Some reactivity and power transients in FBTR
Creators
- 1. Reactor Research Centre, Kalpakkam (India). Fast Breeder Test Reactor Design Group
Description
The external feedback for FBTR plant has a transport lag of about 50 seconds. This permits the study of some incidents by considering the reactor only, detached from the rest of the plant, with a precise computational model. This paper lists the results for certain reactivity transients due to power-coolant mismatch. The computations have been done with the use of Continuous System Modelling Program (CSMP) package available on IBM 370 computer system. The neutronic power is calculated by solving numerically the integral form of the kinetics equation. The changes in temperature at the hot spot and reactor outlet are calculated by solving the heat transfer equations. From the temperature changes, the transient thermal stresses are calculated by means of Fritz method. The allowable number of thermal cycles are calculated according to ASME Criteria. (author)
Additional details
Publishing Information
- Publisher
- Department of Atomic Energy.
- Imprint Place
- Bombay
- Imprint Title
- Proceedings of the symposium on power plant dynamics and control [held at Bombay during] February 23-24, 1976
- Journal Page Range
- p. 133-143.
Conference
- Title
- Symposium on power plant dynamics and control.
- Dates
- 23 - 24 Feb 1976.
- Place
- Bombay, India.
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 8347988
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FBR TYPE REACTORS; FEEDBACK; MATHEMATICAL MODELS; REACTIVITY; REACTOR KINETICS; SYSTEMS ANALYSIS; THERMAL STRESSES; TRANSIENTS
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; KINETICS; REACTORS; STRESSES