| Characterizing a Neutron Energy Spectrum Using a "Forward Edge" Neutron Time-of-Flight Spectroscopy Technique |
19 OCT 2005 |
127 pages |
| Authors:
Jeffrey S. Spear; AIR FORCE INST OF TECH WRIGHT-PATTERSONAFB OH
|
 | A Fermi-style thermal neutron disc chopper was designed, constructed, and calibrated in conjunction with a boron-loaded organic scintillator for use in creating a forward edge neutron time-of-flight spectroscopy technique. The forward edge neutron time-of-flight spectroscopy technique inferred the characteristics of a neutron energy spectrum. The system analyzed the spectrum of a moderated and unmoderated PuBe source with the aid of a MATLAB code. Through the use of pulse shape analysis ... |
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| A Measurement of the Neurton and Gamma Transmission of a Protective Vest |
24 AUG 2005 |
18 pages |
| Authors:
Samuel F. Trevino; ARMY RESEARCH LAB ABERDEEN PROVING GROUND MD
|
| The thermal (meV) and energetic (MeV) neutron transmission of a protective vest is measured. The vest is provided by the National Ground Intelligence Center. The energetic neutron transmission of 0.51 (0.025) was measured with the neutrons from an AmBe source. The thermal neutron transmission of 0.0034 (0.00017) was measured with the neutron activated prompt gamma instrument Prompt Gamma Activation Analysis. The numbers in parentheses are one standard deviation. Both of ... |
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| High-Pressure Helium-3 Scintillation Position-Sensitive Detector of Thermal Neutrons |
2002 |
13 pages |
| Authors:
A. Bolozdynya; A. Bolotnikov; J. Richards; CONSTELLATION TECHNOLOGY CORP LARGO FL
|
| The objective of this study is to demonstrate the feasibility of constructing a compact neutron detector that is sensitive to thermal and epithermal neutrons and has high rejection efficiency relative to gamma-ray background. A two-channel high-pressure 3He scintillation detector is considered for the detection of neutrons in coincidence mode. The detector consists of two large avalanche photodiodes viewing a gas volume filled with pressurized 3He. Experiments with the detector demonstrate ... |
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| Comparison of Radiation Response of LiF:MgCuP and A12O3:C thermoluminescent Dosimeters |
OCT 2001 |
|
| Authors:
L. S. Erhardt; L. Prud'homme-Lalonde; T. Cousins; D. Estan; B. Hoffarth; DEFENCE RESEARCH ESTABLISHMENT OTTAWA (ONTARIO)
|
 | A study was conducted comparing the properties of two types of thermoluminescent dosimeters (TLDs): LiF:MgCuP (TLD-100H) and Al2O3:C (TLD-500). This was done in order to determine which is better suited for the dosimetry requirements of the Radiation Effects Group at DREO (RE/DREO). The dose and energy response of the TLDs were measured by exposing them to a wide range of photon doses and energies. In addition, the sensitivity of the ... |
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| Nuclear Radiation-Induced Dimensional Changes in Borosilicate Glass Substrates |
10 AUG 2001 |
112 pages |
| Authors:
Clark L. Allred; MASSACHUSETTS INST OF TECH CAMBRIDGE DEPT OF MATERIALS SCIENCE AND ENGINEERING
|
| A study was made of radiation-induced dimensional changes in Pyrex(Registered) and Hoya SD-2(Registered) glasses. These glasses are used as substrates for MEMS devices employing silicon oscillating beams, and changes in substrate dimension can compromise device performance. Silicon MEMS strain gauges mounted on glass substrates were exposed to gamma doses up to 385 Mrad. The device-substrate differential strain thus measured corresponds to an expansion in the glass following a linear trend ... |
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| Development of an Improved Direct Neutron Sensor |
NOV 97 |
68 pages |
| Authors:
Francis E. LeVert; KEMP CORP KNOXVILLE TN
|
