Results for FY '16

K. Kora, H. Nakaya, H. Matsuura, M. Goto, S. Nakagawa, S. Shimakawa

A Study on transmutation of LLFPs using various types of HTGRs

Nuclear Engineering and Design, 300, (2016)330-338.

I. Ioka, Y. Kuriki, J. Iwatsuki, S. Kubo, J. Katsuyama, Y. Inagaki

Characteristics of hybrid tube with Fe-high Si alloy lining by centrifugal casting for thermochemical water-splitting iodine-sulfur process

Mechanical Engineering Journal (Internet), 3-3, (2016)15-619_1-15-619_8.

S. Kasahara, T. Murata, Y. Kamiji, A. Terada, Yan. X, Y. Inagaki, M. Mori

Heat transport analysis in a district heating system applying waste heat from GTHTR300, a commercial design of high-temperature gas-cooled reactor

Mechanical Engineering Journal (Internet), 3-3, (2016)15-616_1-15-616_16.

S. Ueta, N. Sakaba, K. Sawa

Shielding technology for upper structure of HTTR

Annals of Nuclear Energy, 94, (2016)72-79.

Yan. X, H. Sato, Y. Kamiji, Y. Imai, A. Terada, Y. Tachibana, K. Kunitomi

GTHTR300 cost reduction through design upgrade and cogeneration

Nuclear Engineering and Design, 306, (2016)215-220

Y. Fukaya, T. Nishihara

Reduction on high level radioactive waste volume and geological repository footprint with high burn-up and high thermal efficiency of HTGR

Nuclear Engineering and Design, 307, (2016)188-196

M. Ogawa

Proposals of new basic concepts on safety and radioactive waste and of new high temperature gas-cooled reactor based on these basic concepts

Nuclear Engineering and Design, 308, (2016)133-141

Y. Inaba, K. Sekita, T. Nemoto, Y. Honda, D, Tochio, H. Sato, S. Nakagawa, S. Takada, K. Sawa

Nuclear heat supply fluctuation tests by non-nuclear heating with HTTR

Journal of Nuclear Engineering and Radiation Science, 2-4, (2016)04100_1-04100_7

Y. Inaba, T. Nishihara

Development of fuel temperature calculation code for HTGRs

tion code for HTGRs

Y. Fukaya, M. Goto

Sustainable and safe energy supply with seawater uranium fueled HTGR and its economy

Annals of Nuclear Energy, 99, (2017)19-27

K. Takamatsu, T. Matsumoto, K. Morita

New reactor cavity cooling system (RCCS) with passive safety features; A Comparative methodology between a real RCCS and a scaled-down heat-removal test facility

Annals of Nuclear Energy, 96, (2016)137-147

K. Takamatsu, T. Matsumoto, K. Morita

New reactor cavity cooling system with a novel shape and passive safety features

2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, U. S. A., April17-20, 2016.

H. Sato, H. Ohashi, S. Nakagawa

Design approach for mitigation of air ingress in high temperature gas-cooled reactor

24th International Conference on Nuclear Engineering (ICONE-24), Charlotte, U. S. A., June26-30, 2016.

Y. Inaba, Y. Honda, T. Nishihara

Development of a core coolant flow distribution calculation code for HTGRs

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

S. Ueta, J. Aihara, Shaimerdenov. A, Dyussambayev. D, Gizatulin. S, Chakrov. P, N. Sakaba

Irradiation test and post irradiation examination of the high burnup HTGR fuel

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

T. Shibata, J. Sumita, N. Sakaba, T. Osaki, H. Kato, S. Izawa, T. Muto, Gizatulin. S, Shaimerdenov. A, Dyussambayev. D, Chakrov. P

Irradiation test about oxidation-resistant graphite in WWR-K research reactor

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

H. Sato, Y. Nomoto, S. Horii, J. Sumita, Yan. X, H. Ohashi

HTTR-GT/H₂ test plant; System performance evaluation for HTTR gas turbine cogeneration plant

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

J. Aihara, M. Goto, Y. Inaba, S. Ueta, J. Sumita, Y. Tachibana

Nuclear thermal design of high temperature gas-cooled reactor with SiC/C mixed matrix fuel compacts

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

H. Ohashi, H. Sato, S. Nakagawa, K. Tokuhara, T. Nishihara, K. Kunitomi

Development of safety requirements for HTGRs design

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

Reitsma. S, K. Kunitomi, H. Ohashi

The IAEA coordinated research project on modular HTGR safety design; Status and outlook

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

S. Kasahara, Y. Imai, K. Suzuki, J. Iwatsuki, A. Terada, Yan. X

Conceptual design of iodine-sulfur process flowsheet with more than 50% thermal efficiency for hydrogen production

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

Y. Honda, Y. Fukaya, S. Nakagawa, Baker. R. I, H. Sato

Sensitivity analysis of xenon reactivity temperature dependency for HTTR LOFC test by using RELAP5-3D code

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

H. Noguchi, H. Takegami, Y. Kamiji, N. Tanaka, J. Iwatsuki, S. Kasahara, S. Kubo

IS process hydrogen production test for components and system made of industrial structural material, 2; H2SO4 decomposition, HI distillation, and HI decomposition section

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

N. Tanaka, H. Takegami, H. Noguchi, Y. Kamiji, J. Iwatsuki, H. Aita, S. Kasahara, S. Kubo

IS process hydrogen production test for components and system made of industrial structural material, 1; Bunsen and HI concentration section

8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, U. S. A., November6-10, 2016.

Y. Fukaya, T. Nishihara

Study on correlation effect between factors of statistical hot spot factor for HTGR design

JAEA-Research 2016-001

Y. Fukaya, K. Tokuhara, T. Nishihara

Study on stability criterion of xenon oscillation based on analysis solution for HTGR design

JAEA-Research 2016-008

H. Sato, S. Nakagawa, H. Ohashi

Selection of design basis event for modular high temperature gas-cooled reactor

JAEA-Technology 2016-014

Y. Kamiji, K. Suzuki, Yan. X

Study of HTGR contribution to Japan's CO₂ emission reduction goal in 2050

JAEA-Technology 2016-010

Y. Imai, H. Sato, Y. Nomoto, Yan. X

Design database of helium gas turbine for high temperature gas-cooled reactor

JAEA-Data/Code 2016-007

Y. Inaba, K. Isaka, T. Shibata

Development of fuel temperature calculation code "FTCC" for high temperature gas-cooled reactors

JAEA-Data/Code 2017-002

N. Mizuta, S. Ueta, J. Aihara, T. Shibata

Confirmation of feasibility of fabrication technology and characterization of high-packing fraction fuel compact for HTGR

JAEA-Technology 2017-004