Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System

Author:

Sato Hiroyuki1,Ohashi Hirofumi1,Tazawa Yujiro1,Sakaba Nariaki2,Tachibana Yukio1

Affiliation:

1. Nuclear Hydrogen and Heat Application Research Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Ibaraki 311-1393 Japan

2. Policy Planning and Administration Department, Japan Atomic Energy Agency, 2-1-8 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100-8577 Japan

Abstract

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.

Publisher

ASME International

Subject

Mechanical Engineering,Energy Engineering and Power Technology,Aerospace Engineering,Fuel Technology,Nuclear Energy and Engineering

Reference16 articles.

1. JAEC, 2008, The Innovative Nuclear Technology Roadmap for Contributing to the Mitigation of Global Warming.

2. Conceptual Design of Hydrogen Production System With Thermochemical Water-Splitting Iodine-Sulphur Process Utilizing Heat From the High-Temperature Gas-Cooled Reactor HTTR;Sakaba;Int. J. Hydrogen Energy

3. JAEA’s VHTR for Hydrogen and Electricity Cogeneration: GTHTR300C;Kunitomi;Nuclear Engineering and Technology

4. Development Scenario of the Iodine-Sulphur Hydrogen Production Process to be Coupled With VHTR System as a Conventional Chemical Plant;Sakaba;J. Nucl. Sci. Technol.

5. Saito, S., Tanaka, T., Sudo, Y., Baba, O., Shindo, M., Shioawa, S., Mogi, H., Okubo, M., Ito, N., Shindo, R., Kobayashi, N., Kurihara, R., Hayashi, K., Hada, K., Kurata, Y., Yamashita, K., Kawasaki, K., Iyoku, T., Kunitomi, K., Maruyama, S., Ishihara, M., Sawa, K., Fujimoto, N., Murata, I., Nakagawa, S., Tachibana, Y., Nishihara, T., Oshita, S., Shinozaki, M., Takeda, T., Sakaba, N., Saikusa, A., Tazawa, Y., Fukaya, Y., Nagahori, H., Kikuchi, T., Kawaji, S., Isozaki, M., Matsuzaki, S., Sakama, I., Hara, K., Ueda, N., and Kokusen, S., 1994, “Design of High Temperature Engineering Test Reactor (HTTR),” JAERI 1332.

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