| The feasibility study of the use of conductive polymers to design and assemble a neutron monitor sensitive to fast and thermal neutrons has been completed. Polyacetylene, polypyrrole and polythiophene conductive polymers with conductivities that range from 10(exp -4) (omega-cm)-1 down to 10(exp -11) (omega-cm)-1 were used in this investigation. The sensors were exposed to neutrons from an Am-Be sealed source with an average energy of 2.5 MeV and a 14 ... |
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| Startup Control of the TOPAZ-II Space Nuclear Reactor |
SEP 96 |
|
| Authors:
Carl D. Astrin; NAVAL POSTGRADUATE SCHOOL MONTEREY CA
|
| The Russian designed and manufactured TOPAZ-II Thermionic Nuclear Space Reactor has been supplied to the Ballistic Missile Defense Organization for study as part of the TOPAZ International Program. A Preliminary Nuclear Safety Assessment investigated the readiness to use the TOPAZ-II in support of a Nuclear Electric Propulsion Space Test Mission (NEPSTP). Among the anticipated system modifications required for launching the TOPAZ-II system within safety goals is for a U.S. designed ... |
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| Development of a Directional Thermal Neutron Detector System |
JUL 96 |
78 pages |
| Authors:
Robert L. Schulte; Martin Kesselman; Frank R. Swanson; NORTHROP GRUMMAN CORP BETHPAGE NY
|
| The development of a portable, thermal neutron detection system for nuclear monitoring is described. The report outlines the design, development, fabrication and testing of a prototype directional thermal neutron detector. The system is a battery powered unit that contains 12 detector modules. Each module consists of a thin gadolinium foil convertor layer sandwiched between two planar, large area, quad silicon detectors and the associated analog electronics to process the 8 ... |
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| Detection of Thermal Neutrons through the Use of Internal Wavelength Shifting Optical Fibers. |
21 MAY 1996 |
|
| Authors:
Hugh D. Copeland; Jon R. Losee; Gary F. Mastny; DEPARTMENT OF THE NAVY WASHINGTON DC
|
| An apparatus for detection of thermal neutrons includes a volume of gas which includes 3He. A wavelength shifting optical (WSO) fiber is disposed to receive ultraviolet (UV) photons generated by reactions between neutrons and 3He. UV photons are absorbed within the WSO fiber to produce longer wavelength fluorescence generated photons that propagate within the WSO fiber. A photodetector is disposed to receive fluorescence generated photons from at least one end ... |
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| The Radiation Transport In Air-Over-Ground Geometry |
DEC 95 |
116 pages |
| Authors:
Craig R. Heimbach; Mark A. Oliver; Michael B. Stanka; ABERDEEN TEST CENTER ABERDEEN PROVING GROUND MD
|
| Radiation Transport from a fast burst reactor has been measured from 60 to 2000 meters. Emphasis was placed on the measurement of thermal neutrons, but both fast neutrons and gamma rays were monitored. Effects investigated were sensitivity to angle of emission from the reactor, height over ground, and proximity to trees. |
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| Neutron Irradiation-Induced Dimensional Changes in MEMS Glass Substrates |
1992 |
7 pages |
| Authors:
LaVern A. Starman; AIR FORCE INST OF TECH WRIGHT-PATTERSONAFB OH SCHOOL OF ENGINEERING
|
| A study is made of radiation-induced expansion/compaction in Pyrex and Hoya SD-2 glasses, which are used as substrates for MEMS devices. Glass samples were irradiated with a neutron fluence composed primarily of thermal neutrons, and a floatation technique was employed to measure the resulting density changes in the glass. Transport of Ions in Matter (TRIM) calculations were performed to relate fast (-l MeV) neutron atomic displacement damage to that of ... |
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| Characterization of the Thermalness of a Fissile System with a 2-Group Diffusion Theory Parameter |
