Validation of the ORIGIEN-S Code for Predicting Radionuclide Inventories in Used CANDU Fuel

📖 The Scoop

This is volume 6, dealing with the zion nuclear power plant, of a seven-volume report of work done at battelle's columbus laboratories to estimate the amount of radioactive material that could be released from light water reactor (lwr) power plants under specific, hypothetical accident conditions. to make these estimates, five power plants were selected that represent the major categories of lwrs: three pressurized water reactors (pwrs) and two boiling water reactors (bwrs). specifications and data from these plants, along with data from laboratory experiments, were input to computer codes designed to describe various conditions prevailing inside an operating reactor. ultimately, these computer codes provide an estimate of how much radioactive material would be able to escape to the environment if a specific series of events (an "accident sequence") took place. volume 6 of this report deals with the zion power station, a westinghouse pwr housed in a large, dry, high-pressure containment building. the two accident sequences analyzed for the zion plant were selected for comparative purposes rather than as being representative of a wide range of possible physical conditions. the computer codes used in the analyses are those used throughout all volumes of this report and are representative of the state of the art available in 1983. other power plants included in the study are surry pwr (volumes 1 and 5); peach bottom bwr (volume 2); grand gulf bwr (volume 3); and sequoyah pwr (volume 4). the seventh volume will address technical questions raised during peer review meetings sponsored by the nuclear regulatory commission.

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