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in subjects: "Shielding"

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First wall/blanket/shield design and optimization system

First wall/blanket/shield design and optimization system (BSDOS) has been developed to provide a state-of-the-art design tool for fast accurate analysis. In addition, it has been designed to perform several other functions: (1) allowing comparison and evaluation studies for different concepts using the same data bases and ground rules, (2) permitting the use of any figure of merit in the evaluation studies, (3) optimizing the first wall/blanket/shield design parameters for any figure of merit u… more

Date: February 1, 1988

Creator: Gohar, Y.; Baker, C.; Attaya, H.; Cha, Y.; Majumdar, S. & Scandora, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Computer program SCAP-BR for gamma-ray streaming through multi-legged ducts

A computer program, SCAP-BR, has been developed at Burns and Roe for the gamma-ray streaming analysis through multi-legged ducts. SCAP-BR is a modified version of the single scattering code, SCAP, incorporating capabilities of handling multiple scattering and volumetric source geometries. It utilizes the point kernel integration method to calculate both the line-of-sight and scattered gamma dose rates by employing the ray tracing technique through complex shield geometries. The multiple scatter… more

Date: December 8, 1977

Creator: Byoun, T. Y.; Babel, P. J. & Dajani, A. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Shielding considerations for advanced space nuclear reactor systems

To meet the anticipated future space power needs, the Los Alamos National Laboratory is developing components for a compact, 100 kW/sub e/-class heat pipe nuclear reactor. The reactor uses uranium dioxide (UO/sub 2/) as its fuel, and is designed to operate around 1500 k. Heat pipes are used to remove thermal energy from the core without the use of pumps or compressors. The reactor heat pipes transfer mal energy to thermoelectric conversion elements that are advanced versions of the converters u… more

Date: January 1, 1982

Creator: Angelo, J.P. Jr. & Buden, D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Status of reactor-shielding research in the US

While reactor programs change, shielding analysis methods are improved slowly. Version-V of ENDF/B provides improved data and Version-VI will be cost effective in advanced fission reactors are to be developed in the US. Benchmarks for data and methods validation are collected and distributed in the US in two series, one primarily for FBR-related experiments and one for LWR calculational methods. For LWR design, cavity streaming is now handled adequately, if with varying degrees of elegance. Inv… more

Date: January 1, 1980

Creator: Maienshein, F.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Superconductivity: Past, present, and future

This paper provides an overview of superconductor research and development activities, with emphasis on the potential of high-{Tc} materials for future applications. Superconductor applications are grouped under the following categories: electronics/instrumentation, bulk material/castings, research devices, industrial/commercial, electric power, and transportation/propulsion. Near-term applications are typically based on thin film and cast forms of high-{Tc} materials, while large-scale applica… more

Date: January 1, 1992

Creator: Uherka, K.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Effect of high aspect ratio on ITER maintenance design

The International Thermonuclear Experimental Reactor (ITER) baseline machine configuration and auxiliary systems design specify maintainability and repairability as fundamental requirements. Two important maintenance requirements for ITER are a device that is fully remotely maintainable, with the provision for hands-on maintenance wherever possible, and the ability to maintain components with short lives or high failure rates without moving other components or disturbing the machine's internal … more

Date: January 1, 1991

Creator: Herrick, T.J.; Davis, F.C.; Hollis, M.J. & Lousteau, D.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

SOILD: A computer model for calculating the effective dose equivalent from external exposure to distributed gamma sources in soil

The SOLID computer model was developed for calculating the effective dose equivalent from external exposure to distributed gamma sources in soil. It is designed to assess external doses under various exposure scenarios that may be encountered in environmental restoration programs. The models four major functional features address (1) dose versus source depth in soil, (2) shielding of clean cover soil, (3) area of contamination, and (4) nonuniform distribution of sources. The model is also capab… more

Date: January 1, 1991

Creator: Chen, S. Y.; LePoire, D.; Yu, C. (Argonne National Lab., IL (United States)); Schafetz, S. (Rockland Community Coll., Suffern, NY (United States)) & Mehta, P. (Fayetteville State Univ., NC (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Engineering considerations of the advanced free electron laser facility

The Advanced Free-Electron Laser (AFEL) is being built at Los Alamos inside a large laboratory building. In addition to cost and available space considerations, several engineering issues affected the design of the AFEL and its facility. The 1300-MHz, 20-MeV electron linac required extensive radiation shielding and a short rf-waveguide run. Free-Electron Lasers (FEL) and photocathode-drive laser optics required a clean, constant temperature environment. New environmental, health, and safety (ES… more

Date: January 1, 1991

Creator: Meier, K.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Material Considerations in the Design of a Bulk Shield for the Fusion Engineering Device

The FED bulk shield provides protection from high-energy neutrons and gamma rays and removes nuclear heat generated. Bulk shield optimization calculations were conducted using the Los Alamos ONEDANT discrete ordinates and the General Atomic PATH point kernel codes. Six candidate steel alloys were considered.