DEC 91 |
|
| Authors:
Brent B. Bredehoft; NEW MEXICO UNIV ALBUQUERQUE DEPT OF CHEMICAL AND NUCLEAR ENGINEERING
|
| Tabulation of critical data has commonly been done using the hydrogen to fissile atom ratio H/X. This does not account for the moderating contribution of other light nuclei in the system or for the absorption characteristics, important to the slowing down process. Using a two energy group diffusion theory analogy to the six-factor-formula, we define the parameter an appropriate parameter for defining moderation characteristics. This parameter adequately accounts for the ... |
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| Methodology Investigation of Neutron Device Monitors |
AUG 90 |
|
| Authors:
Craig R. Heimbach; ARMY COMBAT SYSTEMS TEST ACTIVITY ABERDEEN PROVING GROUND MD
|
| Various diodes have been investigated as monitors for 1 MeV equivalent neutrons. One particular diode, the DN-156, has proved suitable. It is not sensitive to thermal neutrons or gamma rays. Production uniformity is sufficiently good that batch calibration is suitable, and individual device calibration is not necessary. The device is not temperature stable, so precautions must be taken to obtain correct results. The DN-156 has been used to calibrate a ... |
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| Challenging the European Defense Industrial Base. |
JAN 1990 |
|
| Authors:
A. D. Sullivan
|
|
| China Report Science and Technology |
18 MAR 1987 |
|
| Authors:
JOINT PUBLICATIONS RESEARCH SERVICE ARLINGTON VA
|
| This China report contains articles on Science and Technology. |
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| Operation GREENHOUSE. Scientific Director's Report of Atomic Weapon Tests at Eniwetok, 1951. Annex 1.5. Neutron Measurements. Part 2. External Neutron and Gamma Flux Measurements by Sample Activation. Section 1, |
01 SEP 1985 |
|
| Authors:
Wendell A. Biggers; Leon J. Brown; LOS ALAMOS SCIENTIFIC LAB ALBUQUERQUE NM
|
| The Greenhouse operation consisted of a series of four shots conducted at Eniwetok during the Srping of 1951. The external neutron threshold measurements consisted of the use of good samples to measure integrated thermal neutron fluxes and sulfur, iodine, and zirconium samples to measure fluxes of higher energy neutrons. The iodine also measured high-energy gamma-ray intensity. Measurements were also made on slow- and fast-neutron intensities as a function of time. ... |
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| OPERATION DOMINIC, FISH BOWL Series. Project Officer's Report - Project 2.2. Gamma Radiation Measurements, |
01 SEP 1985 |
|
| Authors:
J. W. Kinch; R. W. Jenkins; ARMY NUCLEAR EFFECTS LAB EDGEWOOD ARSENAL MD
|
| This project was conducted to measure the initial gamma dose as a function of distance fo Shots Star Fish Prime, Blue Gill Triple Prime and King Fish. To accomplish these objectives, the gamma dose was measured by film badges, glass microdosimeters, cobalt-activated borosilicate glass, calcium fluoride thermoluminescent dosimeters, and formic acid chemical dosimeters. The gamma dose versus distance was successfully measured from all three shots; and the gamma doses from ... |
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| OPERATION SUN BEAM SHOTS LITTLE FELLER I and II, JOHNIE BOY, and SMALL BOY. Project Officer's Report. Project 2.3. Neutron Flux Measurements, |
01 SEP 1985 |
|
| Authors:
D. L. Rigotti; J. H. McNeilly; R. E. Brady; J. L. Tarbox; ARMY NUCLEAR EFFECTS LAB EDGEWOOD ARSENAL MD
|
| The objectives of this project were (1) to measure free-field neutron flux and spectrum as required in support of other projects; (2) to document the neutron flux versus ground range; and (3) to determine the effect of various blast containers and shields on detector activation. |
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| Kerma Factors for Use in 37-Group Neutron Spectrum Calculations |
DEC 1983 |
|
| Authors:
G. H. Zeman; W. S. Bice Jr; ARMED FORCES RADIOBIOLOGY RESEARCH INST BETHESDA MD
|
| Neutron kerma factors have been regrouped from the format of the International Commission on Radiation Units and Measurements Report 26 (ICRU-26) to supplement those available in the 37-group format of the Oak Ridge Data Library Collection 31 (DLC-31). Lists of regrouped neutron kerma factors are presented for eight elements and for seven compounds and mixtures. For several elements, disagreements in excess of 15% were observed between those neutron kerma factors ... |
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| Assessment of the Feasibility of Performing Infield Nondestructive Evaluation to Determine the Presence of Explosives Materials within Cased Munitions. Phase II. Nonvapor Detection |
NOV 1983 |
|
| Authors:
H. J. Gryting; SOUTHWEST RESEARCH INST SAN ANTONIO TX
|
| The Navy has the ongoing problem of ordnance being loaded with simulants for various requirements including practice items being difficult to differentiate from explosive-filled ordnance. In addition some practice bombs contain energetic marker materials. Ideally, one portable instrument for all differentiation problems would be chosen if available. The current survey is to determine the status of explosives detection instruments and possibly viable concepts for such detection for Navy ordnance, much ... |
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| Nuclear Transmutation Doping of GaAs |
SEP 1981 |
|
| Authors:
Hans Fritzsche; CHICAGO UNIV IL JAMES FRANCK INST
|
| Shallow donors have been introduced into GaAs crystals by irradiation with thermal neutrons and subsequent nuclear transmutation. Good agreement was found between the measured concentrations of added donors and the values expected from the neutron capture cross sections and the neutron fluences used. This doping method is approximately 1000 times more efficient in GaAs than in Si because of the higher abundances and neutron capture cross sections of the transmutable ... |
|
| Operation REDWING. Project 2.51, Neutron-Flux Measurements. Extracted Version. |
15 MAY 1981 |
67 pages |
| Authors:
C. W. Luke; D. L. Rigotti; J. W. Kinch; R. Fullwood; D. Anderson; KAMAN TEMPO SANTA BARBARA CA
|
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| Reactor Facility, Armed Forces Radiobiology Research Institute |
MAY 1981 |
|
| Authors:
J. A. Sholtis Jr.; M. L. Moore; ARMED FORCES RADIOBIOLOGY RESEARCH INST BETHESDA MD
|
| The Armed Forces Radiobiology Research Institute (AFRRI) reactor is a TRIGA (Training, Research, and Isotope Production General Atomics Reactor) Mark- F pool-type thermal research reactor, capable of both pulsed and steady-state operation at a variety of locations in the pool. Designed and built by General Atomics, it first achieved criticality in 1962 with aluminum-clad fuel. In 1965, stainless-steel-clad fuel was installed and is still in use today. The AFRRI reactor ... |
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| Operation PLUMBBOB. Neutron-Induced Activities in Soil Elements. Project 2.2. |
01 FEB 1980 |
|
| Authors:
GENERAL ELECTRIC CO SANTA BARBARA CA TEMPO
|
| Neutrons which escape following the detonation of a nuclear device interact with matter within range of the neutron flux. Some of these interactions produce radioactive isotopes. It was the purpose of this project to study the nature of this radioactivity, especially the problems associated with induced radioactivity in soils near ground zero. |
|
| Operation PLUMBBOB. Soil Activation by Neutrons. Project 2.1. |
01 OCT 1979 |
|
| Authors:
DEPARTMENT OF ENERGY WASHINGTON DC
|
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| The Effects of Fast and Thermal Neutron Flux and Gamma Radiation on the Transmission Characteristics of Optical Fibers. |
JUL 1977 |
|
| Authors:
D. C. Sieber; R. G. McCormack; W. J. Croisant; CONSTRUCTION ENGINEERING RESEARCH LAB (ARMY) CHAMPAIGN ILL
