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JAEA Reports

Nuclear criticality benchmark analyses on TRIGA-type reactor systems by using continuous-energy Monte Carlo code MVP with JENDL-5

Yanagisawa, Hiroshi; Umeda, Miki; Motome, Yuiko; Murao, Hiroyuki

JAEA-Technology 2022-030, 80 Pages, 2023/02

JAEA-Technology-2022-030.pdf:2.57MB
JAEA-Technology-2022-030(errata).pdf:0.11MB

Nuclear criticality benchmark analyses were carried out for TRIGA-type reactor systems in which uranium-zirconium hydride fuel rods are loaded by using the continuous-energy Monte Carlo code MVP with the evaluated nuclear data library JENDL-5. The analyses cover two sorts of benchmark data, the IEU-COMP-THERM-003 and IEU-COMP-THERM-013 in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook, and effective neutron multiplication factors, reactivity worths for control rods etc. were calculated by JENDL-5 in comparison with those by the previous version of JENDL. As the results, it was confirmed that the effective neutron multiplication factors obtained by JENDL-5 were 0.4 to 0.6% greater than those by JENDL-4.0, and that there were no significant differences in the calculated reactivity worths by between JENDL-5 and JENDL-4.0. Those results are considered to be helpful for the confirmation of calculation accuracy in the analyses on NSRR control rod worths, which are planned in the future.

Journal Articles

Evaluation of radiation effects on residents living around the NSRR under external hazards

Motome, Yuiko; Akiyama, Yoshiya; Murao, Hiroyuki

Journal of Nuclear Engineering and Radiation Science, 6(2), p.021115_1 - 021115_11, 2020/04

The nuclear safety research reactor (NSRR) is a research reactor of training research isotopes general atomics -annular core pulse reactor type. The NSRR facility has been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity-initiated accident conditions. Under the new regulation standards, which was established after the Fukushima Daiichi accident, research reactors are regulated based on the risk of the facilities. To apply the graded approach, the radiation effects on residents living around the NSRR under the external hazards were evaluated, and the level of the risk of the NSRR facility was investigated. This paper summarizes the result of the evaluation in the case where the safety functions are lost due to a tornado, an earthquake followed by a tsunami. All in all, the risk is confirmed to be relatively low, since the effective dose on the residents is found to be below 5 mSv per event due to the loss of the safety functions.

Journal Articles

Evaluation of the radiation effects of residents living around the NSRI under the external hazards

Motome, Yuiko; Akiyama, Yoshiya; Murao, Hiroyuki

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 8 Pages, 2018/07

The NSRR is a research reactor of TRIGA-ACPR type, located in the Nuclear Science Research Institute. The NSRR facility has been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity initiated accident conditions. Under the new regulation standards after the Fukushima Daiichi accident, the research reactors are being regulated according to the risk of the facility. Graded approach is introduced in the regulation. In order to apply the graded approach, the radiation effects of residents living around the NSRI under the external hazards were evaluated and the level of the risk of the NSRR facility was investigating. This report is summarized for the result of the evaluation in case the safety functions were lost by the tornado, earthquake and following tsunami. As the result, the risk is confirmed to be low, since the effective dose of the residents has been below 5 mSv per event due to the loss of the safety functions by the tornado, earthquake and following tsunami.

JAEA Reports

Criticality safety evaluation of the fresh fuel storage in NSRR; Under consideration of earthquake and tsunami occurrence

Motome, Yuiko; Murao, Hiroyuki

JAEA-Technology 2017-007, 18 Pages, 2017/03

JAEA-Technology-2017-007.pdf:2.16MB

Nuclear Safety Research Reactor (NSRR) facility have been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity initiated accident conditions. Unirradiated test fuels used in fuel irradiation experiments and flesh driver fuel elements for reactor operation are stored in the fuel building of the facility. In response to the 2011 off the Pacific coast of Tohoku Earthquake, the impact of NSRR's nuclear fuel material usage facilities on external events beyond design requirements was evaluated. The subcriticality of the flesh fuel storage was confirmed in consideration of earthquake and tsunami as superimposed event.

