Conn. Agencies Regs. § 19-24-4
(a) (1) "Dose," as used in sections 19-24-1 to 19-24-14, inclusive, means the quantity of radiation absorbed, per unit of mass, by the body or by any portion of the body. When a dose during a period of time is specified, the dose means the total quantity of radiation absorbed, per unit of mass, by the body or by any portion of the body during such period of time. Several different units of dose are in current use. The definitions are set forth in subdivisions (2) and (3) below.
(3) The "rem," as used in said sections, is a measure of the dose of any ionizing radiation to body tissue in terms of its estimated biological effect relative to a dose of one roentgen (r) of x-rays. (One millirem (mrem) = 0.001 rem.) The relation of the rem to other dose units depends upon the biological effect under consideration and upon the conditions of irradiation. For the purpose of this regulation, any of the following is considered to be equivalent to a dose of one rem:
(D) A dose of five-hundredths rad due to particles heavier than protons and with sufficient energy to reach the lens of the eye. If it is more convenient to measure the neutron flux, or equivalent, than to determine the neutron dose in rads, as provided in subparagraph (C) above, one rem of neutron radiation may for purposes of sections 19-24-1 to 19-24-14, inclusive, be assumed to be equivalent to fourteen million neutrons per square centimeter incident upon the body; or, if there exists sufficient information to estimate with reasonable accuracy the approximate distribution in energy of the neutrons, the incident number of neutrons per square centimeter equivalent to one rem may be estimated from the following table:
| Neutron energy (Mev) | Number of neutrons per square centimeter equivalent to a dose of 1 rem (neutrons/cm2) | Average Flux to deliver 100 millirem in 40 hours (neutrons/cm2 per sec.) | |
| Thermal | . . . . . . . . | 970 x 106 | 670 |
| 0.0001 | . . . . . . . . | 720 x 106 | 500 |
| 0.005 | . . . . . . . . | 820 x 106 | 570 |
| 0.02 | . . . . . . . . | 400 x 106 | 280 |
| 0.1 | . . . . . . . . | 120 x 106 | 80 |
| 0.5 | . . . . . . . . | 43 x 106 | 30 |
| 1.0 | . . . . . . . . | 26 x 106 | 18 |
| 2.5 | . . . . . . . . | 29 x 106 | 20 |
| 5.0 | . . . . . . . . | 26 x 106 | 18 |
| 7.5 | . . . . . . . . | 24 x 106 | 17 |
| 10 | . . . . . . . . | 24 x 106 | 17 |
| 10 to 30 | . . . . . . . . | 14 x 106 | 10 |
(b) Units of radioactivity.
(2) For purposes of said sections it may be assumed that the daughter activity concentrations in the following table are equivalent to an air concentration of 10-7 microcuries of Radon 222 per milliliter of air in equilibrium with the daughters RaA, RaB, RaC, and RaC.
| Maximum time between collection and measurement (hours)1 | Alpha-emitting daughter activity collected per milliliter of air | ||
| Microcuries/cc | Total alpha disintegrations per minute per cc. | ||
| 0.5 | . . . . . . . . . . . | 7.2 x 10-8 | 0.16 |
| 1 | . . . . . . . . . . . | 4.5 x 10-8 | 0.10 |
| 2 | . . . . . . . . . . . | 1.3 x 10-8 | 0.028 |
| 3 | . . . . . . . . . . . | 0.3 x 10-8 | 0.0072 |
1 The duration of sample collection and the duration of measurement should be sufficiently short compared to the time between collection and measurement, as not to have a statistically significant effect upon the results.
(3) Natural uranium and natural thorium.
(Effective October 1, 1982)