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Present Status of the U. S. Program on the Solidification of High Level Wastes ALBERT G. BLASEWITZ, Manager KENNETH J. SCHNEIDER, Research Associate Engineering Demonstration Section Battelle Memorial Institute Pacific Northwest Laboratory Richland, Washington INTRODUCTION The conversion of high-level liquid wastes to solids as a pretreatment for storage is being developed in laboratories of nearly all countries with significantly near-future nuclear energy. Solidification is being developed so widely because it is the only practical and reasonably attainable technique for achieving a substantial increase in the safety associated with the storing and disposal of the high-level waste from the nuclear power industry. Four processes for solidification of these wastes have been developed in the U. S. A., to the point of radioactive demonstration on an engineering scale. The four processes are pot calcination, spray solidification, phosphate glass solidification, and fluidized bed calcination. The pot, spray, and phosphate glass processes have been demonstrated for the AEC on a full-level, engineering-scale in the Waste Solidification Engineering Prototypes (WSEP) by Battelle-Northwest at Richland, Washington, since November 1966. Demonstrations will be completed later in 1970. The fluidized bed process has been demonstrated for the AEC in a large capacity plant in the Waste Calcining Facility (WCF) by Idaho Nuclear Corporation at NRTS, operating on intermediate- level wastes since 1963. Most of the development work is completed and most of the basic technology has been obtained (1,2). The processes have been demonstrated to be technically feasible and ready for commercial application. Following an overall review of the management and long-term disposition of high level liquid wastes (3,4), the Atomic Energy Commission published a proposed statement of policy in the June 3, 1969 Federal Register. The proposed policy would require the following actions in regard to high-level waste management: 1) a commercial fuel reprocessing plant's inventory of high-level liquid radioactive waste will be limited to the quantity produced in the prior five yr and high-level liquid radioactive wastes in excess of the authorized inventory must be converted to an AEC-approved solid form; and 2) all high-level radioactive wastes must be transferred in the approved solid form to a Federal repository as soon as practicable, but in no event later than 10 yr following separation of the fission products from the irradiated fuel. It is anticipated that this requirement to solidify the high-level liquid waste prior to its shipment to a Federal repository will be formalized in the near future. The cost of high-level waste management involving solidification in combination with interim liquid storage, interim solid storage, and transportation to final -141-
Object Description
Purdue Identification Number | ETRIWC197013 |
Title | Present status of the U.S. program on the solidification of high level wastes |
Author |
Blasewitz, Albert G. Schneider, Kenneth J. |
Date of Original | 1970 |
Conference Title | Proceedings of the 25th Industrial Waste Conference |
Conference Front Matter (copy and paste) | http://earchives.lib.purdue.edu/u?/engext,18196 |
Extent of Original | p. 141-153 |
Series | Engineering extension series no. 137 |
Collection Title | Engineering Technical Reports Collection, Purdue University |
Repository | Purdue University Libraries |
Rights Statement | Digital object copyright Purdue University. All rights reserved. |
Language | eng |
Type (DCMI) | text |
Format | JP2 |
Date Digitized | 2009-06-09 |
Capture Device | Fujitsu fi-5650C |
Capture Details | ScandAll 21 |
Resolution | 300 ppi |
Color Depth | 8 bit |
Description
Title | page141 |
Collection Title | Engineering Technical Reports Collection, Purdue University |
Repository | Purdue University Libraries |
Rights Statement | Digital object copyright Purdue University. All rights reserved. |
Language | eng |
Type (DCMI) | text |
Format | JP2 |
Capture Device | Fujitsu fi-5650C |
Capture Details | ScandAll 21 |
Transcript | Present Status of the U. S. Program on the Solidification of High Level Wastes ALBERT G. BLASEWITZ, Manager KENNETH J. SCHNEIDER, Research Associate Engineering Demonstration Section Battelle Memorial Institute Pacific Northwest Laboratory Richland, Washington INTRODUCTION The conversion of high-level liquid wastes to solids as a pretreatment for storage is being developed in laboratories of nearly all countries with significantly near-future nuclear energy. Solidification is being developed so widely because it is the only practical and reasonably attainable technique for achieving a substantial increase in the safety associated with the storing and disposal of the high-level waste from the nuclear power industry. Four processes for solidification of these wastes have been developed in the U. S. A., to the point of radioactive demonstration on an engineering scale. The four processes are pot calcination, spray solidification, phosphate glass solidification, and fluidized bed calcination. The pot, spray, and phosphate glass processes have been demonstrated for the AEC on a full-level, engineering-scale in the Waste Solidification Engineering Prototypes (WSEP) by Battelle-Northwest at Richland, Washington, since November 1966. Demonstrations will be completed later in 1970. The fluidized bed process has been demonstrated for the AEC in a large capacity plant in the Waste Calcining Facility (WCF) by Idaho Nuclear Corporation at NRTS, operating on intermediate- level wastes since 1963. Most of the development work is completed and most of the basic technology has been obtained (1,2). The processes have been demonstrated to be technically feasible and ready for commercial application. Following an overall review of the management and long-term disposition of high level liquid wastes (3,4), the Atomic Energy Commission published a proposed statement of policy in the June 3, 1969 Federal Register. The proposed policy would require the following actions in regard to high-level waste management: 1) a commercial fuel reprocessing plant's inventory of high-level liquid radioactive waste will be limited to the quantity produced in the prior five yr and high-level liquid radioactive wastes in excess of the authorized inventory must be converted to an AEC-approved solid form; and 2) all high-level radioactive wastes must be transferred in the approved solid form to a Federal repository as soon as practicable, but in no event later than 10 yr following separation of the fission products from the irradiated fuel. It is anticipated that this requirement to solidify the high-level liquid waste prior to its shipment to a Federal repository will be formalized in the near future. The cost of high-level waste management involving solidification in combination with interim liquid storage, interim solid storage, and transportation to final -141- |
Resolution | 300 ppi |
Color Depth | 8 bit |
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