The Characterization of Carbon-14 Rich Deposits Formed in the Nitrogen Gas Annulus Systems of 500 MWe CANDU Reactors

Greening, Frank R.

doi:10.1524/ract.1989.47.4.209

Cited by 3 publications

(1 citation statement)

References 29 publications

(33 reference statements)

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“… (110) Johnson (1989) followed the biokinetics of 14 C for 146 d after administration to rats by intratracheal instillation of 14 C-bearing material obtained from air filters during re-tubing of a CANDU reactor (Greening, 1989). No 14 C above background was detected in urine or liver, indicating negligible dissolution in the lungs (or alimentary tract).…”

Section: Carbon (Z = 6)mentioning

confidence: 99%

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2

Paquet¹,

Bailey²,

Leggett³

et al. 2016

Ann ICRP

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The 2007 Recommendations of the International Commission on Radiological Protection (ICRP, 2007) introduced changes that affect the calculation of effective dose, and implied a revision of the dose coefficients for internal exposure, published previously in the Publication 30 series (ICRP, 1979, 1980, 1981, 1988b) and Publication 68 (ICRP, 1994b). In addition, new data are available that support an update of the radionuclide-specific information given in Publications 54 and 78 (ICRP, 1988a, 1997b) for the design of monitoring programmes and retrospective assessment of occupational internal doses. Provision of new biokinetic models, dose coefficients, monitoring methods, and bioassay data was performed by Committee 2, Task Group 21 on Internal Dosimetry, and Task Group 4 on Dose Calculations. A new series, the Occupational Intakes of Radionuclides (OIR) series, will replace the Publication 30 series and Publications 54, 68, and 78. Part 1 of the OIR series has been issued (ICRP, 2015), and describes the assessment of internal occupational exposure to radionuclides, biokinetic and dosimetric models, methods of individual and workplace monitoring, and general aspects of retrospective dose assessment. The following publications in the OIR series (Parts 2–5) will provide data on individual elements and their radioisotopes, including information on chemical forms encountered in the workplace; a list of principal radioisotopes and their physical half-lives and decay modes; the parameter values of the reference biokinetic model; and data on monitoring techniques for the radioisotopes encountered most commonly in workplaces. Reviews of data on inhalation, ingestion, and systemic biokinetics are also provided for most of the elements. Dosimetric data provided in the printed publications of the OIR series include tables of committed effective dose per intake (Sv per Bq intake) for inhalation and ingestion, tables of committed effective dose per content (Sv per Bq measurement) for inhalation, and graphs of retention and excretion data per Bq intake for inhalation. These data are provided for all absorption types and for the most common isotope(s) of each element. The electronic annex that accompanies the OIR series of reports contains a comprehensive set of committed effective and equivalent dose coefficients, committed effective dose per content functions, and reference bioassay functions. Data are provided for inhalation, ingestion, and direct input to blood. The present publication provides the above data for the following elements: hydrogen (H), carbon (C), phosphorus (P), sulphur (S), calcium (Ca), iron (Fe), cobalt (Co), zinc (Zn), strontium (Sr), yttrium (Y), zirconium (Zr), niobium (Nb), molybdenum (Mo), and technetium (Tc).

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Section: Carbon (Z = 6)mentioning

confidence: 99%

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2

Paquet¹,

Bailey²,

Leggett³

et al. 2016

Ann ICRP

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Behavior of carbon-14 in waste packages for spent fuel in a tuff repository

Konynenburg

1994

Waste Management

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CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review

Greening¹

2017

Kerntechnik

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In the event of a pressure tube leak from a small through-wall crack during CANDU reactor operations, there is a regulatory requirement – referred to as Leak Before Break (LBB) – for the licensee to demonstrate that there will be sufficient time for the leak to be detected and the reactor shut down before the crack grows to the critical size for fast-uncontrolled rupture. In all currently operating CANDU reactors, worldwide, this LBB requirement is met via continuous dew point measurements of the CO2 gas circulating in the reactor's Annulus Gas System (AGS). In this paper the historical development and current status of this leak detection capability is reviewed and the use of moisture injection tests as a verification procedure is critiqued. It is concluded that these tests do not represent AGS conditions that are to be expected in the event of a real pressure tube leak.

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The Characterization of Carbon-14 Rich Deposits Formed in the Nitrogen Gas Annulus Systems of 500 MWe CANDU Reactors

Cited by 3 publications

References 29 publications

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2

ICRP Publication 134: Occupational Intakes of Radionuclides: Part 2

Behavior of carbon-14 in waste packages for spent fuel in a tuff repository

CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review

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