Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

Abstract

DISCLAIMERPortions of this document may be illegible electronic image products. Images are produced from the best available original document. ABSTRACTThe CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 199 1. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermalhydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/ evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be --viewed as a tool designed to assist the knowledgeable reactor safety analyst in evaluating the consequences of specific modeling assumptions.6/30/97... Rev. 0111

Heat, Mass and Aerosol Transfers in Spray Conditions for Containment Application

“…As we can see the global spray efficiency seems to have a minimum for aerosol size around 0.5 µm. This result corresponds to the fact that, for these ranges of aerosol and droplets size, mechanical effects have a poor efficiency and thermophoresis effects become negligible (13) .…”

The accumulator effects on in-vessel severe accident progression of a three loop PWR nuclear power plant in a SBLOCA without safety injection system

“…4. The composition, solidus, liquids and ablation temperatures of concrete in the cavity are present in Table 2 (Murata et al, 1997). The density of Limestone/ Limestone is 2340 kg/m 3 .…”

Reassessment of selected factors affecting siting of Nuclear Power Plants

“…The characteristics of Peach Bottom release categories are summarized in Table 3. 7. Station blackout sequences as a class are the largest contributor to mean core damage frequency and are the dominant plant damage state leading to early, late, and no containment failures.…”