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Title: Overview of Sandia National Laboratories Technical Area V and the 90?s Medical Isotope Production Program.

Abstract

Abstract not provided.

Authors:
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1395741
Report Number(s):
SAND2016-9452PE
647643
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the Generic Presentation on SNL, TAV, and the Medical Isotope Program.
Country of Publication:
United States
Language:
English

Citation Formats

Parma, Edward J.,. Overview of Sandia National Laboratories Technical Area V and the 90?s Medical Isotope Production Program.. United States: N. p., 2016. Web.
Parma, Edward J.,. Overview of Sandia National Laboratories Technical Area V and the 90?s Medical Isotope Production Program.. United States.
Parma, Edward J.,. Thu . "Overview of Sandia National Laboratories Technical Area V and the 90?s Medical Isotope Production Program.". United States. doi:. https://www.osti.gov/servlets/purl/1395741.
@article{osti_1395741,
title = {Overview of Sandia National Laboratories Technical Area V and the 90?s Medical Isotope Production Program.},
author = {Parma, Edward J.,},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 2016},
month = {Thu Sep 01 00:00:00 EDT 2016}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

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  • In late 1994, Sandia National Laboratories in Albuquerque, New Mexico, (SNL/NM), was instructed by the Department of Energy (DOE) Isotope Production and Distribution Program (IPDP) to examine the feasibility of producing medically useful radioisotopes using the Annular Core Research Reactor (ACRR) and the Hot Cell Facility (HCF). Los Alamos National Laboratory (LANL) would be expected to supply the targets to be irradiated in the ACRR. The intent of DOE would be to provide a capability to satisfy the North American health care system demand for {sup 99}Mo, the parent of {sup 99m}Tc, in the event of an interruption in themore » current Canadian supply. {sup 99m}Tc is used in 70 to 80% of all nuclear medicine procedures in the US. The goal of the SNL/NM study effort is to determine the physical plant capability, infrastructure, and staffing necessary to meet the North American need for {sup 99}Mo and to identify and examine all issues with potential for environmental impact.« less
  • No abstract prepared.
  • This report describes the Sandia National Laboratories Medical Isotope Reactor and hot cell facility concepts. The reactor proposed is designed to be capable of producing 100% of the U.S. demand for the medical isotope {sup 99}Mo. The concept is novel in that the fuel for the reactor and the targets for the {sup 99}Mo production are the same. There is no driver core required. The fuel pins that are in the reactor core are processed on a 7 to 21 day irradiation cycle. The fuel is low enriched uranium oxide enriched to less than 20% {sup 235}U. The fuel pinsmore » are approximately 1 cm in diameter and 30 to 40 cm in height, clad with Zircaloy (zirconium alloy). Approximately 90 to 150 fuel pins are arranged in the core in a water pool {approx}30 ft deep. The reactor power level is 1 to 2 MW. The reactor concept is a simple design that is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the reactor core is minimized since the fuel/target pins are removed and processed after 7 to 21 days. The fuel fabrication, reactor design and operation, and {sup 99}Mo production processing use well-developed technologies that minimize the technological and licensing risks. There are no impediments that prevent this type of reactor, along with its collocated hot cell facility, from being designed, fabricated, and licensed today.« less
  • Sandia National Laboratories has initiated many joint research and development projects with the two premier Russian nuclear laboratories, VNIIEF and VNIITF, (historically known as Arzamas-16 and Chelyabinsk-70) in a wide spectrum of areas. One of the areas in which critical dialogue and technical exchange is continuing to take place is in the realm of system surety. Activities primarily include either safety or security methodology development, processes, accident environment analyses and testing, accident data-bases, assessments, and product design. Furthermore, a continuing dialog has been established between the organizations with regard to developing a better understanding of how risk is perceived andmore » analyzed in Russia versus that in the US. The result of such efforts could reduce the risk of systems to incur accidents or incidents resulting in high consequences to the public. The purpose of this paper is to provide a current overview of the Sandia surety program and its various initiatives with the Russian institutes, with an emphasis on the program scope and rationale. The historical scope of projects will be indicated. A few specific projects will be discussed, along with results to date. The extension of the joint surety initiatives to other government and industry organizations will be described. This will include the current status of a joint Sandia/VNIIEF initiative to establish an International Surety Center for Energy Intensive and High Consequence Systems and Infrastructures.« less
  • A probabilistic risk assessment was completed for a former radioactive waste disposal site. The site, two unlined surface impoundment, was designed as part of the Liquid Waste Disposal System (LWDS) to receive radioactive effluent from nuclear reactors in Technical Area-V (TA-V) at Sandia National Laboratories/New Mexico (SNL/NM). First, a statistical comparison of site sampling results to natural background, using EPA methods, and a spatial distribution analysis were performed. Risk assessment was conducted with SNL/NM`s Probabilistic Risk Evaluation and Characterization Investigation System model. The risk assessment indicated that contamination from several constituents might have been high enough to require remediation. However,more » further analysis based on expected site closure activities and recent EPA guidance indicated that No Further Action was acceptable.« less