Study of advanced fission power reactor development for the United States. Volume III. Final report 1 Jul 1974--15 Jan 1976. [Alternate strategies through year 2020]
Technical Report
·
OSTI ID:7213837
A multistage research study on the comparison of various advanced fission reactors and evaluation of alternate strategies for their development in the USA through the year 2020 is descrbed. The basic data and other input information that were utilized in the process of the study are presented. Detailed reactor and fuel-cycle information is contained on the HTGR, GCFR, MSBR, LWBR, and CANDU-HWR. These data have been assembled, critically reviewed, and modified where necessary to assure consistency, both internally for each reactor system, and between reactor types. similar, comparative, information was required for the LWR mass balances, fuel cycle, etc., but this was generally accepted from ERDA sources without the critical evaluation performed on the other data. Other detailed information that relates to the objective of the study, e.g., projections of nuclear power growth and uranium availability, generic safeguards information, description of computerized models, etc., is incorporated for ready reference.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 7213837
- Report Number(s):
- PB-263360; BCL/NSF/C-946-2-3
- Country of Publication:
- United States
- Language:
- English
Similar Records
Final report on study of advanced fission power reactor development for the United States. Volume III
Study of advanced fission power reactor development for the United States. Volume II. Final report 1 Jul 1974--15 Jan 1976. [Alternate strategies through year 2020]
Relative safeguards risks of advanced reactor concepts. [Material diversion in fuel cycle for seven reactor concepts]
Technical Report
·
Fri Jun 25 00:00:00 EDT 1976
·
OSTI ID:7313911
Study of advanced fission power reactor development for the United States. Volume II. Final report 1 Jul 1974--15 Jan 1976. [Alternate strategies through year 2020]
Technical Report
·
Fri Jun 25 00:00:00 EDT 1976
·
OSTI ID:7213840
Relative safeguards risks of advanced reactor concepts. [Material diversion in fuel cycle for seven reactor concepts]
Conference
·
· Nucl. Mater. Manage.; (United States)
·
OSTI ID:7343899
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210800* -- Nuclear Power Plants-- Economics
29 ENERGY PLANNING, POLICY, AND ECONOMY
290600 -- Energy Planning & Policy-- Nuclear Energy
BREEDER REACTORS
CANDU TYPE REACTORS
COMPARATIVE EVALUATIONS
ECONOMICS
ENVIRONMENTAL IMPACTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CYCLE
GAS COOLED REACTORS
GCFR TYPE REACTORS
GRAPHITE MODERATED REACTORS
HAZARDS
HEAVY WATER MODERATED REACTORS
HTGR TYPE REACTORS
LWBR TYPE REACTORS
MOLTEN SALT REACTORS
NORTH AMERICA
PERFORMANCE
POWER REACTORS
PRESSURE TUBE REACTORS
REACTORS
THERMAL REACTORS
USA
WATER COOLED REACTORS
WATER MODERATED REACTORS
210800* -- Nuclear Power Plants-- Economics
29 ENERGY PLANNING, POLICY, AND ECONOMY
290600 -- Energy Planning & Policy-- Nuclear Energy
BREEDER REACTORS
CANDU TYPE REACTORS
COMPARATIVE EVALUATIONS
ECONOMICS
ENVIRONMENTAL IMPACTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CYCLE
GAS COOLED REACTORS
GCFR TYPE REACTORS
GRAPHITE MODERATED REACTORS
HAZARDS
HEAVY WATER MODERATED REACTORS
HTGR TYPE REACTORS
LWBR TYPE REACTORS
MOLTEN SALT REACTORS
NORTH AMERICA
PERFORMANCE
POWER REACTORS
PRESSURE TUBE REACTORS
REACTORS
THERMAL REACTORS
USA
WATER COOLED REACTORS
WATER MODERATED REACTORS