Design Criteria for the New Waste Calcining Facility at the Idaho Chemical Processing Plant

Design Criteria for the New Waste Calcining Facility at the Idaho Chemical Processing Plant
Author:
Publisher:
Total Pages:
Release: 1976
Genre:
ISBN:

The New Waste Calcining Facility (NWCF) at the Idaho Chemical Processing Plant (ICPP) is being built to replace the existing fluidized-bed, high-level waste calcining facility (WCF). Performance of the WCF is reviewed, equipment failures in WCF operation are examined, and pilot-plant studies on calciner improvements are given in relation to NWCF design. Design features of the NWCF are given with emphasis on process and equipment improvements. A major feature of the NWCF is the use of remote maintenance facilities for equipment with high maintenance requirements, thereby reducing personnel exposures during maintenance and reducing downtime resulting from plant decontamination. The NWCF will have a design net processing rate of 11.36 m3 of high-level waste per day, and will incorporate in-bed combustion of kerosene for heating the fluidized bed calciner. The off-gas cleaning system will be similar to that for the WCF.

NWCF/ICPP Remote Decontamination Facility

NWCF/ICPP Remote Decontamination Facility
Author:
Publisher:
Total Pages:
Release: 1978
Genre:
ISBN:

This paper describes the design features, equipment and facilities incorporated in the Decontamination Area of the New Waste Calcining Facility being constructed at the Idaho National Engineering Laboratory (INEL). Special emphasis is centered upon those items which will provide capability to remotely transfer, handle, disassemble, and decontaminate equipment and components from the New Waste Calcining Process Area or other INEL facility.

Characteristics of Stored High-level ICPP Waste Calcine

Characteristics of Stored High-level ICPP Waste Calcine
Author:
Publisher:
Total Pages:
Release: 1979
Genre:
ISBN:

Calcined high-level radioactive defense waste stored at the Idaho Chemical Processing Plant for up to twelve years was sampled for retrievability. The calcine was determined to be retrievable as expected. A program to determine physical and chemical characteristics for future retrieval and alternative waste treatment processes has been completed.

ICPP Calcined Solids Storage Facility Closure Study. Volume III

ICPP Calcined Solids Storage Facility Closure Study. Volume III
Author:
Publisher:
Total Pages: 481
Release: 1998
Genre:
ISBN:

The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project's scope of work. Should more accurate numbers be required, a new analysis would be necessary.

ICPP Radioactive Liquid and Calcine Waste Technologies Evaluation. Interim Report

ICPP Radioactive Liquid and Calcine Waste Technologies Evaluation. Interim Report
Author:
Publisher:
Total Pages: 104
Release: 1994
Genre:
ISBN:

The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m3) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

Radioactive Waste Management

Radioactive Waste Management
Author: U.S. Atomic Energy Commission. Technical Information Center
Publisher:
Total Pages: 64
Release: 1973
Genre: Radioactive waste disposal
ISBN: