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in subjects: "Reactor Fueling"

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Startup and Initial Testing of SM-1 Core II With Special Components

The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium … more

Date: February 28, 1962

Creator: Moote, F. G. & Schrader, E. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fueling of tandem mirror reactors

This paper summarizes the fueling requirements for experimental and demonstration tandem mirror reactors (TMRs), reviews the status of conventional pellet injectors, and identifies some candidate accelerators that may be needed for fueling tandem mirror reactors. Characteristics and limitations of three types of accelerators are described; neutral beam injectors, electromagnetic rail guns, and laser beam drivers. Based on these characteristics and limitations, a computer module was developed fo… more

Date: January 1, 1985

Creator: Gorker, G. E. & Logan, B. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

THE FERRITE BIASING SYSTEM FOR THE RADIO FREQUENCY CAVITIES OF THE PRINCETON-PENNSYLVANIA 3 Bev PROTON SYNCHROTRON

A description is given of the ferrite biasing system for the four tuned radio frequency cavities of the synchrotron. Each ferrite loaded double cavity has a single turn bias winding which is driven to a peak current of 13,500 amperes by a push-pull transformer arrangement. There is automatic tap changing of the transformer to accommodate the variable impedance load (for power considerations). The programming and frequency response of the system have to be such that each cavity can operate as th… more

Date: August 29, 1962

Creator: Rees, G.H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962

Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. S… more

Date: July 1, 1962

Creator: Motte, F. G.; Best, W. C. & Kortheuer, J. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Personnel Radiation Exposure in HTGR Plants

Occupational radiation exposures in high-temperature gas-cooled reactor (HTGR) plants were assessed. The expected rate of dose accumulations for a large HTGR steam cycle (HTGR-SC) unit is 0.07 man-rem/MW(e)y, while the design basis is 0.17 man-rem/MW(e)y. The comparable figure for actual light water reactor (LWR) experience is 1.3 man-rem/MW(e)y. The favorable HTGR occupational exposure is supported by results from the Peach Bottom Unit No. 1 HTGR and Fort St. Vrain HTGR plants and by operating… more

Date: January 1, 1980

Creator: Su, S. & Engholm, B. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

REACTOR THEORY DEVELOPMENT PROGRAM FOR ABWR. Annual Progress Report, October 1, 1959-September 30, 1960

No Description Available.

Date: January 1, 1960

Creator: Newburg, E A & Noderer, L C

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Results of hydrogen pellet injection into ISX-B

High speed pellet fueling experiments have been performed on the ISX-B device in a new regime characterized by large global density rise in both ohmic and neutral beam heated discharges. Hydrogen pellets of 1 mm in diameter were injected in the plasma midplane at velocities exceeding 1 km/s. In low temperature ohmic discharges, pellets penetrate beyond the magnetic axis, and in such cases a sharp decrease in ablation is observed as the pellet passes the plasma center. Density increases of appro… more

Date: September 1, 1980

Creator: Milora, S. L.; Foster, C. A. & Thomas, C. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Hallam Nuclear Power Facility Preoperational Test Completion Report Dry Criticality

A dry criticality test was carried out to determine the minimum critical mass of the HNPF Core without sodium. A subcritical calibration of the central control rod was performed and the relative reactivity worths of the inner ring of six control rods were determined. The extrapolated critical loading for the various plots after each incremental fuel loading with all rods out is shown. A tabulation is presented of multiplication data taken throughout the dry critical test. In order to find the r… more

Date: February 24, 1962

Creator: Kempt, H. C. & Corcoran, W. P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Cycle 7 outage experience. [Fast Flux Test Facility (FFTF)]

The scheduled 58-day refueling outage in preparation for the seventh operating cycle of the Fast Flux Test Facility (FFTF) was successfully completed three days ahead of schedule. The planning and execution of the outage was greatly aided by Project/2 automated scheduling capabilities. For example, the use of ''maintenance windows'' and resource loading capabilities was particularly effective. The value of the planning process was demonstrated by the smooth transition into the outage phase afte… more

Date: March 1, 1986

Creator: Gadeken, A.D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Structures and Properties of Uranium-Fissium Alloys. Final Report- Metallurgy Program 4.1.23

