[en] 1 - Description of problem or function: This code was developed under sponsorship of the Nuclear Regulatory Commission to serve as a tool for assessing radiation doses that may be associated with consumer products that contain radionuclides. The code calculates radiation dose equivalents resulting from user-supplied scenarios of exposures to radionuclides contained in or released from sources that contain radionuclides. Dose equivalents may be calculated to total body, skin surface, skeletal bone, testes, ovaries, liver, kidneys, lungs, and maximally exposed segments of the gastrointestinal tract from exposures via (1) direct, external irradiation by photons (including Bremsstrahlung) emitted from the source, (2) external irradiation by photons during immersion in air containing photon-emitting radionuclides that have escaped from the source, (3) internal exposures by all radiations emitted by inhaled radionuclides that have escaped from the source, and (4) internal exposures by all radiations emitted by ingested radionuclides that have escaped from the source. 2 - Method of solution: Organ dose equivalents are approximated in two ways, depending on the exposure type. For external exposures, energy specific organ-to-skin-surface dose conversion ratios are used to approximate dose equivalents to specific organs from doses calculated to a point on the skin surface. The organ-to-skin ratios are incorporated in organ- and nuclide-specific dose rate factors, which are used to approximate doses during immersion in contaminated air. For internal exposures, 50 year dose equivalents are calculated using organ- and nuclide-specific, 50 year dose conversion factors. Doses from direct, external exposures are calculated using the energy-specific dose conversion ratios, user supplied exposure conditions, and photon flux approximations for eleven source geometries. Available source geometries include: point, shielded and unshielded; line, shielded and unshielded; disk, shielded and unshielded; cylindrical surface, unshielded; uniform, semi-infinite volume, shielded and unshielded; uniform, infinite slab, shielded and unshielded; uniform, non-absorbing cylindrical volume, unshielded; and uniform, non-absorbing spherical volume, unshielded; and uniform, self-absorbing cylindrical volume, shielded and unshielded. External doses from immersion in contaminated air are calculated using the organ- and nuclide-specific dose rate conversion factors, user supplied exposure conditions, and an infinite to finite air volume correction formula. External doses are calculated using the appropriate inhalation or ingestion, 50 year, organ- and nuclide- specific dose conversion factors and user supplied exposure conditions. 3 - Restrictions on the complexity of the problem: Variable dimensioning limits: the number of nuclide decay chains to 25, the number of sources in an exposure event to 25, and the number of absorbing materials between the source and dose point to 4 (excluding air)