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in subjects: "Radiation Heating"

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Energy dependence of metallic-encapsulated thermoluminescent dosimeters. Annual report

The gamma-ray energy responses of encapsulated /sup 7/LiF and CaF/sub 2/:Mn thermoluminescent dosimeters were measured and compred to calculated values. This study was performed in order to improve the accuracy of gamma-ray heating measurements made in polyenergetic gamma-ray fields such as Argonne National Laboratory's Zero Power Reactors. Equations used in the development of the TERC/III computer code and code input parameters are specified. A section on TLD precision is also included. Compar… more

Date: June 1980

Creator: Simons, G. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Microwave separation of organic chemicals from mixed hazardous waste

The feasibility of utilizing the differential heating characteristics of microwave energy (MW) to aid in the chemical extraction and separation process of hazardous organic compounds from mixed hazardous waste, was studied at the INEL. The long-term objective of this work was to identify a practical method of separating or enhancing the separation process of organic hazardous waste components from mixed waste using microwave (MW) frequency radiation. Methods using MW energy for calcination, sol… more

Date: January 1, 1992

Creator: Anderson, A. A. & Albano, R. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Neutron and gamma transport effects by heterogeneous core designs. [LMFBR]

The use of diffusion theory for the prediction of power production near a reactor core-blanket interface and the assumption that gammas are absorbed in situ can lead to substantial errors. This is primarily due to the breakdown of Fick's law for neutron diffusion near the core-blanket boundary, and the gamma leakage from the core into the blanket. These considerations are more pronounced in a situation where a large number of internal blanket assemblies are present, such as in the large heterog… more

Date: January 1, 1977

Creator: Lam, S.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tank 241-A-105 leak assessment

Tank 241-A-105 is one of 149 single shell tanks constructed at Hanford to contain and store highly radioactive wastes originating from the processing of spent nuclear reactor fuel. Radiation detection and temperature monitoring devices installed beneath the tank indicate that several episodes of leakage of waste from the tank have occurred. The aim of this study was to evaluate the previous estimates and reanalyze the data to provide a more accurate estimate of leakage from the tank. The princi… more

Date: June 1, 1991

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Comprehensive neutron cross-section and secondary energy distribution uncertainty analysis for a fusion reactor

On the example of General Atomic's well-documented Power Generating Fusion Reactor (PGFR) design, this report exercises a comprehensive neutron cross-section and secondary energy distribution (SED) uncertainty analysis. The LASL sensitivity and uncertainty analysis code SENSIT is used to calculate reaction cross-section sensitivity profiles and integral SED sensitivity coefficients. These are then folded with covariance matrices and integral SED uncertainties to obtain the resulting uncertainti… more

Date: May 1, 1980

Creator: Gerstl, S.A.W.; LaBauve, R.J. & Young, P.G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Nuclear performance calculations for the ELMO Bumpy Torus Reactor (EBTR) reference design

The nuclear performance of the ELMO Bumpy Torus Reactor reference design has been calculated using the one-dimensional discrete ordinates code ANISN and the latest available ENDF/B-IV transport cross-section data and nuclear response functions. The calculated results include estimates of the spatial and integral heating rate with emphasis on the recovery of fusion neutron energy in the blanket assembly and minimization of the energy deposition rates in the cryogenic magnet coil assemblies. The … more

Date: December 1, 1977

Creator: Santoro, R. T. & Barnes, J. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

One-dimensional gamma-ray shielding calculations for the EBT-P

Due to the expected large loss of electrons on the magnetic coil assemblies and other components of the proposed EBT-P plasma device, the induced gamma-ray field from bremsstrahlung will be very intense. These gamma rays will yield increased heating loads on the superconducting cryogenic coils as well as produce a significant biological hazard. In this summary, the results from a series of one-dimensional calculations in which the gamma-ray heating loads were determined are presented for severa… more

Date: January 1, 1980

Creator: Lillie, R.A.; Gabriel, T.A.; Bishop, B.L. & Baker, V.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Substitute safety rods: Physics of operation and irradiation

Under certain assumed accidents, an SRS reactor may lose most of its bulk moderator while maintaining flow to fuel assemblies. If this occurs immediately after operation at power, components normally dependent on convective heat transfer to the moderator will heat up with the possibility of melting that component. One component at risk is the currently used cadmium safety rod. A substitute safety rod consisting solely of sintered B{sub 4}C and stainless steel has been designed which is capable … more

Date: November 18, 1991

Creator: Baumann, N.P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Fast Breeder Blanket Facility (FBBF). Quarterly progress report, October 1, 1977--December 31, 1977

