Published December 1972
| Version v1
Report
The influence of primary circuit components of a PWR on the analysis of mass flow rates through the core
Creators
- 1. Technische Univ. Munich, Garching (F.R. Germany). Lab. fuer Reaktorregelung und Anlagensicherung
Description
no abstract available
Additional details
Publishing Information
- Imprint Title
- Proceedings of the crest specialist meeting on emergency core cooling for light water reactors
- Imprint Pagination
- 16 p.
- Report number
- MRR--115(Vol.2)
Conference
- Title
- CREST specialist meeting on emergency core cooling for light water reactors.
- Dates
- 18 Oct 1972.
- Place
- Garching/Munich, F.R. Germany.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 4082688
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; ECCS; FLOW RATE; MASS TRANSFER; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR CORES; SIMULATION; STEAM GENERATORS
- Descriptors DEC
- BOILERS; COMPUTER CODES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; REACTORS; SAFETY; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- With figs.; 4 refs.
- Secondary number(s)
- AED-Conf--72-598-020.