In-pile loop tests for PWR coolant chemistry optimization
- Massachusetts Inst. of Tech., Cambridge (United States)
- Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)
For the past several years, an in-pile loop that simulates pressurized water reactor (PWR) primary coolant conditions has been operated at the Massachusetts Institute of Technology (MIT) research reactor to test changes in chemistry that will reduce corrosion product activity deposition on ex-core surfaces. The basic design can be employed in any pool-type research reactor and represents a fairly inexpensive approach to PWR coolant chemistry research. The loop was constructed for an initial series of seven runs supported by the Electric Power Research Institute (EPRI) and Empire State Electric Energy Research Company (ESEERCO) and is now in the middle of a three-run series sponsored by NUPEC. The principal focus to date in both campaigns has been pH optimization through adjustment of the amount of LiOH added for a given boron (boric acid) concentration.
- OSTI ID:
- 7193504
- Report Number(s):
- CONF-920606-; CODEN: TANSA
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 65; Conference: American Nuclear Society annual meeting, Boston, MA (United States), 7-12 Jun 1992; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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PRIMARY COOLANT CIRCUITS
ACTIVITY LEVELS
WATER CHEMISTRY
PWR TYPE REACTORS
CORROSION PRODUCTS
DEPOSITION
EPRI
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PH VALUE
REACTOR OPERATION
RESEARCH PROGRAMS
ZIRCALOY
ALLOYS
CHEMISTRY
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
HEAVY WATER COOLED REACTORS
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REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
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RESEARCH AND TEST REACTORS
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TANK TYPE REACTORS
THERMAL REACTORS
TRAINING REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled