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.

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.

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

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

https://doi.org/10.3327/taesj.J14.006

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.

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

https://doi.org/10.3327/jnst.37.924

no abstracts in English

Current trend and future prospect of nuclear instruments in industrial radioisotope applications

Radioisotopes, 33(2), p.100 - 108, 1984/00

https://doi.org/10.3769/radioisotopes.33.2_100

no abstracts in English

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

Tasaka, Kanji

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

https://doi.org/10.13182/NT76-A31583

no abstracts in English

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.