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Technical Brief

Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating

[+] Author and Article Information
Masato Ono

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: ono.masato@jaea.go.jp

Atsushi Shimizu

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: shimizu.atsushi35@jaea.go.jp

Makoto Kondo

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: kondo.makoto@jaea.go.jp

Yosuke Shimazaki

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: shimazaki.yosuke@jaea.go.jp

Masanori Shinohara

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: shinohara.masanori@jaea.go.jp

Daisuke Tochio

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: tochio.daisuke@jaea.go.jp

Kazuhiko Iigaki

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: iigaki.kazuhiko@jaea.go.jp

Shigeaki Nakagawa

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: nakagawa.shigeaki@jaea.go.jp

Shoji Takada

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: takada.shoji@jaea.go.jp

Kazuhiro Sawa

Department of HTTR,
Oarai Research and Development Center, Sector of Nuclear Science Research, Japan Atomic Energy Agency,
4002 Narita-Cho, Oarai-machi, Higashi-ibarakigun, Ibaraki 311-1393, Japan
e-mail: sawa.kazuhiro@jaea.go.jp

Manuscript received August 21, 2015; final manuscript received January 6, 2016; published online October 12, 2016. Assoc. Editor: Jovica R. Riznic.

ASME J of Nuclear Rad Sci 2(4), 044502 (Oct 12, 2016) (4 pages) Paper No: NERS-15-1178; doi: 10.1115/1.4032478 History: Received August 21, 2015; Accepted January 06, 2016

In the loss of core cooling test using High Temperature engineering Test Reactor (HTTR), the forced cooling of the reactor core is stopped without inserting control rods into the core and, furthermore, without cooling by the vessel cooling system (VCS) to verify safety evaluation codes to investigate the inherent safety of high-temperature gas-cooled reactor (HTGR) be secured by natural phenomena to make it possible to design a severe accident-free reactor. The VCS passively removes the retained residual heat and the decay heat from the core via the reactor pressure vessel (RPV) by natural convection and thermal radiation. In the test, the local temperature was supposed to exceed the limit from the viewpoint of long-term use at the uncovered water-cooling tube without thermal reflectors in the VCS, although the safety of reactor is kept. Through a cold test, which was carried out by non-nuclear heat input from helium gas circulators (HGCs) by stopping water flow in the VCS, the local higher temperature position was specified in the uncovered water-cooling tube of the VCS, although the temperature was sufficiently lower than the maximum allowable working temperature, and the natural circulation of water had an insufficient cooling effect on the temperature of the water-cooling tube below 1°C. Then, a new safe and secured procedure for the loss of core cooling test was established, which will be carried out soon after the restart of HTTR.

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References

Figures

Grahic Jump Location
Fig. 1

Outline and schematic drawing of VCS

Grahic Jump Location
Fig. 2

Cooling effect of natural convection on water cooling tube

Grahic Jump Location
Fig. 3

Water inlet temperature of VCS

Grahic Jump Location
Fig. 4

Effectiveness of the proposed new test procedure

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