A study was made of the phase relations and the properties of uranium-- fissium alloys which have compositions bracketing that intpnded for the first core loading of Experimental Breeder Reactor II. The fissium aggregate in the alloys consisted of the elements Zr, Nb, Mo, Ru, Rh, and Pd. Phase relations are shown to parallel closely those in the dominant U--Mo--Ru ternary system. The uranium gamma phase is stabilized down to 552 deg C, while the beta phase is entirely suppressed at high fissium… more

Date: July 1, 1961

Creator: Zegler, S. T. & Nevitt, M. V.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Dynamic Simulation of Multi-Pass Pressurized Water Nuclear Power Plants by Analog Computer Techniques

A kinetic model of the primary loop of a multi-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics under conditions of steam generator load and reactor control rod perturbations. Using the 2-pass 28 Mw(t) SM-2 reactor as a typical plant, transient behavior patterns are illustrated and examined for a variety of load inputs, variations in plant constants, and analog model simplifications. (auth)

Date: June 1, 1961

Creator: Brondel, J. O.

Item Type: Thesis or Dissertation

Partner: UNT Libraries Government Documents Department

open access

Pellet fueling development at ORNL

Advanced plasma fueling systems for magnetic confinement devices are being developed at the Oak Ridge National Laboratory (ORNL). The general approach is that of producing and accelerating frozen hydrogenic pellets at speeds in the range of 1-2 km/s and higher. Two specific concepts are under development: (1) high-speed pneumatic acceleration; and (2) mechanical (centrifugal) acceleration. Both approaches are being pursued to meet the projected pellet size and delivery rates for major near-term… more

Date: September 1, 1986

Creator: Combs, S. K.; Milora, S. L.; Foster, C. A.; Schuresko, D. D.; Foust, C. R.; Simmons, D. W. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

U.S. NAVY STRUCTURES. ANNEX 3.2 OF SCIENTIFIC DIRECTOR'S REPORT OF ATOMIC WEAPON TESTS AT ENIWETOK, 1951

Structures are subjected to a 50-kt blast, in order to obtain fundamental data on structures subjected to blast loading, to observe the response of the structures under this loading, and to determine the relative blast-resistance merits of several structural types. Modes of failure are determined. Shaped structures are found to be superdor to rectangular structures. Earth cover for the structures is also found to increase the blast resistance. It is found that standard Navy heavy bomb-proof str… more

Date: June 1, 1952

Creator: Hayen, C.L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Continuous pellet fueling experiments on D-III

A centrifuge pellet injector developed at ORNL was used to continuously fuel beam-heated limiter discharges in D-III. This injector was capable of producing and maintaining a high density neutral beam-heated plasma without auxilary gas fueling. Viewgraphs from the presentation are included.

Date: January 1, 1985

Creator: Foster, C. A.; Milora, S. L.; Attenberger, S. E.; Sengolu, S.; Nagami, M.; Stockdale, R. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Physics of burn control in tokamak reactors

A one-dimensional multifluid transport code was used to investigate some of the critical physics considerations for long burn times in a tokamak fusion reactor. Among these are the effects of helium ash build-up, toroidal field ripple, and fueling in the presence of a divertor. Particle and energy transport models are based on extrapolations from present day devices.

Date: January 1, 1979

Creator: Attenberger, S.E. & Houlberg, W.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Calculation of density profiles in tandem mirrors fueled by pellets

We have modified the LLNL radial transport code TMT to model reactor regime plasmas, fueled by pellets. The source profiles arising from pellet fueling are obtained from existing pellet ablation models. Because inward radial diffusion due to inverted profiles must compete with trapping of central cell ions in the transition region for tandem mirrors, pellets must penetrate fairly far into the plasma. In fact, based on our radial calculations, a pellet with a velocity of 10 km/sec cannot sustain… more

Date: December 2, 1983

Creator: Campbell, R. B. & Gilmore, J. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Magnetic Fusion Energy Plasma Interactive and High Heat Flux Components: Volume 5, Technical assessment of critical issues in the steady state operation of fusion confinement devices

