Concept and objectives of diagnostic rod bundle development for WWER-440 and account of carried out steps
Creators
Description
The advantages of an in-reactor monitoring system as compared with external control and measuring devices are discussed. A short historic retrospective of the in-reactor monitorino. system development is given with the stress on unresolved problems. Realization of such a system on the basis of a diagnostic fuel rod bundle with controlled coolant flow rats is considered. The scientific objectives of the diagnostic rod bundle development proo.ramme are identified. For DK1 and DK2 diagnostic rod bundles specification lists of measured parameters and corresponding sensors are presented. Problems of advanced design diagnostic fuel rod bundles (DK3 family) development are discussed. DK1 - 2 bundle is described in detail as well as the data acquisition and processing system and the results of experiments on Rheinsberg NPP
Additional details
Additional titles
- Original title (Russian)
- Концепция и цели развития диагностических топливных кассет ВВЭР-440 и перечень выполненных работ
Publishing Information
- Imprint Title
- Thermal physics 82. Thermal aspects of WWER nuclear reactors safety. V. 3.
- Journal Page Range
- p. 60-72.
- Report number
- INIS-mf--9441
Conference
- Title
- Thermal physics 82. Thermal aspects of WWER nuclear reactors safety.
- Dates
- 4-6 May 1982.
- Place
- Karlovy Vary (Czechoslovakia).
INIS
- Country of Publication
- International Centre for Scientific and Technical Information (ICSTI)
- Country of Input or Organization
- International Centre for Scientific and Technical Information (ICSTI)
- INIS RN
- 15072882
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL ASSEMBLIES; IN CORE INSTRUMENTS; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; RESEARCH PROGRAMS; TRANSDUCERS; WWER TYPE REACTORS
- Descriptors DEC
- CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs.; 1 tab. Imprint:Teplofizika 82. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov WWER. Tom 3.;Sbornik dokladov iz seminara SEhV g. Karlovy Vary, ChSSR, Maj 1982 g.