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JAEA Reports

Results of JRR-4 operation and use

Nemoto, Tsutomu

JAEA-Technology 2024-004, 203 Pages, 2024/07

JAEA-Technology-2024-004.pdf:12.53MB

JRR-4 is an enriched uranium light water moderated cooling swimming pool research reactor with a thermal output of 3,500kW. It became critical in January 1965, and after undergoing characteristic tests, shielding mock-up experiments for the first nuclear-powered ship began in April 1966. After that, shared operation with a thermal output of 2,500 kW began in January 1974, and the output increased to 3,500 kW in October 1976. Since then, irradiation tests of nuclear fuel and materials, RI it has been used in a wide range of fields of nuclear power research and development, including the production of nuclear energy, neutron diffraction experiments using neutron beams, and medical irradiation (BNCT). During this time, various problems arose, but each time they were resolved one by one through the efforts of those involved, making full use of the latest technology at the time. As a result, stable operation over a long period of time has become possible. As part of business rationalization based on the "JAEA Reform Plan" formulated on September 26, 2013, JRR-4 applied for decommissioning plan approval and moved to decommissioning. This report is the culmination of the results of over 40 years of operation management, maintenance, modification, and utilization of JRR-4.

Journal Articles

Attempts to estimate the amount of contamination by Cs and Sr in cracked concrete considering realistic contamination conditions

Yamada, Kazuo*; Hokora, Hideyuki*; Maruyama, Ippei*; Aihara, Haruka; Tomita, Sayuri*; Tojo, Yasumasa*; Shibuya, Kazutoshi*; Hosokawa, Yoshifumi*; Igarashi, Go*; Koma, Yoshikazu

Proceedings of Waste Management Symposia 2024 (WM2024) (Internet), 7 Pages, 2024/03

Journal Articles

Atomic Energy Society of Japan "2023 Spring Annual Meeting", "Sigma" Investigative Committee and Nuclear Data Division Joint Session, 60th Anniversary of Investigation Committee for Nuclear Data; All Japan Endeavor for Nuclear Data Activities, 1; 60 Years of Investigation Committee for Nuclear Data

Fukahori, Tokio

Kaku Deta Nyusu (Internet), (135), p.19 - 25, 2023/06

Initially, the Sigma Committee consisted of two sides of the same coin: the Atomic Energy Society of Japan (AESJ) Sigma Special Committee and the Japan Atomic Energy Research Institute (JAERI) Sigma Research Committee. It is original the Sigma Committee conducts actual work such as research, evaluation and evaluation of nuclear data (including measurement, called "nuclear data activity") rather than a "place for examination" that can be felt from the sense of the word "committee". At present, the AESJ's Investigation Committee of Nuclear Data and the JAEA's JENDL Committee are working independently, and the JENDL Committee has taken over the actual work of producing nuclear data files. On the occasion of the 60th anniversary of the Sigma Committee, we have reviewed its progress and historical description so far given in the references.

JAEA Reports

Evaluation of insertion property of control rod of JRR-3 at earthquake by time history response analysis method

Kawamura, Sho; Kikuchi, Masanobu; Hosoya, Toshiaki

JAEA-Technology 2021-041, 103 Pages, 2023/02

JAEA-Technology-2021-041.pdf:8.7MB

In response to new regulatory standard for research and test reactor which is enforced December 2013, JRR-3 got license in November 2018 by formulate new design basis ground motion. After that we evaluated for insertion property of control rod using that new design basis ground motion, and that evaluation results were accepted as approval of the design and construction method by Nuclear Regulation Authority. Now, we re-evaluated to insertion property of control rod about neutron absorber and follower fuel element by time history response analysis method. In this report, it shows that new results have sufficiency of margin compared with the past results that are accepted as approval of the design and construction method.

Journal Articles

Estimation of I-131 concentration using time history of pulse height distribution at monitoring post and detector response for radionuclide in plume

Hirayama, Hideo*; Kawasaki, Masatsugu; Matsumura, Hiroshi*; Okura, Takehisa; Namito, Yoshihito*; Sanami, Toshiya*; Taki, Mitsumasa; Oishi, Tetsuya; Yoshizawa, Michio

Insights Concerning the Fukushima Daiichi Nuclear Accident, Vol.4; Endeavors by Scientists, p.295 - 307, 2021/10

JAEA Reports

Prototype fast breeder reactor Monju; Its history and achievements (Translated document)

Mitsumoto, Rika; Hazama, Taira; Takahashi, Keita; Kondo, Satoru

JAEA-Technology 2019-020, 167 Pages, 2020/03

JAEA-Technology-2019-020.pdf:21.06MB
JAEA-Technology-2019-020-high-resolution1.pdf:47.3MB
JAEA-Technology-2019-020-high-resolution2.pdf:34.99MB
JAEA-Technology-2019-020-high-resolution3.pdf:48.74MB
JAEA-Technology-2019-020-high-resolution4.pdf:47.83MB
JAEA-Technology-2019-020-high-resolution5.pdf:18.35MB
JAEA-Technology-2019-020-high-resolution6.pdf:49.4MB
JAEA-Technology-2019-020-high-resolution7.pdf:39.78MB

