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JAEA Reports

Report of summer holiday practical training 2018; Feasibility study on nuclear battery using HTTR core; feasibility study for nuclear design

Ishitsuka, Etsuo; Matsunaka, Kazuaki*; Ishida, Hiroki*; Ho, H. Q.; Ishii, Toshiaki; Hamamoto, Shimpei; Takamatsu, Kuniyoshi; Kenzhina, I.*; Chikhray, Y.*; Kondo, Atsushi*; et al.

JAEA-Technology 2019-008, 12 Pages, 2019/07

JAEA-Technology-2019-008.pdf:2.37MB

As a summer holiday practical training 2018, the feasibility study for nuclear design of a nuclear battery using HTTR core was carried out. As a result, it is become clear that the continuous operations for about 30 years at 2 MW, about 25 years at 3 MW, about 18 years at 4 MW, about 15 years at 5 MW are possible. As an image of thermal design, the image of the nuclear battery consisting a cooling system with natural convection and a power generation system with no moving equipment is proposed. Further feasibility study to confirm the feasibility of nuclear battery will be carried out in training of next fiscal year.

Journal Articles

Calculation of tritium release from driver fuels into primary coolant of research reactors

Ho, H. Q.; Ishitsuka, Etsuo

Physical Sciences and Technology, 5(2), p.53 - 56, 2019/00

Increasing of tritium concentration in the primary coolant of the research and test reactors during operation had been reported. To check the source for tritium release into the primary coolant during operation of the JMTR and the JRR-3M, the tritium release from the driver fuels was calculated by MCNP6 and PHITS. It is clear that the calculated values of tritium release from fuels are as about 10$$^{7}$$ and 10$$^{6}$$ Bq for the JMTR and JRR-3M, respectively, and that calculated values are about 4 order of magnitude smaller than that of the measured values. These results show that the tritium release from fuels is negligible for both the reactors.

JAEA Reports

Calculations of Tritium Recoil Release from Li and U Impurities in Neutron Reflectors (Joint research)

Ishitsuka, Etsuo; Kenzhina, I.*; Okumura, Keisuke; Ho, H. Q.; Takemoto, Noriyuki; Chikhray, Y.*

JAEA-Technology 2018-010, 33 Pages, 2018/11

JAEA-Technology-2018-010.pdf:2.58MB

As a part of study on the mechanism of tritium release to the primary coolant in research and testing reactors, tritium recoil release rate from Li and U impurities in the neutron reflector made by beryllium, aluminum and graphite were calculated by PHITS code. On the other hand, the tritium production from Li and U impurities in beryllium neutron reflectors for JMTR and JRR-3M were calculated by MCNP6 and ORIGEN2 code. By using both results, the amount of recoiled tritium from beryllium neutron reflectors were estimated. It is clear that the amount of recoiled tritium from Li and U impurities in beryllium neutron reflectors are negligible, and 2 and 5 orders smaller than that from beryllium itself, respectively.

Journal Articles

Feasibility study of large-scale production of iodine-125 at the high temperature engineering test reactor

Ho, H. Q.; Honda, Yuki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Ishitsuka, Etsuo

Applied Radiation and Isotopes, 140, p.209 - 214, 2018/10

 Percentile:100(Chemistry, Inorganic & Nuclear)

Journal Articles

Feasibility study of new applications at the high-temperature gas-cooled reactor

Ho, H. Q.; Honda, Yuki*; Hamamoto, Shimpei; Ishii, Toshiaki; Takada, Shoji; Fujimoto, Nozomu*; Ishitsuka, Etsuo

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 6 Pages, 2018/10

Journal Articles

Proposal of a neutron transmutation doping facility for n-type spherical silicon solar cell at high-temperature engineering test reactor

Ho, H. Q.; Honda, Yuki; Motoyama, Mizuki*; Hamamoto, Shimpei; Ishii, Toshiaki; Ishitsuka, Etsuo

Applied Radiation and Isotopes, 135, p.12 - 18, 2018/05

 Times Cited Count:1 Percentile:38.14(Chemistry, Inorganic & Nuclear)

Journal Articles

Investigation of uncertainty caused by random arrangement of coated fuel particles in HTTR criticality calculations

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji

Annals of Nuclear Energy, 112, p.42 - 47, 2018/02

 Times Cited Count:1 Percentile:100(Nuclear Science & Technology)

Journal Articles

Numerical investigation of the random arrangement effect of coated fuel particles on the criticality of HTTR fuel compact using MCNP6

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji

Annals of Nuclear Energy, 103, p.114 - 121, 2017/05

 Times Cited Count:3 Percentile:42.02(Nuclear Science & Technology)

Journal Articles

Benchmark study on realized random packing model for coated fuel particles of HTTR using MCNP6

Ho, H. Q.; Morita, Keisuke*; Honda, Yuki; Fujimoto, Nozomu*; Takada, Shoji

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04

JAEA Reports

Neutronic characteristic of HTTR fuel compact with various packing models of coated fuel particle

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji

JAEA-Technology 2016-040, 16 Pages, 2017/03

JAEA-Technology-2016-040.pdf:2.89MB

To study the packing effects of the truncated coated fuel particle on the criticality for the High Temperature engineering Test Reactor (HTTR), four alternative models including the truncated uniform model, the non-truncated uniform model, the truncated random model and the non-truncated random model for the arrangement of CFP in fuel compact were used, and the neutronic and criticality calculation were performed by using Monte Carlo MCNP6 code with ENDF/B-VII.1 cross section library. The results showed that the infinite multiplication factors (k$$_{rm inf}$$) in the truncated models were lower than those of the non-truncated models regardless of the uniform or random arrangement, and the four factors in the four-factor-formula showed that the difference of k$$_{rm inf}$$ was mainly attributed to the resonance escape probability. The difference in resonance escape probability is caused by the increase of capture reactions in the resonance region as the influence of spatial-self-shielding-effect. It is because the equivalent kernel diameter of the CFP for the truncated model is smaller than that of the non-truncated model.

Oral presentation

Numerical investigation of random packing for CFPs of HTTR using MCNP

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji

no journal, , 

Oral presentation

Development of MCNP6 model for HTTR using the explicit random method

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji; Ishitsuka, Etsuo

no journal, , 

Coated fuel particles (CFPs) play an important role to the passive safety feature of the high temperature engineering test reactor (HTTR). However, random distribution of the CFPs also makes the simulation become more difficult and therefore affects the quality of the HTGR benchmark assessment. The highly accurate calculation enables the design of a commercial HTGR to operate with low cost and high performance. The purpose of this study was to develop MCNP model for the HTTR by using the explicit random model, namely Realized Random Packing (RRP), to improve the accuracy of the benchmark assessment. The RRP model was validated by comparing with the conventional uniform model as well as the experimental data. The neutronic and criticality calculations were performed by using MCNP6 code with ENDF/B-VII.1 nuclear data library.

Oral presentation

Development of realized random model for coated fuel particle of prismatic HTGR

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji; Ishitsuka, Etsuo

no journal, , 

Oral presentation

Impact of truncated coated fuel particles on neutronic characteristic of statistical geometry model in MVP code

Ho, H. Q.; Honda, Yuki; Fujimoto, Nozomu*; Goto, Minoru; Ishitsuka, Etsuo

no journal, , 

Oral presentation

Neutron transmutation doping of n-type spherical silicon solar cell at high-temperature engineering test reactor

Ho, H. Q.; Honda, Yuki; Hamamoto, Shimpei; Ishii, Toshiaki; Ishitsuka, Etsuo

no journal, , 

Oral presentation

Proposal of a neutron transmutation doping facility for n-type spherical silicon solar cell at high-temperature engineering test reactor

Ishii, Toshiaki; Ho, H. Q.; Honda, Yuki; Hamamoto, Shimpei; Ishitsuka, Etsuo

no journal, , 

no abstracts in English

Oral presentation

Feasibility study of 99mTc production at HTTR using sublimation method

Ho, H. Q.; Ishida, Hiroki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Takaki, Naoyuki*; Ishitsuka, Etsuo

no journal, , 

Oral presentation

Proposal of direct $$^{rm 99m}$$Tc production facility at high temperature engineering test reactor

Ho, H. Q.; Ishida, Hiroki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Takaki, Naoyuki*; Ishitsuka, Etsuo

no journal, , 

Oral presentation

Tritium release source and mechanism in research and testing reactors

Ishitsuka, Etsuo; Kenzhina, I.*; Okumura, Keisuke; Ho, H. Q.; Takemoto, Noriyuki; Chikhray, Y.*

no journal, , 

An increase of tritium concentration in the primary coolant for JMTR and JRR-3M revealed that the recoil tritium release from the beryllium reflector is dominant.

Oral presentation

Calculation of 3D neutron flux distribution in the HTTR using MCNP6

Ho, H. Q.; Fujimoto, Nozomu*; Hamamoto, Shimpei; Ishii, Toshiaki; Nagasumi, Satoru; Ishitsuka, Etsuo

no journal, , 

20 (Records 1-20 displayed on this page)
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