Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility
Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10172219
- Report Number(s):
- DOE/RW-0184-R1-Vol.4; ORNL/M-2217-Vol.4; ON: TI92019054
- Resource Relation:
- Other Information: PBD: Jul 1992
- Country of Publication:
- United States
- Language:
- English
Similar Records
Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility
Characterization plan for Fort St. Vrain and Peach Bottom graphite fuels
Primary coolant chemistry of the Peach Bottom and Fort St. Vrain high-temperature gas-cooled reactors
Technical Report
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Wed Jul 01 00:00:00 EDT 1992
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OSTI ID:10172219
Characterization plan for Fort St. Vrain and Peach Bottom graphite fuels
Technical Report
·
Wed Sep 01 00:00:00 EDT 1993
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OSTI ID:10172219
+4 more
Primary coolant chemistry of the Peach Bottom and Fort St. Vrain high-temperature gas-cooled reactors
Conference
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Sat Nov 01 00:00:00 EST 1980
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OSTI ID:10172219
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
PEACH BOTTOM-1 REACTOR
SPENT FUELS
FUEL ELEMENTS
RESEARCH REACTORS
VRAIN REACTOR
FFTF REACTOR
COMPILED DATA
HIGH-LEVEL RADIOACTIVE WASTES
210300
220600
052000
220300
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
WASTE MANAGEMENT
22 GENERAL STUDIES OF NUCLEAR REACTORS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
PEACH BOTTOM-1 REACTOR
SPENT FUELS
FUEL ELEMENTS
RESEARCH REACTORS
VRAIN REACTOR
FFTF REACTOR
COMPILED DATA
HIGH-LEVEL RADIOACTIVE WASTES
210300
220600
052000
220300
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
WASTE MANAGEMENT