Date: January 1, 1981

Creator: Kirchner, J. & Engholm, B. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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CRBRP reactor system shield design and impact of new materials irradiation damage data

Structural materials radiation damage data have received considerable attention in the design of LMFBR permanent reactor structures. A recent FFTF/CRBRP structural materials irradiation experiment, conducted as part of the national program plan for irradiation effects on mechanical properties of LMFBR out-of-core structural materials, has found engineering application in setting energy-dependent neutron exposure limits of irradiated structures. This paper describes the impact of the new irradia… more

Date: January 1, 1980

Creator: Wrights, G.N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)

Date: September 29, 1960

Creator: Chupak, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Design studies of a laser fusion power plant

The conceptual design of a laser fusion power plant has been undertaken to exploit recent developments in target design. Advanced high-gain targets which have been developed make it possible to significantly relax the laser and optical system requirements. The power plant design features a reactor concept which utilizes a thick falling region of liquid lithium to protect the first-wall from the neutrons, x-rays, and charged particles that are produced in the thermonuclear microexplosion. The li… more

Date: October 7, 1977

Creator: Maniscalco, J. A.; Meier, W. R. & Monsler, M. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Design analysis and optimization of self-cooled lithium blankets and shields

A study of self-cooled lithium blankets was carried out to define the performance of these blankets and to determine the potential to operate at the maximum possible values of the performance parameters. The main design parameters considered during the course of the study were the tritium breeding ratio, the blanket energy multiplication factor, the energy fraction lost to the shield, the total blanket thickness, the reflector material selection, and the compositions of the different blanket zo… more

Date: February 1, 1988

Creator: Gohar, Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Electron cyclotron resonance heating (ECRH) in the TMX-Upgrade tandem-mirror experiment

Results are described of engineering tests of operation of two gyrotrons from one power supply, tests of waveguide components and antennae, antenna design, and the x-ray shielding concept. Finally, we describe considerations of interaction with other system components.

Date: October 1, 1981

Creator: Griffin, D.H.; Rubert, R.R.; Simonen, T.C.; Stallard, B.W. & Wieskamp, T.F.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear data relevant to shield design of FMIT facility

Nuclear data requirements are reviewed for the design of the Fusion Materials Irradiation Test (FMIT) facility. This accelerator-based facility, now in the early stages of construction at Hanford, will provide high fluences in a fusion-like radiation environment for the testing of materials. The nuclear data base required encompasses the entire range of neutron energies from thermal to 50 MeV. In this review, we consider neutron source terms, cross sections for thermal and bulk shield design, a… more

Date: January 1, 1980

Creator: Carter, L. L.; Morford, R. J. & Wilcox, A. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Low-background measurements of neutron emission from Ti metal in pressurized deuterium gas

A wide variety of neutron detector systems have been used at various research facilities to search for anomalous neutron emission from deuterated metals. Some of these detector systems are summarized here together with possible sources of spurious signals from electronic noise. During the past two years, we have performed experiments to measure neutron emission from pressurized D{sub 2} gas mixed with various forms of titanium metal chips and sponge. Details concerning the neutron detectors, ex… more

Date: January 1, 1991

Creator: Menlove, H. O.; Paciotti, M. A.; Claytor, T. N. & Tuggle, D. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

ICRF (Ion Cyclotron Range of Frequencies) edge modeling studies

Theoretical models have been developed, and are currently being refined, to explain the edge plasma-antenna interaction that occurs during ICRF heating. The periodic structure of a Faraday shielded antenna is found to result in strong ponderomotive force in the vicinity of the antenna. A fluid model, which incorporates the ponderomotive force, shows an increase in transport to the Faraday shield. A kinetic model shows that the strong antenna near fields act to increase the energy of deuterons w… more

Date: January 1, 1989

Creator: Lehrman, I.S. (Grumman Aerospace Corp., Princeton, NJ (USA). Corporate Research Center) & Colestock, P.L. (Princeton Univ., NJ (USA). Plasma Physics Lab.)

