Study of behavior of running parameters after scram on Nuclear Ship MUTSU
- 1. Japan Atomic Energy Research Inst., Mutsu, Aomori (Japan). Mutsu Establishment
Description
It is very important for an operator on Nuclear Ship to control the plant after scram properly, in order to prevent the nuclear plant condition from exceeding the permitted limits and to regain her propulsion rapidly. And the proper control needs an exact knowledge about the transient pattern of some principal parameters such as primary coolant temperature, steam flow, bus electric power and etc. Present paper describes characteristic behavior of these parameters every 0.1 second, 1 second and 1 minute after scram, in connection with the sequential workings of the equipment and the manual operation. And it includes a study about the effects of the reactor power before scram. As the results of the present investigation, for example concerning primary coolant temperature, some phenomena worthy of mention are here. (1) The instantaneous rate of temperature drop runs up to 1000 degC/h immediately after 100% scram. (2) Transient of the rate of temperature drop always calms down after two peaks. (3) The maximum value of temperature drop is mainly influenced by manual operation. It would be useful for an operator to know the cause-and-effect relationship between the behavior of principal parameters and the operation after scram. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
23008873.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 62 p.
- Report number
- JAERI-M--91-113
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23008873
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; LIQUID FLOW; MUTSU REACTOR; NS MUTSU; POWER SUPPLIES; PRIMARY COOLANT CIRCUITS; REACTOR OPERATION; SCRAM; STEAM GENERATORS; TEMPERATURE DISTRIBUTION; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; ELECTRONIC EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; NUCLEAR MERCHANT SHIPS; NUCLEAR SHIPS; OPERATION; POWER REACTORS; PROPULSION REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SHIP PROPULSION REACTORS; SHIPS; SHUTDOWN; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS