ATHENA [Advanced Thermal-Hydraulic Energy Network Analyzer] transient analysis of a fusion engineering test reactor
Description
Two potential undercooling transients are of concern in the design of TIBER-II (Tokamak Ignition/Burn Experimental Reactor), namely loss of coolant and loss of flow accidents. The major area of concern for TIBER-II is the inboard shield, where, due to tungsten material, the decay heat is extremely high. The purpose of this study was to analyze these transients using the thermal-hydraulic code ATHENA (Advanced Thermal-Hydraulic Energy Network Analyzer). The most comprehensive portion of this project involved creating a simple, yet complete, ATHENA model representative of TIBER-II. The completed model represents the case when the plasma is off and contains the inboard shield, the outboard shield, the divertor shields, and the primary loop. The primary loop contains the piping, pump, pressurizer, and heat exchanger. The heat exchanger is at the same elevation as the reactor, the least favorable to establishing natural circulation. The only transient analyzed so far, however, is a loss of flow accident. Results from the loss of flow analysis show that there is sufficient natural circulation in the inboard, outboard, and lower divertor shield to remove the decay heat, assuming that the secondary side flow is at full capacity. Although the upper divertor shield does not have sufficient natural circulation, cooling is provided due to vaporization and re-flood oscillations. However, one must recognize that there may be some local hot sport where the flow geometry inhibits cooling in a LOFA; the ATHENA model would not detect any localized problem. 9 refs., 18 figs., 4 tabs
Availability note (English)
Available from NTIS, PC A03/MF A01; 1 as DE88006799.
Files
Additional details
Publishing Information
- Imprint Pagination
- 44 p.
- Report number
- EGG-FSP--7961
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19076751
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- A CODES; DIVERTORS; FLOW RATE; HEAT EXCHANGERS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; LOSS OF FLOW; MATHEMATICAL MODELS; REACTOR SAFETY; SHIELDING; TEMPERATURE DISTRIBUTION; THERMONUCLEAR REACTOR COOLING; TIBER-X TOKAMAK; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CLOSED PLASMA DEVICES; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; REACTOR ACCIDENTS; SAFETY; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.