TMI-2 in-Vessel Hydraulic Systems Utilize High Water and High Boron Content Fluids
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5528004
Choice of a hydraulic fluid for use in the Three Mile Island Unit 2 (TMI-2) reactor vessel defueling equipment required consideration of the following constraints for the hydraulic fluid given an accidental spill into the reactor coolant system (RCS). The TMI-2 RCS hydraulic fluid utilized in the hydraulic operations utilized a solution composition of 95 wt% water and 5 wt% of the above base fluid. The TMI-2 hydraulic system utilizes pressures up to 3500 psi. The selected hydraulic fluid has been in use since December 1986 with minimal operational difficulties.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5528004
- Report Number(s):
- CONF-870601-Summs.; CODEN: TANSA; TRN: 88-009957
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 54; Conference: Annual Meeting of the American Nuclear Society , Dallas, TX (United States), 7 Jun 1987; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
THREE MILE ISLAND-2 REACTOR
HYDRAULIC EQUIPMENT
REACTOR ACCIDENTS
REACTOR DISMANTLING
BORON
CRITICALITY
REACTOR COOLING SYSTEMS
WATER CHEMISTRY
ACCIDENTS
CHEMISTRY
COOLING SYSTEMS
DEMOLITION
ELEMENTS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SEMIMETALS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
Three Mile Island Unit 2 (TMI-2)
Reactor Coolant System (RCS)
Hydraulic Fluid
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
THREE MILE ISLAND-2 REACTOR
HYDRAULIC EQUIPMENT
REACTOR ACCIDENTS
REACTOR DISMANTLING
BORON
CRITICALITY
REACTOR COOLING SYSTEMS
WATER CHEMISTRY
ACCIDENTS
CHEMISTRY
COOLING SYSTEMS
DEMOLITION
ELEMENTS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SEMIMETALS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
Three Mile Island Unit 2 (TMI-2)
Reactor Coolant System (RCS)
Hydraulic Fluid
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled