WorldCat Identities

Tochilin, E. (Eugene)

Overview
Works: 28 works in 40 publications in 1 language and 488 library holdings
Roles: Editor
Classifications: RM849, 539.77
Publication Timeline
Key
Publications about  E Tochilin Publications about E Tochilin
Publications by  E Tochilin Publications by E Tochilin
Most widely held works by E Tochilin
Radiation dosimetry by F. H Attix ( Book )
9 editions published between 1966 and 1972 in English and held by 443 WorldCat member libraries worldwide
Radiation dosimetry by Frank H Attix ( Book )
2 editions published in 1969 in English and held by 8 WorldCat member libraries worldwide
Radiation dosimetry by Frank H Attix ( Book )
2 editions published in 1972 in English and held by 8 WorldCat member libraries worldwide
Radiation dosimetry. Second edition ... Edited by Frank H. Attix ... William C. Roesch. (vol. 3. Edited by Frank H. Attix ... Eugene Tochilin.) by RADIATION DOSIMETRY ( Book )
1 edition published in 1968 in English and held by 2 WorldCat member libraries worldwide
CALORIMETRIC MEASUREMENTS OF GAMMA RAY, FAST NEUTRON, AND CHARGED PARTICLE ABSORBED DOSES by N Goldstein ( Book )
2 editions published in 1963 in English and held by 2 WorldCat member libraries worldwide
The energy absorbed by aluminum, carbon, or tissue-equivalent (TE) material when exposed to gamma rays, fast neutrons, or 900-Mev alpha particles was measured with a microcalorimeter. The instrument has an ethylene glycol bath in stead of water. Spaced mylar sheets about 6-1/2 in. in diameter were mounted on one side of the absorber inside the evacuated cylindrical chamber in order that the detector could be thermally insulated in the direction beam without the presence of bath solution. Gamma-ray absorbed dose rates as low as 2 rads/ min were measured with the instrument. The dose rates obtained from the exposures to Co-60 and Cs-137 sources at this Laboratory (NRDL) agreed with the output of the sources as measured with a National Bureau of Standards secondary standard cavity ionization chamber. Thirteen 10-min exposures of the TE absorber in the microcalorimeter to fast neutrons from a 60-in cyclotron resulted in absorbed dose measurements varying from 24 to 40 rads. The average absorbed dose value was 5% higher than the NRDL determination based on flux and spectrum measurements. Microcalorimeter exposures to the 900-Mev alpha particle beam from a 184-in. synchro-cyclotron gave absorbed doses that agreed reasonably well with ionization chamber determinations
A standardized method for making neutron fluence measurements by fission fragment tracks in plastics by Serge Prêtre ( Book )
2 editions published in 1966 in English and held by 2 WorldCat member libraries worldwide
A neutron detector is described which consists of a fission foil (232Th, 235U, 238U, 237Np or 239Pu) in contact with a plastic track detector. These detectors were exposed to reactor neutrons and to monoenergetic neutrons with energies between 1.0 - 18 MeV. Fission fragment tracks registered in the plastic were selectively etched by an hydroxide and counted in an optical microscope. For thick foils of fissionable metals the sensitivity of the system was found to be (1.16 plus or minus 3%) X 10 to the minus 5th power fission fragment tracks/neutron - barn which is in good agreement with theoretical calculations. This sensitivity is independent of the fissionable element used, independent of the neutron energy, fairly independent of the material chosen for track registration (plastics, glass, mica) and of etching conditions. Since the (n, f) cross sections are accurately known for most neutron energies, the above constant can also be used for standardized measurements of neutron fluences
Radiation dosimetry by International Summer School on Radiation Protection ( Book )
1 edition published in 1968 in English and held by 2 WorldCat member libraries worldwide
Neutron fluence and dose measurements with fission foil-lexan detectors ( Book )
1 edition published in 1968 in English and held by 1 WorldCat member library worldwide
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) are counted under an optical microscope. Fluence is determined from the sensitivity factor of 0.0000116 tracks/neutron-barn. Experimental results are given. (Author)
Flux and spectral measurements of primary and moderated neutron sources ( Book )
1 edition published in 1962 in English and held by 1 WorldCat member library worldwide