|
| This report presents the results of a study of the effects of nuclear radiation on the light transmission characteristics of optical fibers. Two types of radiation were used: 1800-MW pulses of primarily thermal neutrons (10 to the 12th power n/sq.cm.), and a 20-minute exposure of thermal and fast neutrons and gamma radiation. Three representative types of optical fibers were tested: low-loss fused silica, medium-loss lead silicate with borosilicate cladding, and ... |
|
| Image Quality in Neutron Radiography. |
FEB 1975 |
|
| Authors:
r. halmshaw; ROYAL ARMAMENT RESEARCH AND DEVELOPMENT ESTABLISHMENT FORT HALSTEAD (ENGLAND)
|
| The limitations and characteristics of the technique of thermal neutron radiography developed in RARDE, using a 5 MV Linac and the (X,n) reaction in beryllium, have been determined quantitatively using MTF values obtained for various converter screens. The effective source-size has been determined to be 80-90 mm diameter at 840 mm source-to-detector distance, and the implications of this large diameter on the choice of suitable converter screens are detailed. It ... |
|
| Reduction of 41Ar Environmental Releases at Research Reactors. |
AUG 1973 |
|
| Authors:
D. M. Verrelli; R. E. Carter; L. A. Slaback Jr; ARMED FORCES RADIOBIOLOGY RESEARCH INST BETHESDA MD
|
| The reactor facility at the Armed Forces Radiobiology Research Institute consists of a TRIGA Mark-F reactor with two large walk-in exposure rooms and a pneumatic tube facility. Operation of the reactor adjacent to these rooms results in signigicant 41Ar production rated due to the high thermal neutron leakage from the core and from the albedo off the walls. The leakage and albedo have been reduced by placing panels painted with ... |
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| Solution for a Nonlinear Nuclear Reactor with Negative Prompt Feedback and One-Group Delayed Neutron. |
JUN 1973 |
|
| Authors:
Nguyen VAN Minh; NAVAL POSTGRADUATE SCHOOL MONTEREY CALIF
|
| The nonlinear space time neutron flux equation with negative prompt feedback and one-group delayed neutron is reduced by the use of a nonlinear transformation to a partial differential equation, in which the nonlinear term represents a small perturbation. The general procedure of solution for the resulting weakly nonlinear initial-boundary-value problem is then established by means of the method of successive approximation. Convergence of the analytical solution is also discussed. The ... |
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| Neutron Form Factors from Elastic Electron-Deuteron Scattering Ration Experiments at Very Low Momentum Transfer. |
JUN 1973 |
|
| Authors:
Raymond William Berard; Timothy Joseph Traverso; NAVAL POSTGRADUATE SCHOOL MONTEREY CALIF
|
| Measurements of the ratio of the elastic electron-deuteron scattering cross section to the elastic electron-proton scattering cross section were made for low momentum transfers. Augmented by the work of Topping these data span a range of (q sup 2) from 0.05 (fm sup -2) to 0.50 (fm sup -2). From these, the electric form factor of the neutron, (G sub E sub n), was extracted using three Lomon-Feshbach wave functions ... |
|
| Pulsed Neutron Experiment in D2O Water and Ice. |
FEB 1973 |
|
| Authors:
Harold R. Boroson; NAVAL SHIP RESEARCH AND DEVELOPMENT CENTER BETHESDA MD
|
| The first extensive pulsed neutron experiment in heavy water spanning the phase change from +40C to -50C in ice is described. Values for the diffusion coefficient (D sub 0) and the cooling coefficient C were calculated from measurements obtained over a range of buckling from .03 to .05 per square cm. Correlation with past measurements in water was very good. Support was obtained for sparse earlier indications of low values ... |
|
| Damage-Function Analysis of Neutron Embrittlement in Steel at Reactor Service Temperatures. |
08 JUN 1972 |
18 pages |
| Authors:
Charles Z. Serpan Jr; NAVAL RESEARCH LAB WASHINGTON D C
|
| Neutron-induced increases in the brittle-ductile transition temperature (delta TT) of A302-B pressure vessel steel have been measured from irradiations in a number of reactor environments for neutraon fluences representative of pressure vessel design lifetimes. While these measurements have permitted formulation of the trends necessary for delta TT projections in operating reactors, certain anomalous results have been observed wherein measurements fell outside the nominal limits of the trends. As a summation ... |
|
| Isomeric Gamma Rays for Times Less than One Microsecond After 235U(n,f) and 239Pu(n,f). |
15 APR 1972 |
|
| Authors:
R. E. Sund; v. v. verbinski; Hans Weber; GULF RADIATION TECHNOLOGY SAN DIEGO CALIF
|
| Measurements of the isomeric gamma-ray energy spectra from the thermal-neutron fission of 235U and 239Pu were performed with a Ge(Li) detector for times betweeen 20 nsec and about 1 microsec after fission. Sixty-nine resolved gamma-ray peaks with different energies and half lives were observed; 36 of these gamma-ray peaks had not been seen in previous delayed gamma-ray measurements. The fission-fragment mass numbers for many of the gamma rays were determined ... |
|
| Application of Radioactive Tracer Techniques to Flow Decay Problems. |
DEC 1970 |
|
| Authors:
James R. O'Brien ; Kent E. Pullen ; T. Lynn Smith; BOEING AEROSPACE CO SEATTLE WA
|
| In this program various applications of radioactive tracer techniques to flow decay problems were explored. The main object of the program was to develop a sensitive tool which could be used to detect the time, place, and degree of deposition of metal contaminants within various components of a propellant feed system. Such a tool was successfully developed and readily applied to flow studies involving nitrogen tetroxide and hydrazine. As an ... |
|
| Space-Time Pair Correlation Function of a Maxwell-Boltzmann Fluid in the T-Approximation for Temperature Green's Functions. I. Theory, |
19 OCT 1970 |
|
| Authors:
Henri R. Leribaux; Noel K. Pope; ROYAL MILITARY COLL OF CANADA KINGSTON (ONTARIO) DEPT OF MATHEMATICS
|
| A many-body theory is presented for the Van Hove pair (or density) correlation function, in a quantum fluid obeying Boltzmann statistics, of which the Fourier transform S(q,omega) determines the differential cross section for inelastic coherent scattering of slow neutrons. The theoretical formalism of two-particle thermodynamic Green's functions is based on Baym and Kadanoff's conserving T-matrix approximation, developed for strong short-range (intermolecular) potentials. The only other approximations made are: the smallness ... |
|
| Methodology Investigation: Output Characteristics of the White Sands Missile Range Fast Burst Reactor. |
APR 1970 |
|
| Authors:
Ted F. Luera; Don L. Welch; ARMY MATERIEL TEST AND EVALUATION DIRECTORATE WHITE SANDS MISSILE RANGE NM
|
| The results of neutron and gamma radiation dosimetry measurements are presented in this report. Sufficient data are provided so that estimates of the neutron fluence, neutron spectrum, gamma dose, and gamma dose rate can be obtained for both burst operations and power runs. A discussion of the dosimetry techniques presently in use at the Nuclear Effects Directorate is presented, as are plans for improving and expanding upon these techniques. A ... |
|
| A COMPARISON OF FOLDING AND UNFOLDING TECHNIQUES FOR DETERMINING THE GAMMA SPECTRUM FROM THERMAL NEUTRON CAPTURE IN ALUMINUM, |
05 MAR 1970 |
|
| Authors:
R. S. Booth; OAK RIDGE NATIONAL LAB TENN
|
| The gamma-ray spectrum above 1 MeV resulting from thermal-neutron capture in aluminum is determined by both a folding and an unfolding analysis of data. This results in a comparison of the relative merits of the two analysis techniques and demonstrates the accuracy that can be obtained in unfolding a complex spectrum. It is concluded that the accuracy of the final photon spectrum is not governed by the technique employed to ... |
