Conceptual model for deriving the repository source term
Creators
- 1. Roy F. Weston, Inc./Rogers and Assoc. Engineering Corp., Rockville, MD
- 2. Pacific Northwest Lab., Richland, WA
- 3. Department of Energy, Washington, DC
Description
Part of a strategy for evaluating the compliance of geologic repositories with Federal regulations is a modeling approach that would provide realistic release estimates for a particular configuration of the engineered-barrier system. The objective is to avoid worst-case bounding assumptions that are physically impossible or excessively conservative and to obtain probabilitistic estimates of (1) the penetration time for metal barriers and (2) radionuclide-release rates for individually simulated waste packages after penetration has occurred. The conceptual model described in this paper will assume that release rates are explicitly related to such time-dependent processes as mass transfer, dissolution and precipitation, radionuclide decay, and variations in the geochemical environment. The conceptual model will take into account the reduction in the rates of waste-form dissolution and metal corrosion due to a buildup of chemical reaction products. The sorptive properties of the metal-barrier corrosion products in proximity to the waste form surface will also be included. Cumulative released from the engineered-barrier system will be calculated by summing the releases from a probabilistically generated population of individual waste packages. 14 refs., 7 figs
Additional details
Publishing Information
- Publisher
- Materials Research Society.
- Imprint Place
- Pittsburgh, PA (USA)
- ISBN
- 0-931837-09-X
- Imprint Title
- Scientific basis for Nuclear Waste Management VIII
- Journal Page Range
- p. 439-450.
Conference
- Title
- Materials Research Society annual meeting.
- Dates
- 26-29 Nov 1984.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17079269
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTERIZED SIMULATION; CORROSION; GROUND WATER; HIGH-LEVEL RADIOACTIVE WASTES; MATHEMATICAL MODELS; RADIOACTIVE WASTE FACILITIES; RADIONUCLIDE MIGRATION; SAFETY ENGINEERING; SOURCE TERMS; SPENT FUELS; THEORETICAL DATA; TIME DEPENDENCE
- Descriptors DEC
- CHEMICAL REACTIONS; DATA; ENERGY SOURCES; ENVIRONMENTAL TRANSPORT; FUELS; HYDROGEN COMPOUNDS; INFORMATION; MASS TRANSFER; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; NUMERICAL DATA; OXYGEN COMPOUNDS; POLAR SOLVENTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; SIMULATION; SOLVENTS; WASTES; WATER