Published 2004 | Version v1
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CHECWORKSTM - An integrated computer program for controlling flow-accelerated corrosion

  • 1. Electric Power Research Institute, Palo Alto, CA (United States)
  • 2. DuPage Computer Applications Inc., Woodridge, IL (United States)

Description

EPRI has been developing technology to help plant owners control flow-accelerated corrosion (FAC). In 1987 and 1989, EPRI released the CHECreg and CHECMATEreg computer programs to predict the rate of wall thinning caused by FAC in lines containing single-phase water and two-phase wet steam mixtures, respectively. EPRI has also developed the CHEC-NDETM and CHEC-TTM programs to assist engineers in interpreting the inspection data and in performing structural acceptance calculations. These programs have proven to be very successful and are in use at almost all U.S. nuclear plants, at some U.S. fossil plants, and at some foreign nuclear plants. Recently, EPRI updated the technology and combined these individual programs into an integrated package called CHECWORKSTM. The first version of CHECWORKSTM was released in December 1993. An update, planned for May 1994, will meet the software quality assurance requirements of ISO 9000 and 10CFR5052 Appendix B. EPRI designed CHECWORKSTM to support predictions of other types of corrosion. In 1994, EPRI plans to release capability to predict cavitation in piping systems and to predict radiolysis and electro-chemical potential in BWR piping systems, and components and welds within the reactor vessel. This latter capability is intended to help plant owners control stress corrosion cracking of sensitized materials and to evaluate preventive options. Other corrosion predictions will be added in future years as the research progresses. (author)

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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2

Additional details

Publishing Information

Imprint Title
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2
Imprint Pagination
814 p.
Journal Page Range
p. 47C1-47C6
Report number
INIS-XA-N--081

Conference

Title
4. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
5-8 Apr 1994
Place
Taipei, Taiwan (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35097918
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; C CODES; EPRI; FLUID FLOW; MONITORING; STRESS CORROSION; TWO-PHASE FLOW
Descriptors DEC
CHEMICAL REACTIONS; COMPUTER CODES; CORROSION; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
This record replaces 35095651; 8 refs, 3 figs