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Reassessment of the technical bases for estimating source terms (NUREG-0956) (1986)

Author	US NRC
Date	July 1986
Classification	6.01.3.90/37 (NUCLEAR SAFETY - SOURCETERM)
Front

EXECUTIVE SUMMARY

1. Introduction

This document describes a major advance in the technology for calculating 
source terms from postulated accidents at U.S. light-water reactors. The improved 
technology consists of (1) an extensive data base from severe accident research 
programs initiated following the TMI accident, (2) a set of coupled and integrated 
computer codes (the Source Term Code Package), which models key aspects of 
fission product behavior under severe accident conditions, and (3) a number of 
detailed mechanistic codes that bridge the gap between the data base and the 
Source Term Code Package. The improved understanding of severe accident 
phenomena has also allowed an identification of significant sources of uncertainty, 
which should be considered in estimating source terms. These sources of 
uncertainty are also described in this document. The current technology provides 
a significant improvement in evaluating source terms over that available at the 
time of the Reactor Safety Study (WASH-1400) and, because of this significance, 
the Nuclear Regulatory Commission staff is recommending its use.

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