Development and maintenance of quality-assured nuclear-related codes
Creators
- 1. Westinghouse Electric Company, LLC, Windsor, CT (United States)
Description
A general procedure for development and maintenance of quality-assured nuclear-related codes is described in this paper. The main objective here is to reinforce the main steps in developing from scratch or modifying existing codes. The codes in question are the ones used for transient analysis, criticality, and safety, among others. Failing in using such procedures can have strong negative consequences for the company that requested these calculations such as plant accidents, longer downtimes, decrement of profit margin, and endangerment of people's lives. For the company that made the erroneous calculations, high penalty fees are normally applied, besides a possible lost of market share since your company could be seen as non-reliable. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [3080 p.]
- Journal Page Range
- [4 p.]
Conference
- Title
- International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
- Acronym
- INAC 2002
- Dates
- 11-16 Aug 2002
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 33046676
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CRITICALITY; MAINTENANCE; PROGRAMMING; QUALITY ASSURANCE; REACTOR SAFETY; TRANSIENTS; VALIDATION; VERIFICATION
- Descriptors DEC
- SAFETY; TESTING
Optional Information
- Notes
- 6 refs., 1 fig. Imprint:Published only in CD-Rom