An Evaluation of Alternative TRU Technologies

1982 ◽  
Vol 15 ◽  
Author(s):  
G. Bida ◽  
D. R. Mackenzie

In support of the responsibility of the Nuclear Regulatory Commission (NRC) to promulgate a regulation for disposal of high level waste in a geologic repository, a technical support program was conducted at Brookhaven National Laboratory (BNL). The principal objectives of the program were (1) to identify and provide an understanding of those factors and processes which affect repository performance, and (2) to provide the information needed to develop and support proposed regulations, criteria, and performance objectives that will ultimately be issued as the final rule for disposal of high level radioactive wastes in geologic repositories, known as 10 CFR 60 [1]. As part of the technical support program in the development of nuclear waste form criteria, three main areas of transuranic (TRU) waste management have been evaluated: immobilization processes and waste forms proposed for ultimate geologic disposal of TRU waste; management of TRU waste by decontamination; and potential problems associated with gas generation by certain TRU wastes [2]. The evaluation results from a review of, primarily, relevant DOE research and development efforts reported up to the end of CY 80. Also, only the definitions, criteria, and performance objectives detailed in the Advance Notice of Proposed Rulemaking (10 CFR 60) [3] were considered in this evaluation. This is important to note since significant differences in the waste package definition and in the statement of performance objectives as well as in other areas exist between the Advance Notice [31 and the Proposed Rule [1].

2013 ◽  
Vol 62 ◽  
pp. 37-45 ◽  
Author(s):  
Sangeeta Deokattey ◽  
K. Bhanumurthy ◽  
P.K. Wattal

1999 ◽  
Vol 556 ◽  
Author(s):  
D. W. Esh ◽  
K. M. Goff ◽  
K. T. Hirsche ◽  
T. J. Battisti ◽  
M. F. Simpson ◽  
...  

AbstractA ceramic waste form is being developed by Argonne National Laboratory* (ANL) as part of the demonstration of the electrometallurgical treatment of spent nuclear fuel [1]. The halide, alkaline earth, alkali, transuranic, and rare earth fission products are stabilized in zeolite which is combined with glass and processed in a hot isostatic press (HIP) to form a ceramic composite. The mineral sodalite is formed in the HIP from the zeolite precursor. The process, from starting materials to final product, is relatively simple. An overview of the processing operations is given. The metrics that have been developed to measure the success or completion of processing operations are developed and discussed. The impact of variability in processing metrics on the durability of the final product is presented. The process is demonstrated to be robust for the type and range of operation metrics considered and the performance metric (PCT durability test) against which the operation metrics are evaluated.


1996 ◽  
Vol 465 ◽  
Author(s):  
T. H. Pigford ◽  
E. D. Zwahlen

ABSTRACTRecent proposals for a new U.S. standard for high-level waste disposal would limit the average dose to individuals in the vicinity surrounding a geologic repository. This would be a new approach to protecting the public from environmental releases of radioactivity. Heretofore, criteria adopted for geologic disposal have limited the reasonable maximum exposure to a future hypothetical individual. Here we present quantitative analyses of the relation between maximum exposure and vicinity-average exposure, resulting from future human use of ground water contaminated by radioactive releases from a repository.Estimating the vicinity-average exposure would require postulates and guesses of location and habits of future people. Exposure probabilities postulated by others show that proposed dose limit to the vicinity-average individual would be a far more lenient standard than the traditional dose limit to reasonably maximally exposed individuals. The proposed vicinity-average dose limit would allow far greater concentrations of contaminants in ground water than would be allowed by normal standards of ground water protection. A safety standard that limits vicinity-average exposure should also include limits on maximum exposure.


2014 ◽  
Vol 27 ◽  
pp. 1460139
Author(s):  
ISTVAN DIOSZEGI ◽  
GRAHAM C. SMITH ◽  
NEIL A. SCHAKNOWSKI ◽  
BO YU ◽  
JACK FRIED ◽  
...  

A new generation of coded aperture neutron imagers is being developed at Brookhaven National Laboratory. The detector of the camera is a position sensitive thermal neutron chamber. The new device is a 3 He -filled ionization chamber, which uses only anode and cathode planes. The anode is composed of an array of individual pads. The charge is collected on each of the individual 5 × 5 mm2 anode pads, (48 × 48 in total corresponding to a 24 × 24 cm2 sensitive area) and read out by application specific integrated circuits. The new design has several advantages for the field of coded aperture applications compared to the previous generation of wire-grid based neutron detectors. Among these are the rugged design, lighter weight and use of non-flammable stopping gas. The pad-based readout is event by event, thus capable of high count rates, and can perform data analysis and imaging on an event by event basis. The spatial resolution of the detector can be better than the pixel size by using charge sharing between adjacent pads. In this paper, we will report on the development and performance of the new, prototype pad-based neutron camera and present the first pad-based coded aperture images of thermalized neutron sources.


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