High-temperature Gas-cooled Reactor Base-technology Program Annual Progress Report for Period Ending December 31, 1977
Author :
Publisher :
Page : 360 pages
File Size : 17,99 MB
Release : 1978
Category :
ISBN :
Gas-Cooled Reactor Programs. High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual Progress Report for Period Ending December 31, 1977
Author :
Publisher :
Page : pages
File Size : 43,28 MB
Release : 1978
Category :
ISBN :
Book Description
Progress in HTGR studies is reported in the following areas: fission product technology and coolant impurity effects, fueled graphite development, PCRV development, structural materials, characterization and standardization of graphite, and evaluation of the pebble-bed type HTR.
High-temperature Gas-cooled Reactor Base-technology Program Annual Progress Report for Period Ending December 31, 1979
Author :
Publisher :
Page : 276 pages
File Size : 22,14 MB
Release : 1980
Category :
ISBN :
Book Description
Energy Research Abstracts
Author :
Publisher :
Page : 408 pages
File Size : 22,83 MB
Release : 1978
Category : Power resources
ISBN :
Book Description
Gas-cooled Reactor Programs
Author :
Publisher :
Page : pages
File Size : 21,6 MB
Release : 1980
Category :
ISBN :
Book Description
Progress in HTGR studies is reported in the following areas: HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; and evaluation of the pebble-bed HTR.
Energy Research Abstracts
Author :
Publisher :
Page : 652 pages
File Size : 18,16 MB
Release : 1978
Category : Power resources
ISBN :
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Government Reports Annual Index
Author :
Publisher :
Page : 954 pages
File Size : 25,34 MB
Release : 1979
Category : Research
ISBN :
Book Description
Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
High-Temperature Gas-Cooled Reactor Technology Development Program
Author :
Publisher :
Page : 164 pages
File Size : 47,1 MB
Release : 1989
Category :
ISBN :
Book Description
The High-Temperature Gas-Cooled Reactor (HTGR) Program being carried out under the US Department of Energy (DOE) continues to emphasize the development of modular high-temperature gas-cooled reactors (MHTGRs) possessing a high degree of inherent safety. The emphasis at this time is to develop the preliminary design of the reference MHTGR and to develop the associated technology base and licensing infrastructure in support of future reactor deployment. A longer-term objective is to realize the full high-temperature potential of HTGRs in gas turbine and high-temperature, process-heat applications. This document summarizes the activities of the HTGR Technology Development Program for the period ending December 31, 1987.
Radioactive Waste Processing and Disposal
Author : U.S. Nuclear Regulatory Commission
Publisher :
Page : 908 pages
File Size : 29,78 MB
Release : 1980
Category : Radioactive waste disposal
ISBN :
Book Description
High-temperature Gas-cooled Reactor Technology Development Program. Annual Progress Report for Period Ending December 31, 1980
Author :
Publisher :
Page : 310 pages
File Size : 42,9 MB
Release : 1981
Category : Gas cooled reactors
ISBN :
Book Description
Research activities are described concerning HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; HTR core evaluation; reactor physics; shielding; application and project assessments; and HTR Core Flow Test Loop studies.
