Published December 1984
| Version v1
Report
Safety concept and evaluation of the 745 MW KWU-pressurized heavy water reactor (PHWR). Pt. 1
Description
The safety concept of the PHWR is principally based on the same safety features as the light water PWR, e.g. reactor building consisting of a spherical steel containment and an outer concrete building with vented annulus inbetween. However, there are some specialities adherent to the heavy water reactor. Safety related systems are designed to be both, diverse and redundant. The moderator cooling system can be used as a high pressure heat removal sysem and thus is an addition to the heat removal via the steam generators. For reactor shut-down a control rod system and a boron injection system exist independently. (orig./HP)
Additional details
Additional titles
- Subtitle (English)
- Safety concept of the 745 MWe PHWR Atucha II
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 1
- Imprint Pagination
- 761 p.
- Journal Page Range
- p. 693-702.
- Report number
- KFK--3880/1
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068624
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONSTRUCTION; PHWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTORS; SAFETY