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Research Papers: Nuclear Power

Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System

[+] Author and Article Information
Hiroyuki Sato

Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Ibaraki 311-1393 Japansato.hiroyuki09@jaea.go.jp

Hirofumi Ohashi

Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Ibaraki 311-1393 Japanohashi.hirofumi@jaea.go.jp

Yujiro Tazawa

Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Ibaraki 311-1393 Japantazawa.yujiro@jaea.go.jp

Nariaki Sakaba

Policy Planning and Administration Department, Japan Atomic Energy Agency, 2-1-8 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100-8577 Japansakaba.nariaki@jaea.go.jp

Yukio Tachibana

Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Ibaraki 311-1393 Japantachibana.yukio@jaea.go.jp

J. Eng. Gas Turbines Power 133(2), 022902 (Oct 29, 2010) (8 pages) doi:10.1115/1.4002351 History: Received June 29, 2010; Revised July 02, 2010; Published October 29, 2010; Online October 29, 2010

The establishment of a safety evaluation method is one of the key issues for the nuclear hydrogen production demonstration since fundamental differences in the safety philosophy between nuclear plants and chemical plants exist. In the present study, a practical safety evaluation method, which enables to design, construct, and operate hydrogen production plants under conventional chemical plant standards, is proposed. An event identification is conducted for the HTTR-IS system, a nuclear hydrogen production system by thermochemical water splitting iodine-sulfur process (IS process) utilizing the heat from the high temperature engineering test reactor (HTTR) in order to select abnormal events, which would change the scenario and quantitative results of the evaluation items from the existing HTTR safety evaluation. In addition, a safety analysis is performed for the identified events. The results of safety analysis for the identified five anticipated operational occurrences (AOOs) and three accidents (ACDs) show that evaluating items such as a primary cooling system pressure, temperatures of heat transfer tubes at pressure boundary, etc., do not exceed the acceptance criteria during the scenario. In addition, the increase of peak fuel temperature is small in the most severe case and therefore, the reactor core was not damaged and cooled sufficiently. These results will contribute to the safety review from the government and demonstration of the nuclear production of hydrogen.

Copyright © 2011 by American Society of Mechanical Engineers
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References

Figures

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Figure 1

Layout of the HTTR-IS system

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Figure 2

Major modifications of the HTTR-IS system related to the coupling of the IS process

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Figure 3

Nodalization diagram of the calculation model for the HTTR-IS system

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Figure 4

Transient behavior of peak fuel temperature and primary cooling system pressure during the increase in IHX primary gas circulator rotation number

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Figure 5

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the increase in IHX primary gas circulator rotation number

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Figure 6

Transient behavior of peak fuel temperature and pressures of primary and secondary helium cooling systems during the closing of air cooler bypass flow control valve

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Figure 7

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the closing of air cooler bypass flow control valve

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Figure 8

Transient behavior of peak fuel temperature and primary cooling system pressure during the opening of air cooler bypass flow control valve

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Figure 9

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the opening of air cooler bypass flow control valve

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Figure 10

Transient behavior of peak fuel temperature and primary cooling system pressure during the opening of exhaust valve in secondary helium storage and supply system

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Figure 11

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the opening of exhaust valve in secondary helium storage and supply system

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Figure 12

Transient behavior of peak fuel temperature and primary cooling system pressure during the closing of isolation valve in secondary helium cooling system

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Figure 13

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the rupture of inner pipe in coaxial hot gas duct in secondary helium cooling system

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Figure 14

Transient behavior of peak fuel temperature and primary cooling system pressure during the rupture of inner pipe in coaxial hot gas duct in secondary helium cooling system

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Figure 15

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the rupture of inner pipe in coaxial hot gas duct in secondary helium cooling system

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Figure 16

Transient behavior of peak fuel temperature and primary cooling system pressure during the rupture of piping in secondary helium cooling system

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Figure 17

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the rupture of piping in secondary helium cooling system

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Figure 18

Transient behavior of peak fuel temperature and primary cooling system pressure during the rupture of IHX heat transfer tube

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Figure 19

Transient behavior of temperatures of IHX heat transfer tube, PPWC heat transfer tube, and RPV during the rupture of IHX heat transfer tube

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