Published May 1976
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Some basic thermohydraulic calculation methods for the analysis of pressure transients in a multicompartment total containment enclosing a breached water reactor circuit
Description
This paper gives an appreciation and commentary of the basic calculation methods under development at AEE Winfrith for the analysis of multicompartment total containments. The assumptions introduced and the effects of their variation are important in establishing a parametric survey of the range of possible conditions which the containment may be required to meet. These aspects of the performance will be discussed as each individual factor in the train of events is examined in turn. (U.K.)
Availability note (English)
MF available from INIS under the Report Number.
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Additional details
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- AEEW-M--1400
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 7275763
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CONTAINMENT SHELLS; FRACTURES; LOSS OF COOLANT; PRESSURE MEASUREMENT; REACTOR COOLING SYSTEMS; RUPTURES; SYSTEMS ANALYSIS; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; COOLING SYSTEMS; FAILURES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS