Published October 1995
| Version v1
Miscellaneous
Method of numerical experiments for analysis and prognosis of boiling water reactors state
Creators
- 1. Ukrainian State Committee on Nuclear and Radiation Safety, Kiev (Ukraine). Scientific and Technical Center
Description
The method is based on computer codes elaborated for accident regimes and transients calculations. Its application is presented in calculations of stationary processes in a technological channel of a RBMK-1000 unit for the following factor combinations: heat power of a technological channel, coolant flow rate through a channel, and the share of the heat power evaluated at the lower half of the channel. The data obtained were processed using the method of numerical experiments. (Z.S.)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international topical meeting on VVER safety
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 387-390.
- Report number
- INIS-mf--14715
Conference
- Title
- International topical meeting on VVER safety.
- Dates
- 21-23 Sep 1995.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27022924
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; LWGR TYPE REACTORS; REACTOR ACCIDENTS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; GRAPHITE MODERATED REACTORS; REACTORS; SIMULATION; WATER COOLED REACTORS