Safety investigations of the initial loading and future double loading configurations are reported. Comparison of the fluxes generated by discrete sources and a line source are given. Spectra generated by the FBBF are compared to those obtained for a large fast breeder reactor. Further analysis of the gamma-ray heating rates have been performed using coupled neutron-gamma-ray transport calculations. Gamma-ray heating rates in uranium and UO/sub 2/ have been calculated; the effect of changing th… more

Date: December 1, 1977

Creator: Ott, K.O. (ed.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

SLAC Divertor Channel Entrance Thermal Stress Analysis

X-ray beams emerging from the new SLAC electron-positron storage ring (PEP) impinge on the entrance to tangential divertor channels causing highly localized heating in the channel structure. Analyses were completed to determine the temperatures and thermally-induced stresses due to this heating. These parts are cooled with water flowing axially over them at 30/sup 0/C. The current design and operating conditions should result in the entrance to the new divertor channel operating at a peak tempe… more

Date: July 10, 1985

Creator: Johnson, Gary L.; Stein, Werner; Lu, Stephen C. & Riddle, Robert A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Shielding of Fusion Reactors

The blanket and shield assemblies of fusion reactors will contain a significant number of very sizable penetrations (neutral beam injection ducts, pumping ports, etc.). The combination of high-energy neutrons and large penetrations will introduce severe design problems that are quite different from those encountered previously. Fusion reactors with their penetrations are very complex geometric structures and in calculating nuclear effects (heating, activation, etc.) tradeoffs must be made betwe… more

Date: January 1, 1979

Creator: Alsmiller, R. G., Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

MIT LMFBR blanket physics project progress report No. 7, July 1, 1975--September 30, 1976

Work during the period was devoted primarily to a range of analytical/numerical investigations, including evaluation of means to improve external blanket designs, beneficial attributes of the use of internal blankets, improved methods for the calculation of heterogeneous self-shielding and parametric studies of calculated spectral indices. Experimental work included measurements of the ratio of U-238 captures to U-235 fissions in a standard blanket mockup, and completion of development work on … more

Date: September 30, 1976

Creator: Driscoll, M.J. (ed.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Thermal-hydraulic and neutronic considerations for designing a lithium-cooled tokamak blanket

A methodology for the design of lithium cooled blankets is developed. The thermal-hydraulics, neutronics and interactions between them are extensively investigated. In thermal hydraulics, two models illustrate the methodology used to obtain the acceptable ranges for a set of design parameters. The methodology can be used to identify the limiting constraints for a particular design. A complete neutronic scheme is set up for the calculations of the volumetric heating rate as a function of the dis… more

Date: December 1, 1978

Creator: Chao, J; Mikic, B & Todreas, N

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Radiation-damage calculations with NJOY

Atomic displacement, gas production, transmutation, and nuclear heating can all be calculated with the NJOY nuclear data processing system using evaluated data in ENDF/B format. Using NJOY helps assure consistency between damage cross sections and those used for transport, and NJOY provides convenient interface formats for linking data to application codes. Unique features of the damage calculation include a simple momentum balance treatment for radiative capture and a new model for (n, particl… more

Date: January 1, 1983

Creator: MacFarlane, R.E.; Muir, D.W. & Mann, F.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear heating in thick iron slabs at the ORR Pool Side Facility

The purpose of this work was to determine experimentally and computationally the nuclear heating rates in iron in the Pool Side Facility (PSF) of the Oak Ridge Research Reactor (ORR). This work was performed in support of the NRC-Pressure Vessel Surveillance Program, the objective of which is to verify and upgrade dosimetry and damage correlations for pressure vessels of Light Water Reactors (LWR).

Date: January 1, 1979

Creator: Siman-Tov, I.I.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Cross-section sensitivity analyses for a Tokamak Experimental Power Reactor

The objectives of this report were (1) to determine the sensitivity of neutronic responses in the preliminary design of the Tokamak Experimental Power Reactor by Argonne National Laboratory, and (2) to develop the use of a neutron-gamma coupled cross-section set in the calculation of cross-section sensitivity analysis. Response functions such as neutron plus gamma kerma, Mylar dose, copper transmutation, copper dpa, and activation of the toroidal field coil dewar were investigated. Calculations… more

Date: September 1, 1977

Creator: Simmons, E.L.; Gerstl, S.A.W. & Dudziak, D.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Gamma-thermometer-based reactor-core liquid-level detector. [PWR]

A system is provided which employs a modified gamma thermometer for determining the liquid coolant level within a nuclear reactor core. The gamma thermometer which normally is employed to monitor local core heat generation rate (reactor power), is modified by thermocouple junctions and leads to obtain an unambiguous indication of the presence or absence of coolant liquid at the gamma thermometer location. A signal processor generates a signal based on the thermometer surface heat transfer coeff… more

Date: June 16, 1981

Creator: Burns, T.J.

Item Type: Patent

Partner: UNT Libraries Government Documents Department

open access

Aspects of microwave-heating uniformity

Interest has been shown in the field of nuclear reactor safety in the use of microwave heating to simulate the nuclear heat source. The objective of the investigation reported here was to evaluate the usefulness of microwave dielectric heating as a simulator of the nuclear heat source in experiments which simulate the process of boiling of molten mixtures of nuclear fuel and steel. This paper summarizes the results of studies of several aspects of energy deposition in dielectric liquid samples … more

Date: January 1, 1983

Creator: Ginsberg, T. & Makowitz, H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal-hydraulic analysis of the dual-function gamma thermometer

A computational study was performed to investigate the potential of a modified gamma thermometer (GT) as a monitor of both the localized power level and the core cooling in a PWR. The volumetric heat source within the thermometer was updated to include heat deposited by neutrons as well as heat deposited by decay gammas and neutron-induced gammas. Utilizing this source, along with a more detailed thermal-hydraulics model, a series of thermal-hydraulic calculations were performed to simulate cer… more

Date: December 1, 1981

Creator: Johnson, J.O. & Burns, T.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Thermal problems on high flux beam lines

Wiggler and undulator magnets can provide very intense photon flux densities to beam line components. This paper addresses some thermal/materials consequences due to such impingement. The LBL/Exxon/SSRL hybrid-wiggler Beam Line VI now nearing operation will be able to provide up to approx. 7 kW of total photon power at planned SPEAR operating conditions. The first masks are located at 6.5 meters from the source and may receive a peak power density (transverse to the beam) exceeding 20 kW/cm/sup… more

Date: September 1, 1983

Creator: Avery, R.T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Technical evaluation report for the demonstration of radio frequency soil decontamination at Site S-1

The Air Force`s Armstrong Laboratory at Tyndall Air Force Base, Florida, has supported the research and development of Radio Frequency Soil Decontamination. Radio frequency soil decontamination is essentially a heat-assisted soil vapor extraction process. Site S-1 at Kelly Air Force Base, San Antonio, Texas, was selected for the demonstration of two patented techniques. The site is a former sump that collected spills and surface run-off from a waste petroleum, oils, and lubricants and solvent s… more

Date: April 1, 1995

Creator: Lyon, Chesley R.; Blanchard, Clifton F. & Whitt, Laura H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Minutes of the Tank Waste Science Panel meeting September 13--14, 1990

The third meeting of the Tank Waste Science Panel was held September 13--14, 1990. Science Panel members were briefed on the August 5, 1990, gas release from tank 241-101-SY (commonly denoted 101-SY), synthetic waste experiments to investigate gas generation and crust behavior in the tank, computer simulations of the thermal behavior of the waste in the tank, and calculations of gas generation based on radiolytic chemistry in alkaline solutions. Data from tanks 103-SY and 103-AN were presented,… more

Date: February 1, 1991

Creator: Strachan, D.M. & Morgan, L.G. (comps.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Initial progress in the first wall, blanket, and shield Engineering Test Program for magnetically confined fusion-power reactors

The first wall/blanket/shield (FW/B/S) Engineering Test Program (ETP) progressed from the planning stage into implementation during July, 1981. The program, generic in nature, comprises four Test Program Elements (TPE's), the emphasis of which is on defining the performance parameters for the Fusion Engineering Device (FED) and the major fusion device to follow FED. These elements are: (1) nonnuclear thermal-hydraulic and thermomechanical testing of first wall and component facsimiles with emph… more

Date: October 1, 1981

Creator: Herman, H.; Baker, C. C. & Maroni, V. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fluxless laser soldering for electronic packaging

Conventional soldering typically requires the use of reactive fluxes to promote wetting. The resulting flux residues are removed primarily with halogenated or chlorofluorocarbon (CFC) solvents. With the mandated phaseout of CFCs by the year 2000, there has been a concentrated effort to develop alternative, environmentally compatible manufacturing and cleaning technologies that will satisfy the restrictions placed on CFCs, but still yield high quality product. Sandia National Laboratories is cur… more

Date: January 1, 1991

Creator: Hosking, F M & Keicher, D M

Item Type: Article

Partner: UNT Libraries Government Documents Department