Radioactive (a, n) neutron sources include Ra-Be, PuF4, and four PuBe13 sources. Comparative neutron emission rates were determined by two separate methods: (1) the manganese sulfate bath with appropriate corrections made for fast neutron escape or capture and for thermal neutron capture by the source; and (2) long counter measurements corrected for energy response and so rce anisotropy. Agreement to within 1 percent was obtained by the two independent methods. A Ra-Be source calibrated against the NBS neutron standard was used as a primary reference Spectral measurements of PuBe13 and PuF4 neutron sources were made with nuclear emulsions. By the use of cylindrical plastic and lead absorbers, an effort was made to moderate the PuBe13 spectrum and thereby obtain additional calibration points for instrument response studies. Spectral changes were initially studied with the doublemoderator technique, followed by later measurements with nuclear emulsions. From flux and spectral measurements of the primary and moderated radioactive sources, the first collision tissue dose was calculated and, in turn, compared to experimental measurements of absorbed dose with proportional counters designed according to the Bragg-Gray principle. (Author)
DOSE RATE AND SPECTRAL MEASUREMENTS FROM PULSED X-RAY GENERATORS ( Book )
1 edition published in 1965 in English and held by 1 WorldCat member library worldwide
Typical X-ray spectra from high intensity pulsed X-ray sources were determined by means of an equivalent constant voltage accelerator. The photon energy spectrum for the forward X-ray beam was measured with various X-ray target thicknesses at accelerator voltages of 1.0, 1.5 and 2.0 Mv. X-ray spectra were also obtained from a reflection X-ray target an angles of 7 deg and 45 deg with respect to the X-ray beam at applied potentials of 0.55, 1.0 and 2.0 Mv. The dose rate dependence of thermo luminescent LiF, silver-activated phosphate glass, and dosimetry film was investigated over a range of dose rates extending from 10,000 to 10 to the 11th power rad/sec with three separate flash X-ray systems
Photon, neutron and charged particle absorbed dose measurements with a portable microcalorimeter ( Book )
1 edition published in 1966 in English and held by 1 WorldCat member library worldwide
Two compact, portable microcalorimeters were built and used to measure absorbed dose. A thermal shield near liquid nitrogen temperature provides the necessary isothermal environment for the absorber. Temperature increase of the absorber during irradiation is measured with a thermistor. Tissue equivalent plastic and beryllium absorbers were calibrated for absorbed energy as a function of temperature change by exposures to standard Co60 and Cs137 gamma-ray sources. The beryllium absorber detected gamma-ray doses as low as 0.17 rads (17 ergs/g) with a standard error of 6 percent. Microcalorimetric measurements of absorbed dose from continuous and pulsed X-rays, reactor neutrons, and charged particles were compared to measurements with other dosimeter systems. (Author)
Radiation dosimetry by International Summer School on Radiation Protection ( Book )
1 edition published in 1969 in English and held by 1 WorldCat member library worldwide
A beta-ray surface ionization chamber for use as a secondary standard by E Tochilin ( Book )
1 edition published in 1950 in English and held by 1 WorldCat member library worldwide
LITHIUM FLUORIDE FOR MEGARAD DOSIMETRY ( Book )
1 edition published in 1967 in English and held by 1 WorldCat member library worldwide
A LiF dosimeter has been developed to measure gamma-ray exposures between 100,000 and 2 x 10 to the 9th power R. Applicability of the LiF as a megarad dosimeter depends on the fact that a thermoluminescent glow peak at a temperature about 450C has a negligible response to radiation below exposures of 100,000 R.A number of crystal specimens were examined and most of them were found to have the high temperature glow peak which could be followed as a function of exposure for three to five decades. Similar responses of the high temperature glow peak were found for the dosimeter when exposed to 2-MeV pulsed electrons or thermal neutrons. (Author)
PHOTOGRAPHIC DETECTION OF FAST NEUTRONS: APPLICATION TO NEUTRON RADIOGRAPHY ( )
1 edition published in 1964 in English and held by 1 WorldCat member library worldwide
The response of photographic emulsions to fast neutrons has been studied by direct measurements at two neutron energies and by exposure to high- energy charged particles. Dose response was significantly less for neutrons than for gamma rays and decreased progressively with decreasing neutron energy. Increased neutron sensitivity was obtained by use of organic scintillators as intensifying screens in conjunction with film. Neutron radiographs at two different energies were taken with step wedges made of Al, Cu, Pb and plastic. Radiographs were taken behind 2, 4, 6 and 8 inches of lead. Loss of photographic resolution from gamma rays produced in the test sample and by thermal neutron interactions is discussed
