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Journal Articles

Irradiation growth behavior of improved Zr-based alloys for fuel cladding

Amaya, Masaki; Kakiuchi, Kazuo; Mihara, Takeshi

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.1048 - 1056, 2019/09

Journal Articles

Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data

Sugino, Kazuteru; Numata, Kazuyuki*; Ishikawa, Makoto; Takeda, Toshikazu*

Annals of Nuclear Energy, 130, p.118 - 123, 2019/08

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

In MA sample irradiation test data calculations, the neutron fluence during irradiation period is generally scaled by using dosimetry data in order to improve calculation accuracy. In such a case, appropriate correction is required to burnup sensitivity coefficients obtained by the conventional generalized perturbation theory because some cancellations occur in the burnup sensitivity coefficients. Therefore, a new formula for the burnup sensitivity coefficient has been derived with the consideration of the neutron fluence scaling effect (NFS). In addition, the cross-section-induced uncertainty is evaluated by using the obtained burnup sensitivity coefficients and the covariance data based on the JENDL-4.0.

JAEA Reports

Irradiation test with silicon ingot for NTD-Si irradiation technology

Takemoto, Noriyuki; Romanova, N.*; Kimura, Nobuaki; Gizatulin, S.*; Saito, Takashi; Martyushov, A.*; Nakipov, D.*; Tsuchiya, Kunihiko; Chakrov, P.*

JAEA-Technology 2015-021, 32 Pages, 2015/08

JAEA-Technology-2015-021.pdf:3.15MB

Silicon semiconductor production by neutron transmutation doping (NTD) method using the JMTR has been investigated in Neutron Irradiation and Testing Reactor Center, Japan Atomic Energy Agency in order to expand the industry use. As a part of investigations, irradiation test with a silicon ingot was planned using WWR-K in Institute of Nuclear Physics, Republic of Kazakhstan. A device rotating the ingot made with the silicon was fabricated and was installed in the WWR-K for the irradiation test. And that, a preliminary irradiation test was carried out using neutron fluence monitors to evaluate the neutronic irradiation field. Based on the result, two silicon ingots were irradiated as scheduled, and the resistivity of each irradiated silicon ingot was measured to confirm the applicability of high-quality silicon semiconductor by the NTD method (NTD-Si) to its commercial production.

Journal Articles

Nuclear analyses of some key aspects of the ITER design with Monte Carlo codes

Iida, Hiromasa; Petrizzi, L.*; Khripunov, V.*; Federici, G.*; Polunovskiy, E.*

Fusion Engineering and Design, 75(1-4), p.133 - 139, 2005/11

The design of the ITER machine was presented in 2001. A nuclear analysis has been performed on ITER by means of the most detailed models and the best assessed nuclear data and codes. As the construction phase of ITER is approaching, the design of the main components has been optimized/finalized and several minor design changes/optimizations have been made, which required refined calculations to confirm that nuclear design requirements are met. Some of the proposed design changes have been made to mitigate critical radiation shielding problems. This paper reviews some of the most recent neutronic work with emphasis on critical nuclear responses in the TF coil inboard legs and vacuum vessel related to design modifications made to the blanket modules and vacuum vessel.

JAEA Reports

Acceleration irradiation test of first-loading fuel of High Temperature Engineering Test Reactor (HTTR) up to high burnup (Joint research)

Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Takahashi, Masashi; Tobita, Tsutomu*; Hayashi, Kimio; Saito, Takashi; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Kato, Shigeru*

JAERI-Research 2002-012, 39 Pages, 2002/06

JAERI-Research-2002-012.pdf:3.12MB

no abstracts in English

Journal Articles

Effect of neutron irradiation on electromotive force of oxygen sensor using zirconia solid electrolyte

Hiura, Nobuo*; Yamaura, Takayuki; Motohashi, Yoshinobu*; Kobiyama, Mamoru*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.202 - 208, 2002/06

The purpose of this study is to develop oxygen sensor which can measure the oxygen potential of the fuel in a nuclear reactor. The oxygen sensor with CaO stabilized zirconia solid electrolyte has been specially designed in order to prolong its life time. Electromotive force (EMF) of solid galvanic cell Ni/NiO|ZrO$$_{2}$$-CaO|Fe/FeO was measured in both the out-pile tests and the in-situ tests using Japan Material Testing Reactor (JMTR), and the characteristics of EMF was discussed. In the out-pile test, it was found that the EMF was almost equal to the theoretical values at temperatures ranging from 700 to 1,000$$^{circ}C$$, and the life span of the sensor was very long up to 980h at 800$$^{circ}C$$. In the in-situ test, it was found that the EMF showed almost the reliable values up to 300 h (neutron fluence (E $$>$$ 1 MeV) 1.5$$times$$10$$^{23}$$ m$$^{-2}$$), at temperatures from 700 to 900$$^{circ}C$$. The imprecision of the EMF was found to be within 6% of the theoretical values up to 1,650 h irradiation time (neutron fluence (E $$>$$ 1 MeV) 8.0$$times$$10$$^{23}$$ m$$^{-2}$$) at 800$$^{circ}C$$. The oxygen sensors were found to be applicable for the oxygen potential measurement of the fuels in a reactor.

Journal Articles

Conceptual tokamak design at high neutron fluence

Araki, Masanori; Sato, Shinichi*; Senda, Ikuo; Omori, Junji*; Shoji, Teruaki

Fusion Engineering and Design, 58-59, p.887 - 892, 2001/11

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study for improvement of performance of the test and research reactors

JAERI-Research 99-016, 84 Pages, 1999/03

JAERI-Research-99-016.pdf:2.97MB

no abstracts in English

JAEA Reports

Evaluation of fluence to dose equivalent conversion factors for high energy radiations, I; Preparation of code system and basic data

; Uehara, Takashi*; ; Iwai, Satoshi*; Tanaka, Shunichi

JAERI-M 92-126, 88 Pages, 1992/09

JAERI-M-92-126.pdf:1.91MB

no abstracts in English

Journal Articles

Estimation method of fast neutron fluence in the JMTR

;

Nihon Genshiryoku Gakkai-Shi, 25(5), p.56 - 66, 1983/00

no abstracts in English

JAEA Reports

Surveillance Test of OWL-2 Inpile Tube

;

JAERI-M 6667, 33 Pages, 1976/08

JAERI-M-6667.pdf:0.83MB

no abstracts in English

JAEA Reports

A Study on the Behaviors of Resistance Strain Gages in Nuclear Radiation Environments

; ; Kitahara, Tanemichi;

JAERI-M 6200, 22 Pages, 1975/08

JAERI-M-6200.pdf:0.79MB

no abstracts in English

JAEA Reports

Nuclear accident dosimetry system in JAERI, with experiments of simulated criticality accident

; Numakunai, Takao;

JAERI 1229, 31 Pages, 1973/07

JAERI-1229.pdf:1.18MB

no abstracts in English

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