C-14 (Carbon-14) Radiation Safety Data
Published: Aug 21, 2023
Source: Ionactive Radiation Protection Resource
Half life: 5730 years
Specific activity: 1.65×1011 Bq/g
Decay product: N-14 (non radioactive)
Significant emissions (keV) [C-14 (Carbon-14)]
In the data below, % refers to the probability of emission of a particular type of radiation at a specified energy
Gamma / x-ray: n/a
Beta (Emax): 157 keV (100 %)
Alpha particles: n/a
External exposure (in air) [C-14 (Carbon-14)]
The values below are specified as mSv/h for either 1 MBq of activity or an area source of 1 MBq/m2 depending on the geometry. Unless specified below, any bremsstrahlung dose rate is not specified. (HP 0.07) represents a skin dose rate and (HP 10) represents an 'at depth' tissue dose rate (> 10mm).
Point source (at 30cm)
Point source : 0.0 mSv/h
Infinite place source (at 10 cm)
Beta (HP 0.07) : 0.0 mSv/h
Photon (HP 0.07) : 0.0 mSv/h
Photons (HP 10) : 0.0 mSv/h
External exposure (arising from personal contamination) [C-14 (Carbon-14)]
The values below are either for uniform contamination on the skin (for 1 kBq/cm2) or as a single droplet (1 kBq) and are specified in mSv/h. It is assumed that no PPE is being worn which would attenuate the radiation.
Uniform deposit on the skin: 0.324 mSv/h
0.05ml droplet on the skin: 0.0027 mSv/h
Shielding (external radiation) [C-14 (Carbon-14)]
In the data below beta shielding is specified as mm of material to provide 100% absorption of the beta particle (or electron). Gamma (and x-ray) shielding is specified in terms of mm of material relating to 1 TVT or 1 HVT. The TVT is the thickness of material (in mm) which will reduce the radiation intensity (dose rate) down to 1/10 of the pre-shielded dose rate. The HVT is the thickness of material (in mm) which will reduce the radiation intensity down to 1/2 of the pre-shielded dose rate
Beta radiation (for 100% absorption)
Typical PPE (glove): total absorption
Gamma / x-ray radiation (TVT and HVT)
Pure beta emitter - TVT and HVT are not relevant for primary radiation.
Internal exposure [C-14 (Carbon-14)]
The data featured below is derived for employees who work with ionising radiation (and are therefore subject to dose limits specified by the Ionising Radiations Regulations 2017 in the UK, and similar regulation around the world). Whilst not directly applicable to public exposure (e.g. exposure resulting from environmental releases - either planned or accidental), the data will provide a good indication of likely exposures and is therefore adequate for general research, illustration and asking 'what if?' type questions. If you need professional advice, please consider consulting a Radiation Protection Adviser (RPA).
Internal radiation exposure generally means the intake of a radioactive substances by inhalation, ingestion or through cuts (or absorption) in the skin. For this resource assume cuts / absorption are similar to the ingestion values.
This data provides the dose delivered (committed effective dose equivalent) for an intake of [C-14 (Carbon-14)] by inhalation or ingestion to yield 1mSv effective dose. The dose value provided assumes that all the dose is delivered in the first year of intake, in reality this will vary greatly with radioisotope due to a combination of physical half-life, biological half-life and the biochemical behaviour of the particular radioactive substances in the body.
Target organ: Whole body
Inhalation dose (1 mSv): 1.7 MBq
Ingestion dose (1 mSv): 1.7 MBq
Workplace Monitoring and Dosimetry [C-14 (Carbon-14)]
Workplace monitoring means using techniques to detect ionising radiation sources in the working environment (e.g. on benchtops, floors, walls, drains and similar). The monitoring can be direct (e.g. using a radiation detector to gain real time measurements of dose rate and / or activity) or indirect (where a smear / wipe of an area is made and this is then offered up to a radiation monitoring probe or placed in scintillation fluid for liquid scintillation counting).
Dosimetry is used to measure personal exposure from a source of ionising radiation. Passive dosimetry (e.g. film badge, thermoluminescent dosimeter - TLD etc) is worn on the body (e.g. trunk / extremities / near eyes) and measures total integrated dose over time. Active dosimetry (e.g. electronic personal dosimeter - EPD, personal electronic dosimeter - PED etc) is worn on the trunk of the body and provides real time accumulated dose (and sometimes dose rate) - audible dose and dose rate alarms may also be available. Biological monitoring [bioassay] (e.g. urine sampling, faecal sampling etc) takes biological samples from the body where they are analysed in a sensitive detector to determine activity of radionuclides in the body (usually due to the intake of radioactive material by inhalation, ingestion or through absorption / cuts in the skin).
Workplace monitoring [C-14 (Carbon-14)]
- Area wipes following by liquid scintillation counting.
- Geiger-Mueller (GM) tube with thin end window (e.g. Mini EP15) - about 10% efficiency.
- Beta Scintillation probe with large area window (e.g. Thermo HP-380B) - about 28% efficiency.
Dosimetry [C-14 (Carbon-14)]
- Urine sampling followed by laboratory assessment (bioassay)
Occurrences and uses [C-14 (Carbon-14)]
- C-14 is formed naturally in the upper atmosphere (via nuclear reactions of atmospheric nitrogen with thermal neutrons created naturally by cosmic rays).
- C-14 present in all living things [10-10 % C-14 compared to 98.89 % C-12, the rest being C-13].
- Formed during atomic (nuclear) explosions.
- A product of nuclear fission (i.e. in a nuclear reactor). Can be considered a waste product and / or a useful by-product (see below).
- Carbon 14 Dating [Radiocarbon dating] - a method used to date objects, by looking at the ratio of C-14 to C-12 in objects that are no longer absorbing carbon (such as a dead tree). This method can date objects with an age up to about 60,000 years.
- Tracer radionuclides - used in environmental studies, used as a marker in research (i.e. radiolabelling of molecules so that carbon atoms can be tracked through chemical and biological processes). Generally radioactivity is in the 37 kBq - 37 MBq range for most studies.