WorldCat Identities

Tochilin, E. (Eugene)

Overview
Works: 41 works in 83 publications in 1 language and 618 library holdings
Roles: Author, Editor
Publication Timeline
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Most widely held works by E Tochilin
Radiation dosimetry by Frank H Attix( Book )

9 editions published between 1968 and 1972 in English and Undetermined and held by 391 WorldCat member libraries worldwide

Radiation dosimetry by Frank H Attix( )

13 editions published between 1966 and 1972 in English and held by 85 WorldCat member libraries worldwide

Radiation dosimetry by Frank H Attix( Book )

7 editions published in 1969 in English and held by 29 WorldCat member libraries worldwide

Radiation Dosimetry, Second Edition, VOLUME III: Sources, Fields, Measurements, and Applications covers the significant aspects of radiation dosimetry. The book discusses dosimetry relating to x rays and teleisotope gamma rays, discrete and distributed alpha-, beta-, and gamma-ray sources, electron beams, and heavy charged particle beams. The text also describes dosimetry relating to reactors, neutron and mixed n-gamma fields, neutrons from accelerators and radioactive sources, initial and residual ionizing radiation from nuclear weapons, natural and man-made background radiation, radiation i
A photographic method for measuring the distribution of dosage from radium needles and plaques by E Tochilin( )

2 editions published in 1952 in English and held by 9 WorldCat member libraries worldwide

Depth-dose measurements of beta-ray isotopes with photographic film by E Tochilin( )

2 editions published in 1952 in English and held by 9 WorldCat member libraries worldwide

Calorimetric measurements of gamma ray, fast neutron, and charged particle absorbed doses by E. R Schleiger( )

3 editions published in 1963 in English and held by 9 WorldCat member libraries worldwide

Thirteen 10-min exposures of the TE absorber in the microcalorimeter to fast neutrons from the University of California 60-in. cyclotron at Crocker Laboratory resulted in absorbed dose measurements varying from 24 to 40 rads. The average absorbed dose value was 5 percent higher than the NRDL determination based on flux and spectrum measurements. Microcalorimeter exposures to the 900-Mev alpha particle beam from the University of California 184-in. synchro-cyclotron at Lawrence Radiation Laboratory gave absorbed doses that agreed reasonably well with ionization chamber determinations
Flux and spectral measurements of primary and moderated neutron sources by E Tochilin( )

2 editions published in 1962 in English and held by 8 WorldCat member libraries worldwide

Neutron and gamma-ray dosimetry in an animal exposure volume at a pulsed triga reactor by R. E Simpson( )

3 editions published in 1962 in English and held by 8 WorldCat member libraries 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 spectra from mock fission sources by E Tochilin( )

2 editions published in 1958 in English and held by 7 WorldCat member libraries worldwide

Characteristic curves from different ionizing radiations and their significance in photographic dosimetry by R Golden( )

2 editions published in 1958 in English and held by 7 WorldCat member libraries worldwide

Neutron beam characteristics from the University of California 60-in. cyclotron by E Tochilin( )

2 editions published in 1957 in English and held by 7 WorldCat member libraries worldwide

A simplified film dosimeter for fission neutrons by S. W Ross( )

2 editions published in 1958 in English and held by 6 WorldCat member libraries worldwide

Radiation dosimetry. Supplement 1: Topics in Radiation dosimetry by Frank H Attix( Book )

1 edition published in 1972 in English and held by 5 WorldCat member libraries worldwide

Radiation dosimetry--Topics in radiation dosimetry; supplement 1-( Book )

in English and held by 4 WorldCat member libraries worldwide

Radiation dosimetry by Frank H Attix( Book )

2 editions published in 1965 in English and held by 3 WorldCat member libraries worldwide

Flux and spectral measurements of primary and moderated neutron sources( Book )

2 editions published in 1962 in English and held by 2 WorldCat member libraries 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)
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 William C Roesch( Book )

in English and held by 2 WorldCat member libraries worldwide

Radiation Dosimetry, Second Edition, Volume I: Fundamentals describes the significant aspects and fundamentals of radiation dosimetry. This books deals with the concepts and units of dosimetry; special problems of energy deposition in the microscopic domain; interactions of x and y rays, charged particles, and neutrons with matter; mathematical theory of radiation fields; ionization; and cavity-chamber theory. Other topics discussed include the LET distributions, Compton and photoelectric effect, pair production by photons, dosimetry principles, and interactions of neutrons with tissue element
Radiation dosimetry( Book )

in English and held by 2 WorldCat member libraries worldwide

Sources, fields, measurements, and applications by Frank H Attix( Book )

2 editions published in 1969 in English and held by 2 WorldCat member libraries worldwide

 
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Audience Level
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Audience Level
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Audience level: 0.63 (from 0.56 for Radiation ... to 0.97 for Flux and s ...)

Alternative Names
Tochilin, E.

Tochilin, Eugene

Languages
English (61)