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Title: ICBC Version 3. 1: TMI-2 (Three Mile Island) Initial and Boundary Conditions data base

Abstract

The TMI-2 initial and boundary conditions data base is a micro computer data base which provides the required initial and boundary conditions to simulate the TMI-2 accident. Additionally, other time series plant measurements related to the accident are included in the data base. Major features of the data base are the ability to plot, manipulate and list data as well as to enter user supplied data (e.g. results of simulations). The user guide provides the instructions for installation and operation of the data base. 10 refs., 21 figs.

Authors:
; ; ; ;
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls (USA)
OSTI Identifier:
5226177
Report Number(s):
GEND-INF-078
ON: DE88007710
DOE Contract Number:
AC07-76ID01570
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; THREE MILE ISLAND-2 REACTOR; REACTOR ACCIDENTS; COMPUTERIZED SIMULATION; DATA BASE MANAGEMENT; PERSONAL COMPUTERS; REACTOR COOLING SYSTEMS; ACCIDENTS; COMPUTERS; COOLING SYSTEMS; DIGITAL COMPUTERS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MANAGEMENT; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Brower, R W, Fackrell, L J, Golden, D W, Harris, M L, and Olaveson, C L. ICBC Version 3. 1: TMI-2 (Three Mile Island) Initial and Boundary Conditions data base. United States: N. p., 1988. Web. doi:10.2172/5226177.
Brower, R W, Fackrell, L J, Golden, D W, Harris, M L, & Olaveson, C L. ICBC Version 3. 1: TMI-2 (Three Mile Island) Initial and Boundary Conditions data base. United States. doi:10.2172/5226177.
Brower, R W, Fackrell, L J, Golden, D W, Harris, M L, and Olaveson, C L. Fri . "ICBC Version 3. 1: TMI-2 (Three Mile Island) Initial and Boundary Conditions data base". United States. doi:10.2172/5226177. https://www.osti.gov/servlets/purl/5226177.
@article{osti_5226177,
title = {ICBC Version 3. 1: TMI-2 (Three Mile Island) Initial and Boundary Conditions data base},
author = {Brower, R W and Fackrell, L J and Golden, D W and Harris, M L and Olaveson, C L},
abstractNote = {The TMI-2 initial and boundary conditions data base is a micro computer data base which provides the required initial and boundary conditions to simulate the TMI-2 accident. Additionally, other time series plant measurements related to the accident are included in the data base. Major features of the data base are the ability to plot, manipulate and list data as well as to enter user supplied data (e.g. results of simulations). The user guide provides the instructions for installation and operation of the data base. 10 refs., 21 figs.},
doi = {10.2172/5226177},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1988},
month = {Fri Jan 01 00:00:00 EST 1988}
}

Technical Report:

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  • The TMI-2 EPICOR-II Resin/Liner Investigation: Low-Level Waste Data Base Development Program, funded by the US Nuclear Regulatory Commission (NRC), is studying the degradation effects in EPICOR-II organic ion exchange resins caused by radiation; examining the adequacy of test procedures recommended in the Branch Technical Position on Waste Forms to meet the requirements of 10 CFR 61 using solidified EPICOR-II resins; obtaining performance information on solidified EPICOR-II ion exchange resins in a disposal environment; and determining the condition of EPICOR-II liners. This report summarizes accomplishments of Fiscal Year 1988. The steps taken in preparation for the third sampling of ion exchangemore » resins from EPICOR-II prefilters PF-8 and -20 determine degradation are noted under the Resin Degradation Task. In the Resin Solidification Task, the results of leachate analysis for Sr-90 are presented. The leachate samples were obtained from testing of waste forms after irradiation. Those results are compared to results from irradiated and unirradiated waste form Cs-137 leachate sample analysis. In the Field Testing Task, both Portland Type I-II cement and Dow vinyl ester-styrene waste forms are being tested in lysimeter arrays located at Argonne National Laboratory in Illinois (ANL-E) and Oak Ridge National Laboratory (ORNL). The study is designed so that continuous data on nuclide release and movement, as well as envirnomental conditions, will be obtained over a 20-year period. results of the third year of data acquisition are presented and discussed. 14 refs., 41 figs., 8 tabs.« less
  • This is a report on the preparation of data from the TMI-2 primary coolant mass flowrate meters for inclusion into the TMI Data Base. The sources of the as-recorded data are discussed, and a description of the instrument is given. An explanation is given of how corrections were made to the as-recorded data and how the uncertainties were calculated. The identifiers attached to each data set in the TMI Data Base are given.
  • Examinations of video tapes generated by a remote camera inserted into each of the 10 boreholes through the previously melted zone of the Three Mile Island-2 (TMI) reactor core have contributed greatly to our present knowledge of the end state configuration of damaged material in the core. In order to use the volumes of the damaged zones for fission product mass balance calculations, the uncertainty associated with calculations of those volumes must be known. This report documents the method used for evaluating the uncertainty.
  • The source range monitor (SRM) data recorded during the first 4 hours of the Three Mile Island Unit No. 2 (TMI-2) accident following reactor shutdown were analyzed. An effort to simulate the actual SRM response was made by performing a series of neutron transport calculations. Primary emphasis was placed on simulating the changes in SRM response to various system events during the accident, so as to obtain useful information about core conditions at the various stages. Based on the known end-state reactor conditions, the major system events, and the acutal SRM readings, self-consistent estimates were made of core liquid level,more » void fraction in the coolant, and locations of core materials. This analysis expands the possible interpretation of the SRM data relative to core damage progression. The results appear to be consistent with other studies of the TMI-2 Accident Evaluation Program, and provide information useful for the developemnt and determination of the TMI-2 accident scenario.« less
  • Supplement 5 to the Safety Evaluation Report (SER) on TMI-1 Restart documents the review by the Nuclear Regulatory Commission (NRC) staff of nine investigations conducted by the NRC Office of Investigations into matters identified as relevant and material to an evaluation of the licensee's management integrity. The staff has included, as part of its evaluation, materials from its review of the GPU v. B and W lawsuit record (NUREG-1020LD, GPU, v. B and W Lawsuit Review and Its Effect on TMI-1) as well as other relevant materials developed since the close of the record in the TMI-1 Restart proceeding. Inmore » developing its position on General Public Utilities Nuclear Corporation's character (i.e., management integrity), the staff evaluated matters that cast doubt on the licensee's character, individually and collectively; considered the remedial actions taken by the licensee; and balanced past improper conduct of the licensee against its subsequent record of remedial actions and performance and record of current senior management of the licensee. The staff concluded that, while the past improper conduct was grave, the remedial actions taken, the subsequent record of performance, and the record of current senior management support a finding that GPUN can and will operate TMI-1 without undue risk to the health and safety of the public.« less