OPERATION GREENHOUSE. Scientific Director's Report of Atomic Weapon Tests at Eniwetok, 1951. Annex 6.5. Interpretation of Survey-Meter Data ( Book )
1 edition published in 1951 in English and held by 1 WorldCat member library worldwide
This is the Scientific Director's Report of Atomic Weapon Test at Enuivetok, 1951. Under laboratory conditions a study of survey-instrument response to fission-product activity was made. This study involved a knowledge of beta-ray energy, gamma-ray energy, and beta-ray and gamma-ray dose rates associated with fission-product radiation fields. Fission-product activity was collected on aluminum plaques which were flown through the radioactive cloud following each of four bursts. These plaques were flown to the Laboratory for the work done. Beta-ray dose rates were determined with specially constructed beta-ray surface chambers previously calibrated with beta-ray isotopes. Using aluminum absorbers, beta-ray absorption curves were run and compared with similar absorption measurements obtained using known beta-ray isotopes. Gamma-ray dose rates were obtained by shielding out the beta-ray contribution. The response of various types of commercially available G-M counters and ion-chamber counters to fission-product beta-ray and gamma-ray was studied. Changes in beta-ray energy were studied for the period from 44.6 to 215.7 hr. It was found that the beta-ray absorption curve could be reproduced by a high-energy and low-energy component of beta radiation. Laboratory determination of effective gamma-ray energies using half-value-layer measurements by means of aluminum, copper and lead filters showed the energy to be dependent upon the absorber used
The quality and let dependence of three thermoluminescent dosimeters and their potential use as secondary standards ( Book )
1 edition published in 1968 in English and held by 1 WorldCat member library worldwide
The energy dependence of thermoluminescent dosimeters was investigated over a range of x- and gamma-ray energies extending from 6 to 2750 keV. Radiation sources included filtered x rays and isotopes emitting gamma rays of known energies. In order to correlate the energy deposited in the phosphor with light output, the measured response was compared with the computed value of absorbed dose. A systematic increase in light output with decreasing photon energy was observed for all phosphors: this was interpreted as an LET effect. The LET dependence of these phosphors was then investigated with accelerator-produced charged particles for LET values from 0.25 keV/micron to beyond 1000 keV/micron. Response curves are presented which allows the use of LiF and Li2B4O7:Mn as secondary standards to measure absorbed dose or exposure. The use of this method for x- and gamma-ray measurements down to 6 keV is described. Calibration is by means of a 60Co gamma-ray standard. (Author)
Neutron and gamma-ray dosimetry in an animal exposure volume at a pulsed triga reactor ( Book )
1 edition published in 1962 in English and held by 1 WorldCat member library worldwide
The distribution of steady-state and pulsed, neutron and gamma-ray dose was measured in an animal exposure volume at the TRIGA reactor. The usable volume was restricted to the lower 20 in. of an aluminum irradiation tube having an ID of 9-1/2 in. The tube was inserted into the pool adjacent to the reactor void tank, 134 cm from the core. Dosimetry films were used to determine gamma-ray dose while Sievert ionization chambers were used to determine neutron dose. Gold foils were used to measure the thermal neutron flux. Neutron doses were referenced to sulphur foil monitors. The neutron spectrum was examined with a system of threshold detectors and compared with spectra from Godiva II and the biological port of the Argonne CP-5 reactor. The vertical variation of dose along a lucite board was measured at the midplane of a lucite canister lowered into the tube. The dose in the lower 16 in. varied less than 5%. The ratio of neutron to gamma dose was approximately 6 to 1. A tissue equivalent dog phantom, 20 in. long and 7-1/2 in. in diameter, was designed to determine the absorbed dose in depth. The fast neutron dose was about equal to the gamma-ray dose at the midline of the phantom. The neutron plus gamma-ray dose at the midline was 44% of the dose at the front surface of the phantom. (Author)
Neutron flux measurements from 100 kev to 4 mev with a modified long counter by Rubem A Alves ( Book )
1 edition published in 1960 in English and held by 1 WorldCat member library worldwide
 
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Alternative Names
Tochilin, E.
Tochilin, Eugene
Languages
English (32)