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.

Analysis of the radioactivity concentrations in radioactive waste generated from JRR-3, JRR-4 and JRTF facilities

Tobita, Minoru*; Konda, Miki; Omori, Takeshi*; Nabatame, Tsutomu*; Onizawa, Takashi*; Kurosawa, Katsuaki*; Haraga, Tomoko; Aono, Ryuji; Mitsukai, Akina; Tsuchida, Daiki; et al.

JAEA-Data/Code 2022-007, 40 Pages, 2022/11

JAEA-Data-Code-2022-007.pdf:1.99MB

Radioactive wastes generated from nuclear research facilities in Japan Atomic Energy Agency are planning to be buried in the near surface disposal field. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes until the beginning of disposal. In order to contribute to this work, we collected and analyzed concrete, ash, ceramic and brick samples generated from JRR-3, JRR4 and JRTF facilities. In this report, we summarized the radioactivity concentrations of 24 radionuclides (H, C, Cl, Ca, Co, Ni, Sr, Nb, Tc, Ag, I, Cs, Ba, Eu, Eu, Ho, U, U, Pu, Pu, Pu, Am, Am, Cm) which were obtained from radiochemical analysis of the samples in fiscal years 2020-2021.

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR and JRR-4

Aono, Ryuji; Mitsukai, Akina; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka

JAEA-Data/Code 2020-006, 70 Pages, 2020/08

JAEA-Data-Code-2020-006.pdf:2.59MB

Radioactive wastes which generated from research and testing reactors in Japan Atomic Energy Agency are planning to be buried at the near surface disposal field. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes by the time it starts disposal. In order to contribute to this work, we collected and analyzed the samples generated from JPDR and JRR-4. In this report, we summarized the radioactivity concentrations of 19 radionuclides (H, C, Cl, Co, Ni, Sr, Nb, Tc, Ag, I, Cs, Eu, Eu, U, U, Pu, Pu, Am, Cm) which were obtained from radiochemical analysis of those samples.

Annual report of Department of Research Reactor and Tandem Accelerator, JFY2013; Operation, utilization and technical development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2014-047, 153 Pages, 2015/02

JAEA-Review-2014-047.pdf:23.43MB

The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility. This annual report describes a summary of activities of services and technical developments carried out in the period between April 1, 2013 and March 31, 2014.

Current status and future prospects of industrial application for the neutron, Neutron radiography

Matsubayashi, Masahito; Kawabata, Yuji*

Hoshasen To Sangyo, (107), p.4 - 15, 2005/09

http://ci.nii.ac.jp/naid/40006907678

http://ci.nii.ac.jp/naid/40006907680

no abstracts in English

Management techniques of the JRR-4 heat exchanger

Horiguchi, Hironori; Oyama, Koji; Ishikuro, Yasuhiro; Hirane, Nobuhiko; Ito, Kazuhiro; Kameyama, Iwao

JAERI-Tech 2005-001, 38 Pages, 2005/02

JAERI-Tech-2005-001.pdf:2.79MB

After JRR-4 heat exchanger was renewed in made of stainless steel from carbon steel, it was examined how to manage the heat exchanger. The main subject is the cleaning technology of the heat exchanger. The recovery of old heat exchanger cooling performance has been by only chemical cleaning. Now we use chemical and dry cleaning as a new technique. It helps prevent of corrosions of secondary pipes and reduce of management costs. This report describes the performance management and cleaning technology of the JRR-4 heat exchanger and the management of the JRR-4 coolant.

Calibration of epithermal neutron beam intensity for dosimetry at JRR-4

Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Sakurai, Yoshinori*; Kobayashi, Toru*

Proceedings of 11th World Congress on Neutron Capture Therapy (ISNCT-11) (CD-ROM), 15 Pages, 2004/10

To carry out the boron neutron capture therapy (BNCT) using the epithermal neutron, the epithermal neutron beam intensity was measured by using Au reaction rate activated on the resonance absorption peak (4.9eV). Two scaling factors, which are the reactor power calibration factor and the calculation/experiment (C/E) scaling factor, are necessary in order to correct with the simulation and actual irradiation experiment. First, an optimum detector position was investigated using MCNP code. The result of MCNP calculation showed that the influence of subject placed at the collimator was below 1% when the detector was placed in the distance of over 20cm from the collimator. Therefore we installed the monitor holders near the bismuth block in order to set three gold wire monitors. The factors were determined in the calibration experiments that measure the thermal neutron flux in the phantom and reaction rate of the gold wire monitors. The monitoring technique to measure epithermal neutron beam intensity was applied to clinical irradiation with the epithermal neutron beam.

Verification of the JAERI Computational Dosimetry System (JCDS) for boron neutron capture therapy

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya; Matsumura, Akira*; Nakagawa, Yoshinobu*

Japanese Journal of Medical Physics, Vol.23, Supplement 3, p.292 - 295, 2003/09

no abstracts in English

Development of the JAERI Computational Dosimetry System (JCDS) for boron neutron capture therapy (Cooperative research)

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya; Matsumura, Akira*; Yamamoto, Tetsuya*; Nose, Tadao*; Nakagawa, Yoshinobu*; Kageji, Teruyoshi*; Uchiyama, Junzo

JAERI-Tech 2003-002, 49 Pages, 2003/03

JAERI-Tech-2003-002.pdf:5.22MB

no abstracts in English

Clinical review of boron neutron capture therapy and a proposed strategy using epithermal neutron beams in Japan

Nakagawa, Yoshinobu*; Pooh, K. H.*; Kageji, Teruyoshi*; Uyama, Shinichi*; Kobayashi, Toru*; Sakurai, Yoshinori*; Matsumura, Akira*; Yamamoto, Tetsuya*; Kumada, Hiroaki

Research and Development in Neutron Capture Therapy, p.1113 - 1116, 2002/09

To make a new protocol using epithermal neutron beam for high-grade glioma patients, we elucidated the relationship between the radiation dose, histological tumor grade, and clinical outcome. One hundred and eighty-three patients with kinds of brain tumors were treated by BNCT since 1968, however, we performed a retrospective study of 105 patients with glial tumors treated in Japan between 1978 and 1997. As for the radiation side effect, we analyzed all patients(n=159) treated between 1977 and 2001. Ten patients with glioblastoma were treated according to the new protocol using epithermal neutron.