|
| NEUTRON RADIOGRAPHY, |
15 JAN 1970 |
|
| Authors:
Philip W. Hesse; NAVAL ORDNANCE LAB WHITE OAK MD
|
| Thermal neutron output from a moderated 14 Mev D-T reaction is discussed as applicable to neutron radiography. Detectors for radiography are evaluated and the results using the thermal beam of the Naval Ordnance Laboratory's Neutron Diffraction Facility at the National Bureau of Standards for the detection of low atomic number materials contained in high atomic number materials are presented. (Author) |
|
| GAMMA-RAY SPECTRA ARISING FROM THERMAL-NEUTRON CAPTURE IN ELEMENTS FOUND IN SOILS, CONCRETES, AND STRUCTURAL MATERIALS, |
AUG 1969 |
|
| Authors:
R. E. Maerker; F. J. Muckenthaler; OAK RIDGE NATIONAL LAB TENN
|
| Gamma-ray spectra arising from the capture of thermal neutrons are presented for iron, aluminum, copper, zinc, titanium, nickel, silicon, calcium, potassium, sodium, barium, chlorine, sulfur, and stainless steel. The spectral intensities in photons per 100 captures are presented as both individual lines and as sums of these lines over 0.5-MeV intervals which are intended for use in shielding calculations. The latter results have an estimated accuracy of plus or minus ... |
|
| APPLICATION OF GREENS'S FUNCTION ANALYSIS TO THE SOLUTION OF THE NEUTRON DIFFUSION EQUATION IN HETEROGENEOUS SYSTEMS, |
JUL 1969 |
|
| Authors:
Norman E. Banks; G. Lansing Blackshaw; BALLISTIC RESEARCH LABS ABERDEEN PROVING GROUND MD
|
| The general time-dependent, one-velocity neutron diffusion equation is formulated in generalized three-dimensional coordinates for bare heterogeneous systems containing N very thin heterogeneities. This diffusion equation is written first in the Heaviside notation and subsequently transformed to a Dirac delta function representation. Green's function integral techniques are then applied to determine the solution. (Author) |
|
| EFFECT OF DISLOCATION DENSITY ON THE RADIATION EXPANSION OF THE VOLUME OF CRYSTALS, |
03 APR 1969 |
|
| Authors:
D. O. Kalnin; k. k. shvarts; E. E. Feldmane; FOREIGN TECHNOLOGY DIV WRIGHT-PATTERSON AFB OHIO
|
| The effect of the dislocation density on the expansion of the volume of LiF during irradiation in a reactor was investigated. The LiF crystals were grown in a vacuum and etched in an aqueous solution. The dislocations have no significant effect on the radiation expansion. |
|
| THERMAL NEUTRON CAPTURE GAMMA-RAY SPECTRA OF THE ELEMENTS, |
JAN 1969 |
|
| Authors:
Norman C. Rasmussen; Yoshiyuti Hukai; Tamon Inouye; victor j. orphan; MASSACHUSETTS INST OF TECH CAMBRIDGE
|
| A determination of the energy and intensity of the gamma rays resulting from thermal neutron capture in 74 natural elements is reported. The measurements include energies above 200 keV and were done with a Ge(Li) detector. (Author) |
|
| FISSION YIELDS OF SEVERAL IODINE ISOTOPES AND HALF-LIFE AND FISSION YIELD OF 135Te, |
31 DEC 1968 |
|
| Authors:
Allen E. Greendale; Arnaldo A. Delucchi; NAVAL RADIOLOGICAL DEFENSE LAB SAN FRANCISCO CALIF
|
| Measurements have been made of the independent fission yields of several iodine isotopes in thermal-neutron-induced fission of 235U. These yields were obtained by isolation of iodine fission products at early times after fission by a new, fast radiochemical procedure. The fractional cumulative fission yield and half-life of 135Te were also determined from the experimental results. (Author) |
|
| NEUTRON FLUENCE AND DOSE MEASUREMENTS WITH FISSION FOIL-LEXAN DETECTORS, |
04 NOV 1968 |
|
| Authors:
Paul F. Rago; Norman Goldstein; Eugene Tochilin; NAVAL RADIOLOGICAL DEFENSE LAB SAN FRANCISCO CALIF
|
