Published 1997
| Version v1
Miscellaneous
Safety enhancement of the midloop operation of Ulchin 3 and 4 plant (KSNP)
Description
This paper describes the design characteristics of the Ulchin 3 and 4 reactor coolant system, the responses to generic letter 88-17, and the verification test for the critical water level. 3 figs
Additional details
Publishing Information
- Publisher
- KAIF.
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- The 19th KAIF-JAIF seminar on nuclear industry, September 29-30, 1997, Seoul, Korea
- Imprint Pagination
- 385 p.
- Journal Page Range
- p. 311-333.
Conference
- Title
- 19. KAIF-JAIF seminar on nuclear industry.
- Dates
- 29-30 Sep 1997.
- Place
- Seoul (Korea, Republic of).
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 29017271
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; COOLANT LOOPS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR SHUTDOWN; RELIABILITY; SAFETY ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS