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Title: Analysis data on samples from the TMI-2 reactor-coolant system and reactor-coolant bleed tank

Abstract

Two liquid samples from the Three Mile Island Unit 2 (TMI-2) Reactor Coolant System (RCS) and three liquid samples from the three Reactor Coolant Bleed Tanks (RCBT) were taken during the time period March 29, 1979 to August 14, 1980. The samples were analyzed for radionuclide concentrations by two independent laboratories, Exxon Nuclear Idaho Co., Inc. (ENICO) and EG and G Idaho, Inc. at the Idaho National Engineering Laboratory (INEL). The RCS sample taken on March 29, 1979 was also analyzed by Science Applications, Inc. (SAI). This report presents the methods used and the results of these analyes. 14 tables.

Authors:
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls (USA)
OSTI Identifier:
5330865
Report Number(s):
GEND-INF-021
ON: DE82016227; TRN: 82-013429
DOE Contract Number:
AC07-76ID01570
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions of document are illegible
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; COOLANTS; EMISSION SPECTROSCOPY; EXPERIMENTAL DATA; GAMMA SPECTROSCOPY; RADIOACTIVITY; RADIOCHEMICAL ANALYSIS; RADIOISOTOPES; CHEMICAL ANALYSIS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; ISOTOPES; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; REACTORS; SPECTROSCOPY; 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

Nitschke, R.L. Analysis data on samples from the TMI-2 reactor-coolant system and reactor-coolant bleed tank. United States: N. p., 1982. Web. doi:10.2172/5330865.
Nitschke, R.L. Analysis data on samples from the TMI-2 reactor-coolant system and reactor-coolant bleed tank. United States. doi:10.2172/5330865.
Nitschke, R.L. Sat . "Analysis data on samples from the TMI-2 reactor-coolant system and reactor-coolant bleed tank". United States. doi:10.2172/5330865. https://www.osti.gov/servlets/purl/5330865.
@article{osti_5330865,
title = {Analysis data on samples from the TMI-2 reactor-coolant system and reactor-coolant bleed tank},
author = {Nitschke, R.L.},
abstractNote = {Two liquid samples from the Three Mile Island Unit 2 (TMI-2) Reactor Coolant System (RCS) and three liquid samples from the three Reactor Coolant Bleed Tanks (RCBT) were taken during the time period March 29, 1979 to August 14, 1980. The samples were analyzed for radionuclide concentrations by two independent laboratories, Exxon Nuclear Idaho Co., Inc. (ENICO) and EG and G Idaho, Inc. at the Idaho National Engineering Laboratory (INEL). The RCS sample taken on March 29, 1979 was also analyzed by Science Applications, Inc. (SAI). This report presents the methods used and the results of these analyes. 14 tables.},
doi = {10.2172/5330865},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat May 01 00:00:00 EDT 1982},
month = {Sat May 01 00:00:00 EDT 1982}
}

Technical Report:

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  • This report compiles the analytical results and sample history of four reactor coolant samples, four reactor coolant bleed-tank samples, two reactor coolant bleed-tank in situ gamma scans, and one steam generator sample obtained from TMI-2 at various times. EG and G Idaho, Inc., Exxon Nuclear Idaho Company Inc., Science Applications, Inc., and Hanford Engineering Development Laboratory performed the various analyses.
  • This data package presents field data and analytical results for vapor sampling activities associated with the AN tank farm ventilation system sampling event performed on July 27, 2000. Vapor sampling was performed to validate existing air emission estimates and to provide data for future air permitting applications.
  • The objective of this work was to help characterize the contamination on the primary system surfaces of TMI-2 in support of decontamiation process selection and planning. The approach adopted was to use available analytical techniques or models to describe the release of contamination from the core region and its subsequent transport and deposition in the primary coolant loops. While the results obtained are subject to some uncertainty, they do lead to significant conclusions for decontamination process selection and planning.
  • The physical and chemical properties of six elements were studied and combined with cost estimates to determine the feasibility of adding them to the TMI-2 reactor coolant to depress k/sub eff/ to less than or equal to 0.95. Both soluble and insoluble forms of the elements B, Cd, Gd, Li, Sm, and Eu were examined. Criticality calculations were performed by Oak Ridge National Laboratory to determine the absorber concentration required to meet the 0.95 k/sub eff/ criterion. The conclusion reached is that all elements with the exception of boron have overriding disadvantages which preclude their use in this reactor. Solubilitymore » experiments in the reactor coolant show that boron solubility is the same as that of boron in pure aqueous solutions of sodium hydroxide and boric acid; consequently, solubility is not a limiting factor in reaching the k/sub eff/ criterion. Examination of the effect of pH on sodium requirements and costs for processing to remove radionuclides revealed a sharp dependence; small decreases in pH lead to a large decrease in both sodium requirements and processing costs. Boron addition to meet any contemplated reactor safety requirements can be accomplished with existing equipment; however, this addition must be made with the reactor coolant system filled and pressurized to ensure uniform boron concentration.« less