Refine your search:     
Report No.
 - 
Search Results: Records 1-9 displayed on this page of 9
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Report of summer holiday practical training 2020; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design, 3

Ishitsuka, Etsuo; Mitsui, Wataru*; Yamamoto, Yudai*; Nakagawa, Kyoichi*; Ho, H. Q.; Ishii, Toshiaki; Hamamoto, Shimpei; Nagasumi, Satoru; Takamatsu, Kuniyoshi; Kenzhina, I.*; et al.

JAEA-Technology 2021-016, 16 Pages, 2021/09

JAEA-Technology-2021-016.pdf:1.8MB

As a summer holiday practical training 2020, the feasibility study for nuclear design of a nuclear battery using HTTR core was carried out, and the downsizing of reactor core were studied by the MVP-BURN. As a result, it is clear that a 1.6 m radius reactor core, containing 54 (18$$times$$3 layers) fuel blocks with 20% enrichment of $$^{235}$$U, and BeO neutron reflector, could operate continuously for 30 years with thermal power of 5 MW. Number of fuel blocks of this compact core is 36% of the HTTR core. As a next step, the further downsizing of core by changing materials of the fuel block will be studied.

JAEA Reports

Report of summer holiday practical training 2019; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design, 2

Ishitsuka, Etsuo; Nakashima, Koki*; Nakagawa, Naoki*; Ho, H. Q.; Ishii, Toshiaki; Hamamoto, Shimpei; Takamatsu, Kuniyoshi; Kenzhina, I.*; Chikhray, Y.*; Matsuura, Hideaki*; et al.

JAEA-Technology 2020-008, 16 Pages, 2020/08

JAEA-Technology-2020-008.pdf:2.98MB

As a summer holiday practical training 2019, the feasibility study for nuclear design of a nuclear battery using HTTR core was carried out, and the $$^{235}$$U enrichment and burnable poison of the fuel, which enables continuous operation for 30 years with thermal power of 5 MW, were studied by the MVP-BURN. As a result, it is clear that a fuel with $$^{235}$$U enrichment of 12%, radius of burnable poison and natural boron concentration of 1.5 cm and 2wt% are required. As a next step, the downsizing of core will be studied.

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

Ce substitution and reduction annealing effects on electronic states in Pr$$_{2-x}$$Ce$$_x$$CuO$$_4$$ studied by Cu $$K$$-edge X-ray absorption spectroscopy

Asano, Shun*; Ishii, Kenji*; Matsumura, Daiju; Tsuji, Takuya; Ina, Toshiaki*; Suzuki, Kensuke*; Fujita, Masaki*

Journal of the Physical Society of Japan, 87(9), p.094710_1 - 094710_5, 2018/09

 Times Cited Count:7 Percentile:63.33(Physics, Multidisciplinary)

Journal Articles

Reduction and oxidation annealing effects on Cu $$K$$-edge XAFS for electron-doped cuprate superconductors

Asano, Shun*; Suzuki, Kensuke*; Matsumura, Daiju; Ishii, Kenji*; Ina, Toshiaki*; Fujita, Masaki*

Journal of Physics; Conference Series, 969, p.012051_1 - 012051_5, 2018/04

 Times Cited Count:2 Percentile:83.27

Journal Articles

Preparation of $$gamma$$-LiV$$_{2}$$O$$_{5}$$ from polyoxovanadate cluster Li$$_{7}$$[V$$_{15}$$O$$_{36}$$(CO$$_{3}$$)] as a high-performance cathode material and its reaction mechanism revealed by ${{it operando}}$ XAFS

Wang, H.*; Idobe, Jin*; Shimizu, Takeshi*; Matsumura, Daiju; Ina, Toshiaki*; Yoshikawa, Hirofumi*

Journal of Power Sources, 360, p.150 - 156, 2017/08

 Times Cited Count:9 Percentile:44.85(Chemistry, Physical)

Journal Articles

Determination of Plutonium in High Active Liquid Waste by Spectrophotometry using Neodymium as an Internal Standard for Safeguards Analysis

Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kitao, Takahiko; Hina, Tetsuro; Toshiaki, Hiyama,

Dai-25-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, p.120 - 127, 2004/00

For the determination of Pu in the high active liquid waste (HALW), isotope dilution mass spectrometry (IDMS) has been applied to verification analysis at Tokai Reprocessing Plant. IDMS has been considered as the most reliable analytical technique for accountability measurement of Pu in spent fuel reprocessing plant. However, it takes quite long time for inspector to obtain an analytical result because inspection sample has to be transported to safeguards analytical laboratory for off-site analysis. In order to overcome this disadvantage, a rapid verification analysis of Pu in HALW by conventional spectrophotometer using Nd as an internal standard was proposed to achieve on-site verification measurements. In this method, Nd standard is intended to be provided by International Atomic Energy Agency (IAEA) so that an inspector can independently control it not only as an internal standard but also as an authentication purpose. The validation analysis was carried out by comparing with IDMS. It was found that the values of Pu concentration obtained by proposed method were in good agreement with those obtained by IDMS. Therefore the proposed method can be expected for the application to the verification analysis.

Journal Articles

Determination of Plutonium in High Active Liquid Waste of Reprocessing Plant by Spectrophotometry using Neodymium as an Internal Standard

Surugaya, Naoki; Taguchi, Shigeo; Sato, Soichi; Kitao, Takahiko; Hina, Tetsuro; Hiyama, Toshiaki,

Proceedings of 45th INMM Annual Meeting, (112), p.33 - 34, 2004/00

A technique of measuring rapidly and correctly the concentration of Pu contained in the high radioactive liquid waste in a reprocessing plant has been developed. This method is based on spectrophotometry using Nd as an internal standard, and can be expected the application as measurement technology for the safeguards which has been utilizing the conventional method of isotope dilution mass spectrometry. This report describes the measurement principle and the result of the examination which used a real sample.

Journal Articles

Determination of Plutonium in High Active Liquid Waste of Reprocessing Plant by Spectrophotometry using Neodymium as an Internal Standard

Surugaya, Naoki; Taguchi, Shigeo; Sato, Soichi; Hina, Tetsuro; Toshiaki, Hiyama,; Kitao, Takahiko

Proceedings of 45th INMM Annual Meeting, CD-ROM, 8p., 8 Pages, 2004/00

A rapid verification technique with conventional spectrophotometer has been developed to achieve on-site safeguards measurements in which neodymium as an internal standard was chosen to determine the plutonium concentration in high radioactive liquid waste.This method will provide the on-site analytical capabilities as it allows rapid and simple analyses at Tokai Reprocessing Plant.

9 (Records 1-9 displayed on this page)
  • 1