Analysis of characteristics and mechanism of self-load-following in NHR-5
Creators
- 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology
Description
Via program RETRAN-02 with the model of highly-subcooled nucleate boiling, both self-load-following experiments on the 5MW Nuclear Heating Reactor (NHR-5), load increased by 50% and loss of full load, have been analyzed respectively. The results of the experiments and analyses are quite accordant. Under rated operation condition, the transients resulted from increase of external load by 30% and loss of full load have also been analyzed, by which the safety of NHR-5 has been verified. After load variation, in such a reactor cooled by natural circulation as NHR-5, the flow rate varies first. The characteristics of this kind of transients are summarized and a discussion of behavior of highly-subcooled void and the influence of the back flow from the control rod system are offered as well
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 20
- Journal Issue
- 5
- Journal Page Range
- p. 385-388
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 32003347
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FEEDBACK; FLOW RATE; NATURAL CONVECTION; R CODES; REACTIVITY INSERTIONS; REACTOR SAFETY; SAFETY ANALYSIS; THR REACTOR; TRANSIENTS; VOID COEFFICIENT; VOID FRACTION
- Descriptors DEC
- COMPUTER CODES; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; POWER REACTORS; PROCESS HEAT REACTORS; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS