Abstract
During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.
| Original language | English |
|---|---|
| Pages (from-to) | 69-80 |
| Number of pages | 12 |
| Journal | Nuclear Engineering and Design |
| Volume | 150 |
| Issue number | 1 |
| DOIs | |
| Publication status | Published - Sep 2 1994 |
| Externally published | Yes |
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All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering
Cite this
Fuel temperature analysis method for channel-blockage accident in HTTR. / Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Kiso, Yoshihiro; Hayakawa, Hitoshi.
In: Nuclear Engineering and Design, Vol. 150, No. 1, 02.09.1994, p. 69-80.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Fuel temperature analysis method for channel-blockage accident in HTTR
AU - Maruyama, So
AU - Fujimoto, Nozomu
AU - Sudo, Yukio
AU - Kiso, Yoshihiro
AU - Hayakawa, Hitoshi
PY - 1994/9/2
Y1 - 1994/9/2
N2 - During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.
AB - During operation of the High Temperature Engineering Test Reactor (HTTR), coolability must be maintained without core damage under all postulated accident conditions. Channel blockage of a fuel element was selected as one of the design-basis accidents in the safely evaluation of the reactor. The maximum fuel temperature for such a scenario has been evaluated in the safety analysis and is compared to the core damage limits. For the design of the HTTR, an in-core thermal and hydraulic analysis code Flownet/trump was developed. This code calculates fuel temperature distrubution, not only for a channel blockage accident but also for transient conditions. The validation of flownet/trump code was made by comparison of the analytical results with the results of thermal and hydraulic tests by the Helium Engineering Demonstration Loop (HENDEL) multi-channel test rig (T1-M), which simulated one fuel column in the core. The analytical results agreed well with experiments in which the HTTR operating conditions were simulated. The maximum fuel temperature during a channel blockage accident is 1653°C. Therefore, it is confirmed that the integrity of the core is maintained during a channel blockage accident.
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U2 - 10.1016/0029-5493(94)90052-3
DO - 10.1016/0029-5493(94)90052-3
M3 - Article
AN - SCOPUS:0028761474
VL - 150
SP - 69
EP - 80
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
IS - 1
ER -