| A fission foil-Lexan detector system has been developed to monitor reactor neutrons. It is similar to the system based on counting fission gamma rays but has some advantages; i.e., permanently recorded tracks that can be read any time after exposure; integrated recording; microgram amounts of fissionable material needed; independence of fission product distribution; and the elimination of specialized gamma-ray counting equipment. Fission product damage tracks in the Lexan (or mica) ... |
|
| AN EMPIRICAL APPROACH TO THERMAL NEUTRON ABSORPTION CROSS SECTIONS. |
26 SEP 1968 |
|
| Authors:
S. Podgor; NAVAL RESEARCH LAB WASHINGTON D C
|
| A simple procedure is proposed to simulate the cyclic variation of the thermal neutron absorption cross sections of the odd-Z, even-N nuclei. The assumption is made that the cross sections vary with (a) the number of protons in the last open proton shell, and (b) the number of neutron holes in the last open neutron shell. With the major nuclear shells as a basis and with variations as to which ... |
|
| GAMMA-RAY SPECTRA OF THE PRODUCTS OF THERMAL-NEUTRON FISSION OF 235U AT SELECTED TIMES AFTER FISSION, |
16 AUG 1968 |
40 pages |
| Authors:
Leland R. Bunney; Daniel Sam; NAVAL RADIOLOGICAL DEFENSE LAB SAN FRANCISCO CALIF
|
| Experimental measurements of the gamma-ray spectra emitted by the products of thermal-neutron fission of 235U have been made at nine selected times (1/4, 1/2, 1, 2, 5, 10, 24, 48, and 72 hours) after fission. A calibrated and highly collimated 5 in. x 5 in. NaI(T1) detector was used. The 100-energy-bin gamma-ray spectra were unfolded from the pulse-height distributions by means of an iterative method. Extensive use was made of ... |
|
| PHYSICAL CHARACTERISTICS OF THE IRT-2000 SWIMMING-POOL RESEARCH REACTOR WITH LOOP CHANNELS (FIZICHNYYA KHARAKTARYSTYKI DASLEDCHAGA REAKTARA BASEINAVAGA TYPU IRT-2000 Z PETLYAVYM KANALAM), |
09 JUL 1968 |
|
| Authors:
A. K. Krasin; V. A. Navumaw; I. A. Savushkin; NAVAL INTELLIGENCE COMMAND WASHINGTON D C TRANSLATION DIV
|
| The IRT-2000 reactor installed in the Institute of Heat and Mass Exchange of the Academy of Sciences of the Belorussian SSR was put in operation in May 1962. Water-cooled water-moderated reactors of the IRT type are simple in design, highly reliable, and safe, while providing great possibilities for experimental work in radiation chemistry, nuclear physics, and biology. Since the IRT-2000 reactor is a prototype, its design did not provide for ... |
|
| REPORT OF LINAC OPERATION 1 JANUARY - 30 JUNE 1968. |
JUL 1968 |
|
| Authors:
NAVAL RESEARCH LAB WASHINGTON D C
|
| The operation and use of the NRL 60 MeV Electron Linear Accelerator is described for the period 1 January - 30 June 1968. Progress reports on the Linac Branch experiments are included, covering electron scattering at 180 deg, two photonuclear experiments, and preliminary neutron capture time-of-flight measurements. Total user time decreased to 1058 hours due to two vacuum accidents, each of which partially destroyed an electron gun. The downtime was ... |
|
| REACTOR UTILIZATION IN SUPPORT OF RESEARCH AND TECHNOLOGY. |
21 JUN 1968 |
|
| Authors:
Charles V. Strain; NAVAL RESEARCH LAB WASHINGTON D C
|
| The radiations generated in a nuclear reactor are useful not only in nuclear physics research but also in many nonnuclear fields of science and technology. A review of present and potential applications of the NRL 1-MW reactor is undertaken with the purpose of encouraging additional utilization of this facility. Neutron activation analysis, a technique capable of assaying very small amounts of many of the chemical elements, is widely used, with ... |
|
| BEHAVIOR OF NUCLEAR FUEL UNDER IRRADIATION (AN INVESTIGATION OF THIN LAYERS OF IRRADIATED URANIUM DIOXIDE), |
29 FEB 1968 |
|
| Authors:
V. M. Golyanov; N. F. Pravdyuk; FOREIGN TECHNOLOGY DIV WRIGHT-PATTERSON AFB OHIO
|
| The effects of irradiation on UO2 were investigated by electron microscopy of thin films. Annealing of defects, the nature and formation of defects, fission gas formation, and the relation of radiation dose to defect concentration were considered. |
|
Reports by Keyword(s)
THERMAL NEUTRONS
