摘要:

The Space Exploration Initiative includes both lunar and Mars program elements as well as robotic science missions. Space transportation is a primary part of all planning for exploration. The high performance propulsion capabilities of nuclear propulsion offer the potential to reduce substantially the flight times to and from Mars and to reduce the mass launched into low Earth orbit.

ISSN:0094-243X    

DOI:10.1063/1.40038

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

Missions requiring electrical power in the 10 to 100 kW range have been identified as potential applications for a space reactor power system which uses the technology currently being developed under the SP‐100 Ground Engineering System Program. The design approaches proposed for these applications build upon the key technologies being developed under this program, thereby maximizing the potential applicability of this effort by fully utilizing the inherent scalability of the design implementations defined as elements of the 100 kWeGeneric Flight System.Total mass and physical size are presented as a function of rated power output over the range from 10 to 100 kW0. Mass‐effective design dictates a change in system implementation, affecting the application of basic technology, as the system power level is scaled‐down from the 100 kWepoint design. These technology tradeoffs are described along with the rationale leading to the identification of specific transition power levels within this range.

ISSN:0094-243X    

DOI:10.1063/1.40144

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

A fully licensed transportation system for Radioisotope Thermoelectric Generators and Light‐Weight Radioisotope Heater Units is currently being designed and built. The system will comply with all applicable U.S. Department of Transportation regulations without the use of a ‘‘DOE Alternative.’’ The U.S. Department of Transportation has special ‘‘double containment’’ requirements for plutonium. The system packaging uses a doubly contained ‘‘bell jar’’ concept. A refrigerated trailer is used for cooling the high‐heat payloads. The same packaging is used for both high‐ and low‐heat payloads. The system is scheduled to be available for use by mid‐1992.

ISSN:0094-243X    

DOI:10.1063/1.40037

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

An on‐line production information system has been designed to support radioisotope thermal generator assembly and testing in a new facility being built at the Department of Energy Hanford Site in Washington State. This system is intended to make handling the large volumes of information associated with radioisotope thermal generator production and certification more efficient with less opportunity for error than traditional paper methods. It provides for tracking materials, implementing work procedures directly from computer terminals, and cross referencing among materials, procedures, and other documents related to production. This system will be implemented on a network of microcomputers using UNIXTMfor its operating system. It has been designed to allow increased capabilities to be added as operating experience with the new facility dictates.

ISSN:0094-243X    

DOI:10.1063/1.40042

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

The French studies on space nuclear power systems were relatively active the past six years. It was anticipated that 20‐kWe should have to be supplied to a spacecraft as soon as in 2005 and a reference near term liquid metal‐cooled reactor using available terrestrial technologies as much as possible was mainly investigated. A Brayton cycle heat conversion has been adopted from the beginning and it remains considered. Because first applications are delayed, more attractive concepts can be contemplated. The basic idea is to take advantage of the Brayton cycle specific properties and for instance to use them for the temperature conditioning of the moderator of a thermal spectrum reactor. At first, the utilization of ZrH was thought mandatory, but recent proposals have prompted to use the conventional, effective light water material for that purpose. A gas cycle high pressure (HP) derivation technique makes it possible to maintain water within an adequate temperature range. A Brayton cycle adaptation and an example of a gas‐cooled, particle bed fuel elements, H2O moderated reactor are briefly described. Key comparison data are given. Such concepts should be attractive from fuel inventory, mass, radition shielding and control points of view.

ISSN:0094-243X    

DOI:10.1063/1.40051

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

The post SP‐100 reactor testing period will focus on defueling the reactor, packaging the various radiactive waste forms, and shipping this material to the appropriate locations. Remote‐handling techniques will be developed to defuel the reactor. Packaging the spent fuel and activated reactor components is a challenge in itself. This paper presents an overview of the strategy, methods, and equipment that will be used during the closeout phase of nuclear testing.

ISSN:0094-243X    

DOI:10.1063/1.40005

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

This paper is presented as an overview of the remote handling equipment validation testing, which will be conducted before installation and use in the ground engineering test facility. This equipment will be used to defuel the SP‐100 reactor core after removing it from the Test Assembly following nuclear testing. A series of full scale mock‐up operational tests will be conducted at a Hanford Site facility to verify equipment design, operation, and capabilities.

ISSN:0094-243X    

DOI:10.1063/1.40009

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

The Generic Flight System (GFS) reactor control approach will be tested at the SP‐100 Ground Engineering System (GES) test site as part of the Nuclear Assembly Test (NAT) program. A control scheme for the NAT has been developed to emulate the GFS conditions for testing of the GFS reactor control approach in the NAT. Comparisons between the GFS simulation results and the NAT simulation results show that a reasonably good emulation of the GFS conditions can be achieved in the NAT using the control scheme described in this paper.

ISSN:0094-243X    

DOI:10.1063/1.40023

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

The effect of tungsten‐coated graphite fibers on the radiant heat transfer characteristics of salt‐fiber composites was studied by measuring the onset of melting as a function of applied furnace power. As the fiber concentration was increased from 0 to 5.40% fiber by weight, the furnace temperature required to melt the lithium fluoride also increased. Upon cooling, each of the crystalline salt‐fiber composites were cut open with a diamond saw to expose the void. Optical photographs of the voids revealed a trend in void location and size, with the largest void, and the least change in the outer dimension of the boule upon cooling, occurring in the sample with the most fiber.

ISSN:0094-243X    

DOI:10.1063/1.40142

出版商:AIP    

年代:1991

数据来源: AIP

摘要:

An experimental program to investigate the corrosion compatibility of the high temperature thermal energy storage (TES) salts with Inconel‐617 container was initiated at the Thermal Laboratory of the Wright Research and Development Center (WRDC) in 1985. Three fluoride eutectic mixtures: LiF‐MgF2‐KF, LiF‐MgF2‐NaF, and LiF‐MgF2having melting points in the neighborhood of 1000 K and heats of fusion above 750 kJ/kg were chosen. High purity analytical grade component salts were processed in oxygen and moisture‐free inert atmosphere, and meltedin situin the Inconel‐617 containers. The containers were sealed by electron beam‐welding of the end caps thereby evacuating the void volume. The TES capsules thus formed were placed in a tubular vacuum furnace for continuous thermal cycle life testing by cycling them ±100 K from the eutectic temperature every 2 hours. The capsules have successfully undergone 40,000 hours and 10,000 cycles of testing as of April 1990 and continuing on the test. This is believed to be the longest record available on the TES corrosion compatibility data. The present results clearly indicate that careful processing and proper welding are key factors in obtaining a longlife TES salt‐containment system.

ISSN:0094-243X    

DOI:10.1063/1.40143

出版商:AIP    

年代:1991

数据来源: AIP