Published 1977
| Version v1
Book
Safety evaluation of inlet-tube break for a pressure tube type reactor
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
- 2. Hitachi Ltd., Ibaraki (Japan). Hitachi Works
Description
The safety evaluation of an inlet tube break for the pressure tube reactor, FUGEN is described. The investigation was conducted by using the computer code SENHOR and the experimental results obtained at the Oarai Engineering Center, PNC. It was found that, for a smaller rupture at the inlet tube with a small leakage (<= 10 kg/s), sufficient core flow is expected even in the ruptured channel and the minimum critical heat flux ratio is expected to remain above 1.0 under full power operating condition. A postulated inlet tube break accident with large leakage (>10 kg/s) is also evaluated in comparison with the experiment. (author)
Additional details
Publishing Information
- Publisher
- Mechanical Engineering Pub. for the Institution of Mechanical Engineers.
- Imprint Place
- London
- ISBN
- 0 85298 379 4
- Imprint Title
- Heat and fluid flow in water reactor safety. Conference sponsored by the Thermodynamics and Fluid Mechanics Group of the Institution of Mechanical Engineers, Manchester, 13-15 September 1977
- Journal Issue
- no. 8
- Series
- IMechE Conference Publications 1977.
- Journal Page Range
- p. 125-130.
Conference
- Title
- Conference on heat and fluid flow in water reactor safety.
- Dates
- 13 - 15 Sep 1977.
- Place
- Manchester, UK.
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 9376554
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; CRITICAL FLOW; CRITICAL HEAT FLUX; ECCS; FLOW MODELS; JATR REACTOR; LEAKS; LOSS OF COOLANT; PRESSURE TUBES; REACTOR SAFETY EXPERIMENTS; RUPTURES; S CODES; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FAILURES; FLUID FLOW; HEAT FLUX; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; MATHEMATICAL MODELS; NATURAL URANIUM REACTORS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS