Measuring methods for helium leakage rate of the primary coolant loop of HTR-10
Creators
- 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear and New Energy Technology
Description
This article introduces two kinds of methods for helium leakage rate measurement of the primary coolant loop of HTR-10, which are direct measuring method and stock balance method. it analyzes the practicability of direct measuring method towards the variety property of parameters of HTR-10 primary loop, and presents method of the empirical formula used in calculating the average temperature of the helium in the pressure vessel. It also compares the two results obtained from these two methods with the actual parameters, and the maximal relative error is 5.7%. It proves that the results from direct measuring method are credible, and the results can be used to monitor whether the helium leakage rate per day is less than 1% of total helium in the primary coolant loop. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 27
- Journal Issue
- 3
- Journal Page Range
- p. 234-239
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 39075615
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; COMPARATIVE EVALUATIONS; HELIUM; HTR-10 REACTOR; LEAKS; MEASURING METHODS; MONITORING; MONITORS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MEASURING INSTRUMENTS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Notes
- 1 fig., 3 tabs., 1 ref.