The prototype fast breeder reactor Monju has produced valuable technological achievements through design, construction, operation and maintenance over half a century since 1968. This report compiles the reactor technologies developed for Monju, including the areas: history and major achievements, design and construction, commissioning, safety, reactor physics, fuel, systems and components, sodium technology, materials and structures, operation and maintenance, and accidents and failures.

Journal Articles

Estimation of I-131 concentration using time history of pulse height distribution at monitoring post and detector response for radionuclide in plume

Hirayama, Hideo*; Kawasaki, Masatsugu; Matsumura, Hiroshi*; Okura, Takehisa; Namito, Yoshihito*; Sanami, Toshiya*; Taki, Mitsumasa; Oishi, Tetsuya; Yoshizawa, Michio

Nihon Genshiryoku Gakkai Wabun Rombunshi, 13(3), p.119 - 126, 2014/09

A method of deducing the I-131 concentration in a radioactive plume from the time history of peak count rates determined from pulse height spectra obtained from an NaI(Tl)scintillation detector employed as a detector of a monitoring post was presented. The concentrations of I-131 in the plumes were estimated from the count rates using the calculated response of the NaI(Tl) detector with egs5 for a model of a plume uniformly containing I-131. This method was applied to the data from the monitoring posts at Nuclear Science Research Institutes of Japan Atomic Energy Agency (JAEA). The estimated time history variation of I-131 concentrations in plumes was in fair agreement with those measured directly by an air sampling method. The difference was less than a factor of 4 for plumes that arrived on March 15 and March 21, indicating relatively high I-131 concentrations among the plumes studied in this work.

JAEA Reports

Reactivity effect of spent fuel depending on burn-up history

Hayashi, Takafumi*; Suyama, Kenya; Mochizuki, Hiroki*; Nomura, Yasushi

JAERI-Tech 2001-041, 158 Pages, 2001/06

JAERI-Tech-2001-041.pdf:5.15MB

no abstracts in English

Journal Articles

Estimation of spent fuel compositions from light water reactors

Ando, Yoshihira*; Nishihara, Kenji; Takano, Hideki

Journal of Nuclear Science and Technology, 37(10), p.924 - 933, 2000/10

no abstracts in English

JAEA Reports

CORCON-Mod3 analysis of SURC experiments on molten core concrete interaction

J.Yan*; Maruyama, Yu; Sugimoto, Jun

JAERI-Tech 95-052, 27 Pages, 1995/12

JAERI-Tech-95-052.pdf:1.32MB

no abstracts in English

Journal Articles

Estimation of irradiation history of a spent fuel by gamma-ray spectroscopy

Tasaka, Kanji

Nuclear Technology, 29(2), p.239 - 248, 1976/02

 Times Cited Count:1

no abstracts in English

JAEA Reports

STAT:A Code for Analysis of Statistical Properties of Averaged Resonance Cross Section

Kikuchi, Yasuyuki

JAERI-M 6248, 17 Pages, 1975/09

JAERI-M-6248.pdf:0.7MB

no abstracts in English

Oral presentation

60th Anniversary of Investigation Committee for Nuclear Data; All Japan endeavor for nuclear data activities, 1; 60 years of Investigation Committee for Nuclear Data

Fukahori, Tokio

no journal, , 

Initially, the Sigma Committee consisted of two sides of the same coin: the Atomic Energy Society of Japan (AESJ) Sigma Special Committee and the Japan Atomic Energy Research Institute (JAERI) Sigma Research Committee. It is original the Sigma Committee conducts actual work such as research, evaluation and evaluation of nuclear data (including measurement, called "nuclear data activity") rather than a "place for examination" that can be felt from the sense of the word "committee". At present, the AESJ's Investigation Committee of Nuclear Data and the JAEA's JENDL Committee are working independently, and the JENDL Committee has taken over the actual work of producing nuclear data files. On the occasion of the 60th anniversary of the Sigma Committee, we have reviewed its progress and historical description so far given in the references.

Oral presentation

Experience of waste management in decommissioning of FUGEN

Tezuka, Masashi

no journal, , 

Regarding the disposal of radioactive waste, Japan Nuclear Fuel already operates a repository for commercial reactor at Rokko, and waste materials such as research facilities are under consideration by JAEA, the implementing entity. In Fugen under decommissioning, the dismantled waste is separated and managed according to the radioactivity level classification, type, lineage, etc., and the waste management system is used to manage the history.

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