Critical issues for the steady state operation of plasma confinement devices exist in both the physics and technology fields of fusion research. Due to the wide range and number of these issues, this technical assessment has focused on the crucial issues associated with the plasma physics and the plasma interactive components. The document provides information on the problem areas that affect the design and operation of a steady state ETR or ITER type confinement device. It discusses both tokam… more

Date: January 1, 1988

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Selection of Core Design No. 1 for Type 5 Replacement Cores in SM-1 and SM-1A

Nuclear and thermal analyses were performed to determine the characteristics of the Type 5 core in the SM-1 and SM-1A reactor plants as a function of geometry and composition. The following nuclear properties were investigated: core energy release, maximum midlife reactivity, average fuel burnup fraction, B-10 reactivity coefficient, and power distribution. Thermal parameter surveys determined the effects of channel thickness and power distribution upon the DNBR, nominal and hot channel thermal… more

Date: July 1, 1962

Creator: Davidson, S. L. & Paluszkiewicz, S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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End cell I and C requirements for operating tandem mirror reactors

The next generation of fusion reactors will be developed to achieve near-ignition conditions and operate in a tritium environment for significant periods of time. Radiation-hardened diagnostic instrumentation must be developed for these reactors. Although neutral beam injection (NBI) will be used for plasma heating and fueling of experimental fusion machines like MFTF-..cap alpha.. + T, it is believed that ion cyclotron resonance heating (ICRH) will be used in future machines for heating the pl… more

Date: January 1, 1983

Creator: Gorker, G.E. & Osher, J.E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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PL FINAL DESIGN REPORT. VOLUME VI. PLANT PERFORMANCE ANALYSIS

Data and information are presented concerning analyses of PL-2 transient performance, normal startup and shutdown procedures, and shield design. (J.R.D.)

Date: May 10, 1962

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Design and development of the CRBRP ex-vessel transfer machine

The Reactor Refueling System (RRS) for the Clinch River Breeder Reactor Project (CRBRP) uses the Ex-Vessel Transfer Machine (EVTM) for transferring core assemblies outside the reactor vessel. The design of the Ex-Vessel Transfer Machine (EVTM) and its gantry-trolly for the CRBRP is discussed. The development tests required for the design are presented, in conjunction with the impact of the test results on the design. The impact of the increased seismic requirements on the design are also presen… more

Date: January 1, 1977

Creator: Jones, C.E. Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Density rise experiment on PLT

The evolution of the density profile in PLT during intense gas puffing is documented and analyzed. Measurements of the spectrum of low energy edge neutrals and of the change in central neutral density indicate that charge-exchange processes alone cannot account for the central density rise. The transient density profile changes can be reproduced numerically by a diffusivity of approx. 10/sup 4/ cm/sup 2//s, and a spatially averaged inward flow of 10/sup 3/ cm/s. These transport coefficients are… more

Date: May 1, 1982

Creator: Strachan, J.D.; Bretz, N. & Mazzucato, E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Empirical particle transport model for tokamaks

A simple empirical particle transport model has been constructed with the purpose of gaining insight into the L- to H-mode transition in tokamaks. The aim was to construct the simplest possible model which would reproduce the measured density profiles in the L-regime, and also produce a qualitatively correct transition to the H-regime without having to assume a completely different transport mode for the bulk of the plasma. Rather than using completely ad hoc constructions for the particle diff… more

Date: August 1, 1986

Creator: Petravic, M. & Kuo-Petravic, G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

SUMMARY OF HRT RUNS 22, 23 AND 24

In runs 22, 23, and 24 the HRT was operated with downward flow through the core at powers up to 5 Mw. Because of leakage past the lower core tank patch, uranium could not be prevented from entering tbe blanket, so the concentration was deliberately kept above 1 g U/kg D/sub 2/O. The core power was about 0.6 of the total. Nuclear power fluctuations were larger than with upward core flow, and the cause was investigated intensively in run 22 at powers up to 1.8 Mw. Run 22 was terminated after 778 … more

Date: March 1, 1962

Creator: Bauman, H.F.; Buchanan, J.R.; Engel, J.R.; Haubenreich, P.N. & Richardson, D.M.

Item Type: Report

Partner: UNT Libraries Government Documents Department