LOW-RADIOACTIVITY-LEVEL WASTE TREATMENT. PART I. LABORATORY DEVELOPMENT OF A SCAVENGING-PRECIPITATION ION-EXCHANGE PROCESS FOR DECONTAMINATION OF PROCESS WATER WASTES

PDF Version Also Available for Download.

Description

A scavenging-precipitation ion-exchange process using phenolic resins was developed to decontaminate lowradioactivity-level process water waste prior to discharge to the environment. In laboratory and small engineeringscale tests, greater than 99.9% of the cesium and strontium, the principal biological hazards were removed from ORNL low-level waste, and the total activity level was lowered to less than the maximum permissible concentration recommended for populations in the neighborhood of atomic energy installations. The water was treated by a scavenging-precipitation with sodium hydroxide, pH 11.7, and ferrous sulfate, copperas-5 ppm Fe, to remove suspended solids and soluble hardness, clarified, and then passed through a ... continued below

Physical Description

Pages: 41

Creation Information

Holcomb, R.R. July 10, 1963.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Author

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Description

A scavenging-precipitation ion-exchange process using phenolic resins was developed to decontaminate lowradioactivity-level process water waste prior to discharge to the environment. In laboratory and small engineeringscale tests, greater than 99.9% of the cesium and strontium, the principal biological hazards were removed from ORNL low-level waste, and the total activity level was lowered to less than the maximum permissible concentration recommended for populations in the neighborhood of atomic energy installations. The water was treated by a scavenging-precipitation with sodium hydroxide, pH 11.7, and ferrous sulfate, copperas-5 ppm Fe, to remove suspended solids and soluble hardness, clarified, and then passed through a carboxylic-phenolic ion-exchange resin to sorb the remaining radionuclides. After passage of 1,500 to 2,000 resin-bed volumes, the resin was eluted with 10 volumes of 0.5 M HNO/sub 3/. Sodium carbonate can be added in the precipitation step to aid the quantitative precipitation of calcium for wastes that contain small amounts of phosphates, or alternatively, an extra ion-exchange column of carboxylic resin can be used to remove calcium and thus conserve the capacity of the phenolic resin for cesium and strontium. Three kinds of studies were made: batch laboratory-scale studies, continuous nonradioactive runs at 15 liters/hr, and runs with radioactive waste at 60 liters/ hr. These studies led to a pilot-plant demonstration of the process. The process is similar to that reported in ORNL-3036, which describes the use of a sulfonic-phenolic resin and a 5 M HCl regenerant. (auth)

Physical Description

Pages: 41

Source

  • Other Information: Orig. Receipt Date: 31-DEC-63

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

  • Report No.: ORNL-3322
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4686390 | External Link
  • Office of Scientific & Technical Information Report Number: 4686390
  • Archival Resource Key: ark:/67531/metadc1033034

Collections

This report is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • July 10, 1963

Added to The UNT Digital Library

  • Oct. 18, 2017, 7:39 a.m.

Description Last Updated

  • Oct. 23, 2017, 1:37 p.m.

Usage Statistics

When was this report last used?

Congratulations! It looks like you are the first person to view this item online.

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

Citations, Rights, Re-Use

Holcomb, R.R. LOW-RADIOACTIVITY-LEVEL WASTE TREATMENT. PART I. LABORATORY DEVELOPMENT OF A SCAVENGING-PRECIPITATION ION-EXCHANGE PROCESS FOR DECONTAMINATION OF PROCESS WATER WASTES, report, July 10, 1963; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc1033034/: accessed December 15, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.