Nuclear Production of Hydrogen, Fourth Information Exchange ...

CONCEPTUAL DESIGN OF THE HTTR-IS NUCLEAR HYDROGEN PRODUCTION SYSTEM
Figure 6: Calculation results of transient behaviour of primary coolant pressure,
heat transfer tube temperature of PPWC and IHX, RPV temperature and fuel temperature
PPWC tube temperature ( o C)
1200
1000
800
600
400
RPV acceptance criteria: 550 o C
PPWC acceptance criteria: 650 o C
600
500
400
300
200
RPV temperature ( o C)
Fuel temperature ( o C)
1600
1400
1200
1000
800
600
400
100
200
Primary coolant pressure
acceptance criteria: 5.75 MPa
10
9
8
7
6
5
4
Primary coolant pressure (MPa)
200
0
0 1000 2000 3000 4000 5000
Elapsed time from IHX tube rupture (s)
0
3
0 1000 2000 3000 4000 5000
Elapsed time from IHX tube rupture (s)
Conclusion
IHXTR is one of the potential concerns for the demonstration of nuclear hydrogen production. The
detection method of the heat transfer tube rupture of IHX in the HTTR-IS nuclear hydrogen production
system was proposed in this paper. In addition, system behaviour was evaluated with a deterministic
approach. The results are summarised as follows:
• Monitoring the integral of the secondary helium gas supply due to the primary-secondary
pressure differential control system enables the immediate detection of heat transfer tube
rupture of IHX.
• Interfacing isolation valves simultaneously could reduce the helium gas transportation from
the primary to the secondary cooling system.
• Evaluation items to be evaluated do not exceed the acceptance criteria during the IHXTR.
The requirement of the isolation valve actuation time would be determined in the next step
considering the results of public radiation exposure assessment and detail valve design.
This result is expected to contribute to the demonstration of the nuclear heat utilisation not only
for the IS process but also for various heat application systems coupled to the HTTR.
Acknowledgements
The authors are indebted to Dr. M. Ogawa and Dr. R. Hino in JAEA for their advice. The authors also
would like to express their gratitude to Dr. K. Takamatsu in JAEA, and Mr. T. Maeda in CSA of Japan
Co., Ltd. for the valuable help in performing the numerical analysis.
394 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010