Hydrogen water chemistry for BWRs. A status report on the US development program

Technical Report · Sun Jun 01 04:00:00 EDT 1986

OSTI ID:5741505

Bilanin, W; Cubicciotti, D; Jones, R; Machiels, A; Nelson, L; Wood, C

Intergranular stress corrosion cracking (IGSCC) has been responsible for nearly 1000 cases of cracking in austenitic stainless steel piping systems in boiling water reactors (BWRs). This report presents the status of efforts in the United States to prevent IGSCC in BWRs during power operation by modifying the chemistry of the reactor water. The technical basis for this alternative water chemistry, called hydrogen water chemistry (HWC), is described and the results are presented of an ongoing in-plant program, at Commonwealth Edison's Dresden-2 plant, to verify the HWC concept and systematically assess the consequences of using it in an operating BWR. In addition, progress toward implementation of HWC at other US plants is summarized. 36 refs.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA). Nuclear Power Div.
• OSTI ID: 5741505
• Report Number(s): EPRI-NP-4592-SR; ON: TI86920339
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BWR TYPE REACTORS
CARBON STEELS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DRESDEN-2 REACTOR
ELEMENTS
ENRICHED URANIUM REACTORS
HYDROGEN
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NONMETALS
OPERATION
POWER REACTORS
REACTOR MATERIALS
REACTOR OPERATION
REACTORS
STAINLESS STEELS
STEELS
STRESS CORROSION
THERMAL REACTORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS