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Journal Articles

Measurement for thermal neutron capture cross sections and resonance integrals of the $$^{243}$$Am(n,$$gamma$$)$$^{rm 244g}$$Am, $$^{rm 244m+g}$$Am reactions

Nakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*

KURNS Progress Report 2019, P. 132, 2020/08

Research and development were made for accuracy improvement of neutron capture cross section data on $$^{243}$$Am among minor actinides. First, the emission probabilities of decay $$gamma$$ rays were obtained with high accuracy, and the amount of the ground state of $$^{244}$$Am produced by reactor neutron irradiation of $$^{243}$$Am was examinded by $$gamma$$-ray measurement. Next, the total amount of isomer and ground states was examoned by $$alpha$$-ray measurement.

Journal Articles

What should we learn from the back numbers of HAMON ?

Takeda, Masayasu

Hamon, 30(1), p.7 - 8, 2020/02

Safety review of JRR-3 under the New Regulatory Requirements was completed on 7th November 2018. Neutron beam will come back in early 2021 after reinforcement works of the roof of the reactor building, the peripheral structures like a stack, a cooling tower, and the experimental hall. The future of neutron sciences using the research reactor strongly depends on how many impacted researches using JRR-3 are achieved after restarting JRR-3. At this stage, we can learn a lot of things from the back numbers of HAMON.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in radioactive waste generated from the dismantling of research reactors

Murakami, Masashi; Hoshino, Yuzuru; Nakatani, Takayoshi; Sugaya, Toshikatsu; Fukumura, Nobuo*; Sanda, Toshio*; Sakai, Akihiro

JAEA-Technology 2019-003, 50 Pages, 2019/06

JAEA-Technology-2019-003.pdf:4.42MB

Toward the establishment of a common approach to determine the radioactivity concentrations in dismantling wastes arising from research reactors, radionuclide concentrations in the reactor structure materials of aluminum, carbon steel, shield concrete, and graphite of TRIGA Mark II reactor at Rikkyo University, Japan, were evaluated with both radiochemical analysis and theoretical calculation. The measured nuclides by the radiochemical analysis were $$^{3}$$H, $$^{60}$$Co, and $$^{63}$$Ni in aluminum, $$^{3}$$H, $$^{60}$$Co, $$^{63}$$Ni, and $$^{152}$$Eu in carbon steel, $$^{3}$$H, $$^{60}$$Co, and $$^{152}$$Eu in shield concrete, and $$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{63}$$Ni, and $$^{152}$$Eu in graphite. Neutron-flux distributions and neutron-induced activities were computed with DORT and ORIGEN-ARP codes, respectively. Using the results of material composition analysis, radioactivity concentrations were conservatively predicted with good accuracy except for graphite material.

Journal Articles

Utilization in testing/research reactors

Tsuchiya, Kunihiko; Nagao, Yoshiharu

Kinzoku, 86(10), p.893 - 899, 2016/10

no abstracts in English

Journal Articles

The Role of the research reactor JRR-3 in neutron sciences

Takeda, Masayasu; Matsubayashi, Masahito

Nippon Genshiryoku Gakkai-Shi, 58(6), p.371 - 375, 2016/06

no abstracts in English

JAEA Reports

Development of calculation tool of neutron flux used for evaluation of radioactivity inventory in radioactive waste generated from research, medical and industrial facilities

Kurosawa, Ryohei; Okada, Shota; Sakai, Akihiro; Nakata, Hisakazu; Amazawa, Hiroya

JAEA-Data/Code 2015-005, 82 Pages, 2015/06

JAEA-Data-Code-2015-005.pdf:3.47MB

The calculation tool of neutron flux at materials within and around the research reactor was developed so that the user more easily evaluate radioactivity inventory in radioactive waste generated from the decommissioning of research reactors at various conditions. The tool consists of some computer programs which calculate macroscopic effective cross section at materials, calculate the neutron flux at materials within and around the research reactor, and edit the neutron flux to evaluate the radioactive inventory. This report describes the outline of evaluation method of neutron flux at materials within and around the research reactor, the structure and functions of the calculation tool of neutron flux, input and output data, and sample run with the tool.

Journal Articles

Industrial production with the reactor for research

Kawamura, Hiroshi

Gakujutsu No Doko, 20(6), p.32 - 38, 2015/06

no abstracts in English

Journal Articles

Industrial production with the reactor for research

Kawamura, Hiroshi

Denki Hyoron, 100(5), p.11 - 12, 2015/05

no abstracts in English

Journal Articles

Introduction to the neutron scattering, 1

Kakurai, Kazuhisa; Endo, Yasuo

Kotai Butsuri, 40(4), p.239 - 250, 2005/04

no abstracts in English

Journal Articles

Steady state neutron source by reactor

Morii, Yukio; Isshiki, Masahiko

Kessho Kaiseki Handobukku, p.111 - 114, 1999/09

no abstracts in English

Journal Articles

Prompt gamma-ray analysis with cold neutrons

Yonezawa, Chushiro

Radioisotopes, 46(6), p.74 - 81, 1997/06

no abstracts in English

Journal Articles

Reactor Neutron

Morii, Yukio; Isshiki, Masahiko

Radioisotopes, 45(11), p.717 - 721, 1996/11

no abstracts in English

Journal Articles

Counter flow of air-water system

Matsubayashi, Masahito

Chuseishi Rajiogurafi Shashinshu, P. 112, 1995/11

no abstracts in English

Journal Articles

Generating material strength standards of aluminum alloys for research reactors,I; Yield strength values Sy and tensile strength values Su

Tsuji, Hirokazu; Miya, Kenzo*

Nucl. Eng. Des., 155, p.527 - 546, 1995/00

 Times Cited Count:1 Percentile:83.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Generating material strength standards of aluminum alloys for research reactors, II; Design fatigue curve under non-effective creep condition

Tsuji, Hirokazu; Miya, Kenzo*

Nucl. Eng. Des., 155, p.547 - 557, 1995/00

 Times Cited Count:1 Percentile:83.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Sources of released tritium vapor from stack of JRR-3M

Hoken Butsuri, 29, p.366 - 368, 1994/00

no abstracts in English

Journal Articles

Research and test reactor in Japan, Present status and prospect, 2; Research and test reactor in JAERI

Shirai, Eiji; Saito, Minoru; Tanaka, Toshiyuki

Genshiryoku Kogyo, 39(11), p.10 - 17, 1993/00

no abstracts in English

Journal Articles

Research reactors in Japan; Present status in the world

Shirai, Eiji; Soyama, Kazuhiko

Genshiryoku Kogyo, 39(11), p.48 - 53, 1993/00

no abstracts in English

JAEA Reports

None

; ; ; ; ; ;

PNC-TN9080 92-008, 52 Pages, 1992/04

PNC-TN9080-92-008.pdf:1.72MB

None

JAEA Reports

None

; ; ; ; ; ;

PNC-TN9080 92-007, 113 Pages, 1992/04

PNC-TN9080-92-007.pdf:3.26MB

None

43 (Records 1-20 displayed on this page)