Ytterbium: Effect of Pressure and Temperature on Resistance

Higashimura, Takenobu; Ichikawa, Yoneta; Sidei, Tunahiko

doi:10.1126/science.139.3561.1284-a

Cited by 28 publications

(10 citation statements)

References 7 publications

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“…For Nagasaki, these data were in agreement with T57D and T65D gamma-ray doses. For Hiroshima, these data were in better agreement with the new T65D gamma-ray doses than with T57D [29][30][31].…”

Section: Tentative 1965 Doses (T65d)supporting

confidence: 63%

The dosimetry system DS86 and the neutron discrepancy in Hiroshima - historical review, present status, and future options

Rühm¹,

Kellerer²,

Korschinek

et al. 1998

Radiation and Environmental Biophysics

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The historical development of the dosimetry systems for Hiroshima and Nagasaki is outlined from the time immediately after the A-bomb explosions to the publication of the dosimetry system DS86 in 1987, and the present status of the so-called Hiroshima neutron discrepancy is summarized. Several long-lived radionuclides are discussed with regard to their production by neutrons from the A-bomb explosions. With the exception of 63Ni, these radionuclides have not, up to now, been measured in samples from Hiroshima and Nagasaki. Two of them, 63Ni in copper samples and 39Ar in granite samples, were predominantly produced by fast neutrons. 63Ni can be determined by accelerator mass spectrometry with a gas-filled analyzing magnet. It should be measurable, in the near future, in copper samples up to 1500 m from the hypocenter in Hiroshima. 39Ar can be measured in terms of low-level beta-counting. This should be feasible up to a distance of about 1000 m from the hypocenter. Three radionuclides, 10Be, 14C, and 59Ni, were produced predominantly by thermal neutrons with smaller fractions due to the epithermal and fast neutrons, which contribute increasingly more at larger distances from the hypocenter. State-of-the-art accelerator mass spectrometry is likely to permit the determination of 10Be close to the hypocenter and of 14C up to a distance of about 1000 m. 59Ni should be detectable up to a distance of about 1000 m in terms of accelerator mass spectrometry with a gas-filled magnet. The measurements of 10Be, 14C, 39Ar, 59Ni -- and potentially of 131Xe -- can be performed in the same granitic sample that was already analyzed for 36Cl, 41Ca, 6Co, 152Eu, and 154Eu. This will provide extensive information on the neutron spectrum at the specified location, and similarly complete analyses can conceivably be performed on granite samples at other locations.

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Section: Tentative 1965 Doses (T65d)supporting

confidence: 63%

The dosimetry system DS86 and the neutron discrepancy in Hiroshima - historical review, present status, and future options

Rühm¹,

Kellerer²,

Korschinek

et al. 1998

Radiation and Environmental Biophysics

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“…The HPRR was used in calibration studies. Similar studies were concerned with the radiation-induced thermoluminescence in Japanese roof tiles (Hi63).…”

Section: Operation Brenmentioning

confidence: 95%

Dosimetry - A. Physical Dose Estimates for A-bomb Survivors - Studies at Oak Ridge, U.S.A.

Auxier¹

1980

Health Physics

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The radiation exposures for the survivors of the nuclear bombings of Hiroshima and Nagasaki have been determined in the course of studies conducted since the mid-1950's at the Oak Ridge National Laboratory. An extensive series of experiments in Japan, at weapons tests, and in the laboratory were supported by a comprehensive calculational effort to produce the "air dose" distributions and the shielding factors. The absorbed doses to tissues of the body have been calculated for the ease of homogeneous tissue cylinders, and studies of dose distribution in heterogeneous, anthropomorphic configurations are under way. Because the device detonated over Hiroshima was never test fired before or after the bombing, the greatest difficulties were associated with the normalization of the radiation yield of this device. However, after several years of study, the "air dose" curves were obtained to an accuracy of 2 15% for Hiroshima and 2 10% for Nagasaki. Subsequently, the shielding factors for typical dwellings in both cities were determined to a comparable accuracy. Continuing work is focused on obtaining shielding factors for the heavily shielded survivors, the doses to survivors who are now located in the United States and more comprehensive depth dose distributions.

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“…The roots of retrospective luminescence dosimetry lie in work dating back to the early 1960s when it was realized that granular quartz within fired ceramic roof tiles exposed to gamma radiation from the Hiroshima and Nagasaki bombs could be used as a tool for performing dosimetry many years after the exposure event had occurred (Higashimura et al, 1963). This seminal work laid the foundations, not only for radiological application, but also in leading to the identification of dosimeter minerals that subsequently proved to be of central importance to the development of luminescence dating (Aitken, 1985, Aitken, 1998and Bötter-Jensen et al, 2003.…”

Section: Retrospective Dosimetrymentioning

confidence: 99%

“…The results of the formative luminescence work (Higashimura et al, 1963) were available during the development of the first dosimetry model, TD65, and they included determinations of cumulative gamma dose obtained with roof tiles. Although ceramic tiles were used widely on the roofs of traditional Japanese houses, and consequently distributed across residential areas, very few were suitable for dosimetry measurements (Ichikawa et al, 1966) because of the heating they experienced before and after roof collapse during the conflagration that followed bomb detonation, particularly at Hiroshima.…”

Section: Hiroshima and Nagasakimentioning

confidence: 99%

Retrospective and emergency dosimetry in response to radiological incidents and nuclear mass-casualty events: A review

Bailiff

Sholom

McKeever

2016

Radiation Measurements

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Additional information:Use policyThe full-text may be used and/or reproduced, and given to third parties in any format or medium, without prior permission or charge, for personal research or study, educational, or not-for-prot purposes provided that:• a full bibliographic reference is made to the original source • a link is made to the metadata record in DRO • the full-text is not changed in any way The full-text must not be sold in any format or medium without the formal permission of the copyright holders.Please consult the full DRO policy for further details. HIGHLIGHTSReview of the use of luminescence and electron paramagnetic resonance in retrospective and emergency dosimetry.Optically stimulated luminescence (OSL), thermoluminescence (TL) and Electron Paramagnetic Resonance (EPR) results on biological and physical materials.Descriptions of use in emergency and retrospective dosimetry, following large-scale radiological events.http://www.sciencedirect.com/science/article/pii/S1350448716302359 ABSTRACTThis paper reviews recent research on the application of the physical dosimetry techniques of electron paramagnetic resonance (EPR) and luminescence (optically stimulated luminescence, OSL, and thermoluminescence, TL) to determine radiation dose following catastrophic, large-scale radiological events. Such data are used in dose reconstruction to obtain estimates of dose due to the exposure to external sources of radiation, primarily gamma radiation, by individual members of the public and by populations. The EPR and luminescence techniques have been applied to a wide range of radiological studies, including nuclear bomb detonation (e.g., Hiroshima and Nagasaki) nuclear power plant accidents (e.g., Chernobyl), radioactive pollution (e.g., Mayak plutonium facility), and in the future could include terrorist events involving the dispersal of radioactive materials. In this review we examine the application of these techniques in 'emergency' and 'retrospective' modes of operation that are conducted on two distinct timescales. For emergency dosimetry immediate action to evaluate dose to individuals following radiation exposure is required to assess deterministic biological effects and to enable rapid medical triage. Retrospective dosimetry, on the other hand, contributes to the reconstruction of doses to populations and individuals following external exposure, and contributes to the long-term study of stochastic processes and the consequential epidemiological effects. Although internal exposure, via ingestion of radionuclides for example, can be a potentially significant contributor to dose, this review is confined to those dose components arising from exposure to external radiation, which in most studies is gamma radiation.The nascent emergency dosimetry measurement techniques aim to perform direct dose evaluations for individuals who, as members of the public, are most unlikely to be carrying a dosimeter issued for radiation monitoring purposes in the event of a radiation incident. Hence attention has focused on b...

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Ytterbium: Effect of Pressure and Temperature on Resistance

Cited by 28 publications

References 7 publications

The dosimetry system DS86 and the neutron discrepancy in Hiroshima - historical review, present status, and future options

The dosimetry system DS86 and the neutron discrepancy in Hiroshima - historical review, present status, and future options

Dosimetry - A. Physical Dose Estimates for A-bomb Survivors - Studies at Oak Ridge, U.S.A.

Retrospective and emergency dosimetry in response to radiological incidents and nuclear mass-casualty events: A review

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