Thermoluminescence Dosimetry of Gamma Rays from Atomic Bombs in Hiroshima and Nagasaki

Ichikawa, Yoneta; Higashimura, Takenobu; Sidei, Tunahiko

doi:10.1097/00004032-196603000-00013

Cited by 31 publications

(9 citation statements)

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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: 62%

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: 62%

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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“…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. Alternative ceramic samples were available in the form of façade and decorative tiles fastened to concrete buildings, albeit at fewer locations.…”

Section: Hiroshima and Nagasakimentioning

confidence: 99%

“…The formulation of DS02 also included the additional luminescence determinations of cumulative gamma dose to ceramics that had been obtained after the publication of DS86, and various aspects of earlier measurements were re-examined Maruyama et al, 2005), including the early work by Ichikawa et al (1966) that had provided key data at distances of less than 1 km from the hypocenter in both cities. The measurement data had been subject to screening, with samples selected on the basis of minimal shielding and where the age of the building was known.…”

Section: Current Dosimetry System Ds02mentioning

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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“…TL and OSL have been used in a limited number of epidemiologic studies including many of the major dose reconstructions carried out to date, e.g., for A-bomb survivors (Young and Kerr, 2005;Ichikawa et al, 1996Ichikawa et al, , 1987Nagatomo et al, 1988Nagatomo et al, , 1991Hoshi et al, 1989), Nevada test site exposures (Haskell et al, 1994), for the Chernobyl accident (Stepanenko et al, 2003;Bailiff et al, 2004aBailiff et al, , 2005 and more recently, for Semipalatinsk nuclear test site exposures (Bailiff et al, 2004b;Stepanenko et al, 2006a-c. Göksu et al, 2006Sato et al, 2006;Simon et al, 2005;Takada et al, 1999). In all cases, building materials were evaluated for TL or OSL signals.…”

Section: Use Of Tl/osl In Epidemiologic Studiesmentioning

confidence: 99%

BiodosEPR-2006 consensus committee report on biodosimetric methods to evaluate radiation doses at long times after exposure

Simon

Bailiff

Bouville

et al. 2007

Radiation Measurements

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'kaev, Alexander V.; Tucker, James D.; and Wieser, Albrecht, "BiodosEPR-2006 consensus committee report on biodosimetric methods to evaluate radiation doses at long times after exposure" (2007 AbstractThe requirements for biodosimetric techniques used at long times after exposure, i.e., 6 months to more than 50 years, are unique compared to the requirements for methods used for immediate dose estimation. In addition to the fundamental requirement that the assay measures a physical or biologic change that is proportional to the energy absorbed, the signal must be highly stable over time to enable reasonably precise determinations of the absorbed dose decades later. The primary uses of these biodosimetric methods have been to support long-term health risk (epidemiologic) studies or to support compensation (damage) claims. For these reasons, the methods must be capable of estimating individual doses, rather than group mean doses. Even when individual dose estimates can be obtained, inter-individual variability remains as one of the most difficult problems in using biodosimetry measurements to rigorously quantify individual exposures. Other important criteria for biodosimetry methods include obtaining samples with minimal invasiveness, low detection limits, and high precision. Cost and other practical limitations generally prohibit biodosimetry measurements on a large enough sample to replace analytical dose reconstruction in epidemiologic investigations. However, these measurements can be extremely valuable as a means to corroborate analytical or model-based dose estimates, to help reduce uncertainty in individual doses estimated by other methods and techniques, and to assess bias in dose reconstruction models. There has been extensive use of three biodosimetric techniques in irradiated populations: EPR (using tooth enamel), FISH (using blood lymphocytes), and GPA (also using blood); these methods have been supplemented with luminescent methods applied to building materials and artifacts. A large number of investigations have used biodosimetric methods many years after external and, to a lesser extent, internal exposure to reconstruct doses received from accidents, from occupational exposures, from environmental releases of radioactive materials, and from medical exposures. In most applications, the intent has been to either identify highly exposed persons or confirmed suspected exposures. Improvements in methodology, however, have led many investigators to attempt quantification of whole-body doses received, or in a few instances, to estimate organ doses. There will be a continued need for new and improved biodosimetric techniques not only to assist in future epidemiologic investigations but to help evaluate the long-term consequences following nuclear accidents or events of radiologic terrorism.

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Thermoluminescence Dosimetry of Gamma Rays from Atomic Bombs in Hiroshima and Nagasaki

Cited by 31 publications

References 0 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

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

BiodosEPR-2006 consensus committee report on biodosimetric methods to evaluate radiation doses at long times after exposure

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