG was fully instrumented and functionally tested at the Energy Technology Engineering Ce… more

Date: January 1, 1982

Creator: Viri, D.P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Interim report on the feasibility study of acoustic leak location for WTD steam generators. [LMFBR]

This interim report summarizes the current status of a feasibility study of an acoustic leak location system for two Westinghouse-Tampa Division (WTD) double-wall steam generators. The primary WTD design requirement is that a leak of helium gas into sodium be located to within a cluster of seven tubes at hot standby conditions. The report documents the results of an extensive analytical assessment, outlines areas of concern resulting from the analyses which will require experimental validation,… more

Date: March 1, 1979

Creator: Greene, D. A. & McMurtrie, K. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Multidimensional numerical modeling of heat exchangers. [LMFBR]

A comprehensive, multidimensional, thermal-hydraulic model is developed for the analysis of shell-and-tube heat exchangers for liquid-metal services. For the shellside fluid, the conservation equations of mass, momentum, and energy for continuum fluids are modified using the concept of porosity, surface permeability and distributed resistance to account for the blockage effects due to the presence of heat-transfer tubes, flow baffles/shrouds, the support plates, etc. On the tubeside, the heat-t… more

Date: January 1, 1982

Creator: Sha, W.T.; Yang, C.I.; Kao, T.T. & Cho, S.M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

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

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.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Evaluation of exposure conditions for the water-side corrosion test of a sodium heated steam generator evaporator model employing a duplex tube (2160 hours at critical heat flux - phase III SSGM tests). [LMFBR]

This report describes the specialized corrosion test water steam loop, test procedures, test conditions, and test results. A complete water chemistry and thermal hydraulic performance history is given and evaluated for the Phase III test program. The movement of the dryout location and the heat flux variations in pre- and post-critical heat flux regions are documented and analyzed. On seven occasions during the course of the test program to date, the operating conditions drifted from the CHF re… more

Date: December 1, 1975

Creator: Waszink, R. P.; Hwang, J. Y. & Efferding, L. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Selection of transition leak size for LLTR series II test A-4. [LMFBR]

The objective of this report is to provide the basis for the selection of this transition leak size for testing in the LLTR. This test, designated as Test A-4, is of particular interest because, of all the larger nonflame-jet-type-leaks, it has the longest dwell time in the vessel before the rupture disc blows, thus terminating the IHTS pressure rise. Its potential for generating secondary leaks is considered high. It is easy to postulate the generation of such a leak starting with small leak w… more

Date: March 1, 1979

Creator: Roberts, J.M. & Quintana, L.M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Design of the US-CRBRP sodium/water reaction pressure relief system

Protection against intermediate sodium system overpressure from the sodium/water reaction associated with large leaks within the CRBRP Steam Generators is provided by the sodium/water reaction pressure relief system (SWRPRS). This system consists of rupture disks connected to the intermediate sodium piping adjacent to the inlet to the superheater and outlet from the evaporator modules. The rupture discs relieve into piping that leads to reaction produce separator tanks, which in turn are vented… more

Date: January 1, 1976

Creator: Kruger, G. B.; Murdock, T. B.; Rodwell, E. & Sane, J. O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A method for pressure-pulse suppression in fluid-filled piping

A simple, nondestructive method to suppress pressure pulses in fluid-filled piping was proposed and theoretically analyzed earlier. In this paper, the proposed method is verified experimentally. The results of experiments performed for the range of parameters of practical importance indicated that the attenuation of pressure pulses was in accordance with the theoretical predictions. This paper describes the experimental setup and the test models of the proposed pulse suppression devices and dis… more

Date: January 1, 1990

Creator: Shin, Y.W.; Bielick, E.F. (Argonne National Lab., IL (USA)); Wiedermann, A.H. (IIT Research Inst., Chicago, IL (USA)) & Ockert, C.E. (USDOE, Washington, DC (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Transient simulation of a helical-coil sodium/water steam generator

The MINET (Momentum Integral Network) code heat exchanger model was used to analyze transient test data provided by PNC of Japan. Testing of the MINET model is part of a larger effort to facilitate and validate the use of the SSC/MINET code for MONJU plant transient analysis. In MINET, a heat exchanger is modeled using one or more representative tubes, with each tube consisting of the fluid inside the tube, the tube wall, and the fluid outside that is associated with the tube. The heat exchange… more

Date: January 1, 1982

Creator: Van Tuyle, G.J. & Iwashita, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Ultrasonic inspection for wastage in the LMFBR steam generator due to sodium--water reactions

As part of a program to study the results of large sodium-water reactions in the LMFBR Steam Generator, a boreside ultrasonic inspection device was developed to measure the wall thickness and diameter of the 2-/sup 1///sub 4/Cr-1 Mo, 0.397 in. I.D. steam tubes. The reaction was created in a near prototype steam generator by guillotine-type rupture of a steam tube, while the generator was at operating conditions. Wastage occurred on the surrounding tubes due to the high temperature reaction. The… more

Date: January 1, 1977

Creator: Neely, H. H. & Renger, Lee

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Field radiography using 100 Ci of Co-60 without interrupting adjacent manufacturing operations

Radiography is the primary method of Nondestructive Examination recognized by the ASME B and PV Code as providing objective evidence of volumetric examination of the pressure boundary welds that are present in the Clinch River Breeder Reactor Program (CRBRP) Steam Generator. In order to support the steam generator production schedule, the radiographic examinations must be performed without interrupting any other manufacturing or inspection operations taking place within a 20-ft radius from the … more

Date: January 1, 1979

Creator: Donnelly, C.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

GCFR development status report

This report describes the major design features of the gas-cooled fast breeder reactor being developed in the United States principally at General Atomic Company. The report gives the general design strategy and highlights the design features of the reactor core and the nuclear steam supply components. It describes the design results on plant safety and licensing.

Date: May 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Critical heat flux and transition boiling characteristics for a sodium-heated steam generator tube for LMFBR applications

An experimental program was conducted to characterize critical heat flux (CHF) in a sodium-heated steam generator tube model at a proposed PLBR steam generator design pressure of 7.2 MPa. Water was circulated vertically upward in the tube and the heating sodium was flowing counter-current downward. The experimental ranges were: mass flux, 110 to 1490 kg/s.m/sup 2/ (0.08 to 1.10 10/sup 6/ lbm/h.ft/sup 2/); critical heat flux, 0.16 to 1.86 MW/m/sup 2/ (0.05 to 0.59 10/sup 6/ Btu/h.ft/sup 2/); and… more

Date: April 1, 1977

Creator: Wolf, S. & Holmes, D. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

US GCFR demonstration plant design

A general description of the US GCFR demonstration plant conceptual design is given to provide a context for more detailed papers to follow. The parameters selected for use in the design are presented and the basis for parameter selection is discussed. Nuclear steam supply system (NSSS) and balance of plant (BOP) component arrangements and systems are briefly discussed.

Date: May 1, 1980

Creator: Hunt, P. S. & Snyder, H. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department