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Waste acid detoxification and reclamation: Phase 1, Project planning and concept development

Description: The objectives of this project are to develop processes for reducing the volume, quantity, and toxicity of metal-bearing waste acids. The primary incentives for implemeting these types of waste minimization processes are regulatory and economic in that they meet requirements in the Resource Conservation and Recovery Act and reduce the cost for treatment, storage, and disposal. Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication oper… more
Date: February 1, 1988
Creator: Stewart, T. L. & Brouns, T. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Personnel Radiation Exposure in HTGR Plants

Description: Occupational radiation exposures in high-temperature gas-cooled reactor (HTGR) plants were assessed. The expected rate of dose accumulations for a large HTGR steam cycle (HTGR-SC) unit is 0.07 man-rem/MW(e)y, while the design basis is 0.17 man-rem/MW(e)y. The comparable figure for actual light water reactor (LWR) experience is 1.3 man-rem/MW(e)y. The favorable HTGR occupational exposure is supported by results from the Peach Bottom Unit No. 1 HTGR and Fort St. Vrain HTGR plants and by operating… more
Date: January 1, 1980
Creator: Su, S. & Engholm, B. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nonintrusive irradiated fuel inventory confirmation technique

Description: Successful tests showing correlation between the intensity of the Cerenkov glow surrounding irradiated fuel assemblies in water-filled spent fuel storage ponds and the exposure and cooling times of assemblies have been concluded. Fieldable instruments used in subsequent tests confirmed that such measurements can be made easily and rapidly, without fuel assembly movement or the introduction of apparatus into the storage ponds.
Date: January 1, 1980
Creator: Dowdy, E.J.; Nicholson, N. & Caldwell, J.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

Description: This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm/sup 2/ of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm/sup 2/. The other three spots are 100 cm/sup 2/ or less. The beta-gamma r… more
Date: February 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Behavior of Spent Nuclear Fuel and Storage System Components in Dry Interim Storage. Revision 1

Description: Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are sto… more
Date: February 1, 1983
Creator: Johnson, A. B., (Jr.); Gilbert, E. R. & Guenther, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A safety assessment of the use of graphite in nuclear reactors licensed by the US NRC

Description: This report reviews existing literature and knowledge on graphite burning and on stored energy accumulation and releases in order to assess what role, if any, a stored energy release can have in initiating or contributing to hypothetical graphite burning scenarios in research reactors. It also addresses the question of graphite ignition and self-sustained combustion in the event of a loss-of-coolant accident (LOCA). The conditions necessary to initiate and maintain graphite burning are summariz… more
Date: September 1, 1987
Creator: Schweitzer, D.G.; Gurinsky, D.H.; Kaplan, E. & Sastre, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiment operations plan for the MT-4 experiment in the NRU reactor. [PWR]

Description: A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for MT-4 - the fourth materials deformation experiment conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. A major objective of MT-4 was to simulate a pressurized water reactor LOCA that could… more
Date: June 1, 1983
Creator: Russcher, G. E.; Wilson, C. L.; Parchen, L. J.; Marshall, R. K.; Hesson, G. M.; Webb, B. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary neutronics calculations for the super SARA test program. [PWR; BWR]

Description: The Super SARA Test Program (SSTP) is a major European Economic Community effort to study light-water reactor safety during large- and small-break loss-of-coolant accident (LOCA) events in the ESSOR reactor. The SSTP will simulate small-break LOCA's by producing slow temperature ramps to high fuel rod temperatures (approx. 2000/sup 0/C). These experiments will provide data to describe high-temperature, severe-fuel damage mechanisms. The first section describes the reactor and test assembly… more
Date: December 1, 1982
Creator: Jenquin, U.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Retrofittable Modifications to Pressurized Water Reactors for Improved Resource Utilization

Description: This report summarizes work performed for the U.S. Arms Control and Disarmament Agency under BOA AC9NX707 (Task Order 80-02), as part of the Agency's continuing program on improved fuel utilization in light water reactors. The objective of the study was to investigate improvements in fuel management and design of water reactors (PWRs) that could potentially increase the utilization of natural uranium resources in a once-through fuel cycle (i.e., without using spent fuel reprocessing and recycle… more
Date: October 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Behavior of Spent Nuclear Fuel and Storage System Components in Dry Interim Storage.

Description: Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are sto… more
Date: August 1, 1982
Creator: Johnson, A. B., (Jr.); Gilbert, E. R. & Guenther, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor safety research programs. Quarterly report, July-September 1983

Description: Evaluations of nondestructive examination (NDE) techniques and instrumentation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experime… more
Date: April 1, 1984
Creator: Edler, S.K. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor safety research programs. Quarterly report, October-December 1983. Vol. 4

Description: Evaluations of nondestructive examination (NDE) techniques and instrumentation include investigating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems and examining NDE reliability and probabilistic fracture mechanics. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making reg… more
Date: May 1, 1984
Creator: Edler, S.K. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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