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Radiation Shielding Design Considerations for Doublet III

Calculations and measurements were made of the bremsstrahlung (x-ray) doses resulting from runaway electron shots at Doublet III. The analysis considered direct, wall-scattered, and skyshine contributions. Reasonably good agreement was obtained between calculations and measurements. The x-ray dose in the control room was about 1 mR per runaway shot, while that at the north boundary was undetectable, with a calculated value of 0.05 mR per shot. These low doses attest to the adequacy of the 2 ft … more

Date: June 1, 1980

Creator: Engholm, B. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Computational determination of ballistic limits for a simple Whipple bumper shield

A series of numerical simulations has been performed using the multi-dimensional hydrodynamics code CTH to computationally determine a ballistic limit for a Whipple bumper shield. The ballistic limit is generally characterized as a critical diameter such that particle diameters greater than the ballistic limit will generate debris clouds that will penetrate the rear wall and particle diameters less than the ballistic limit will not. The particular shield design used for these analyses is define… more

Date: January 1, 1991

Creator: Hertel, E.S.; Chhabildas, L.C.; Yarrington, L. (Sandia National Labs., Albuquerque, NM (United States)) & Hill, S.A. (National Aeronautics and Space Administration, Huntsville, AL (United States). George C. Marshall Space Flight Center)

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Comparison of Calculated and Experimental Neutron Attenuation and Streaming Data for Fusion Reactor Design

Integral experiments that measure the neutron and gamma-ray energy spectra resulting from the attenuation of approx. 14 MeV T(D,n)/sup 4/He reaction neutrons in laminated slabs of stainless steel type 304, borated polyethylene, and a tungsten alloy (Hevimet) and from neutrons streaming through a 30-cm-diameter iron duct (L/D = 3) imbedded in a concrete shield have been performed at the Oak Ridge National Laboratory. The facility, NE-213 liquid scintillator detector system, and experimental tech… more

Date: January 1, 1980

Creator: Santoro, R. T.; Alsmiller, R. G., Jr.; Barnes, J. M. & Chapman, G. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A user's guide to CEPXS/ONELD Version 1. 1

This is the user's guide to CEPXS/ONELD Version 1.1, a code package for coupled electron-photon transport in one-dimensional slab geometry. The code package consists of the multigroup cross-section generating code, CEPXS; the preprocessor code, PRE1D; the discrete ordinates code, ONELD; and the postprocessor code, POST1D. In Version 1.1, new features have been implemented through several new keywords. Since Version 1.0 keywords are still applicable, this document should be considered as an adde… more

Date: October 1, 1991

Creator: Lorence, L. J., Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Beryllium usage in fusion blankets and beryllium data needs. [None]

Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among all nonfissile materials, produces the highest number (2.5 neutron in an infinite media) of neutrons per 14-MeV incident neutron. In amounts of about 20 cm of equivalent solid density, it can be used to produce fissile material, to breed all the tritium consumed in ITER from outboard blankets only, and in designs to produce Co-60. The problem is that predictions of neutron multiplication in bery… more

Date: April 6, 1988

Creator: Moir, Ralph W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Sensitivity study of neutron transport through standard and rebar concrete

An investigation is under way at ORNL to (1) develop a data base pertinent to the transport of neutrons through thick concrete shields, (2) use the data base in an energy group boundary selection and collapsing scheme, and (3) develop a simple methodology to access the data base to provide rapid solutions to practical shielding problems. This paper describes work carried out to fulfill objective (1), the work consisting of calculations of the transport of fission neutrons through 1- and 2-m-thi… more

Date: January 1, 1982

Creator: Bhuiyan, S. I.; Roussin, R. W. & Lucius, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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The ion cyclotron heating (ICH) system for BPX

The ICH system is required to deliver at least 20 MW of rf power to the BPX plasma for pulse lengths of up to 15 s over a range of plasma operating conditions (e.g., average plasma densities from 0.5 to 4.5 {times} 10{sup 20} m{sup {minus}3}, toroidal fields from 5 to 8 T). The power must be delivered to the plasma over a range of frequencies corresponding to the different operating conditions. On the basis of calculations of the load resistance that the antennas will see because of the presenc… more

Date: January 1, 1991

Creator: Swain, D. W.; Yugo, J. J.; Williamson, D. E.; Batchelor, D. B.; Carter, M. D. & Goulding, R. H.

Item Type: Article

Partner: UNT Libraries Government Documents Department