JAEA Reports

Design of type X-IV atmospheric pressure capsule for irradiation test based on JSME S NC-1 2005

Murao, Hiroyuki; Muramatsu, Yasuyuki; Okawara, Masami; Shibata, Isao

JAEA-Technology 2006-062, 32 Pages, 2007/02

JAEA-Technology-2006-062.pdf:1.81MB

In NSRR (Nuclear Safety Research Reactor) experiments, test fuels are inserted in the especial capsule and the capsule will be inserted into the experimental tube which is located in the center of reactor core. In NSRR, there are 17 types of atmospheric pressure capsule, and one of them Type X-IV atmospheric pressure capsule has been produced 6 times under authorization of Ministry of Education, Culture, Sports, Science and Technology (MEXT). Application for the 7th time of authorization was submitted to the MEXT in June 2006. On this application, standard which is used to design was changed to The Japan Society of Mechanical Engineers (JSME) S NC1-2005 from the Notification 501 of the Ministry of Economy, Trade and Industry (METI). The JSME S NC1-2005 introduced the service condition in addition to the reactor condition which has been used in the Notification 501. In this application, stress limits were calculated based on the service condition. The JSME S NC1-2005 requires estimation of combined stress for Class1 support structures, which was unnecessary in the Notification 501. In this application, combined stresses were calculated and confirmed not to exceed the stress limits.

Journal Articles

Improvement of the NSRR simulator

Murao, Hiroyuki; Yachi, Shigeyasu; Ota, Kazunori; Muramatsu, Yasuyuki; Nakamura, Takehiko; Terakado, Yoshibumi

UTNL-R-0435, p.15_1 - 15_9, 2004/03

no abstracts in English

JAEA Reports

Improvement of the NSRR simulator

Murao, Hiroyuki; Yachi, Shigeyasu; Ota, Kazunori; Muramatsu, Yasuyuki; Nakamura, Takehiko; Terakado, Yoshibumi

JAERI-Tech 2003-094, 41 Pages, 2004/01

JAERI-Tech-2003-094.pdf:2.26MB

Prior to actual runs in the shaped pulse and in the combined pulse operations, the online simulation and the offline simulation must be performed to examine safety and appropriation. Actual reactor power of the NSRR can be simulated practically, but a slight difference canbe observed between the present simulation results and the actual operation during the NSRR start-up phase and power controled operation. Regulating rod worth and fuel temperature feedback reactivity were re-evaluated and installed into the simulators. As a result, the accuracy of the simulator was remarkably improved. So that the application and safety of the shaped pulse and combined pulse operation were improved.

Journal Articles

Safety analyses of a passive safety light water reactor JPSR

Araya, Fumimasa; Iwamura, Takamichi; Yoshida, Hiroyuki; Kunii, Katsuhiko; Okumura, Keisuke; Murao, Yoshio

10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.299 - 305, 1996/00

no abstracts in English

Oral presentation

Personnel training in JAEA

Murao, Hiroyuki

no journal, , 

This is a lecture of personnel training in JAEA for the IAEA sponsored Regional Workshop on the Application of the Code of Conduct on the Safety of Research Reactor for Asia region countries. Objective of the lecture is furnishing useful information to Asia region countries to establish the personnel training system. The contents are about NSRR personnel training with systematically implementation according to regulation for safety activity and some other regulations, and improvement of personnel ability with applying training programs of Nuclear Technology and Education Center and other organizations.

Oral presentation

Preliminary review of NSRR aseismic safety evaluation with revision of safety guideline

Awa, Yasuaki; Murao, Hiroyuki; Okawara, Masami; Wada, Shigeru

no journal, , 

no abstracts in English

Oral presentation

Soundness research of the pool-lining with ultrasonic flaw detector in NSRR

Akiyama, Yoshiya; Kawashima, Kazuhito; Muramatsu, Yasuyuki; Murao, Hiroyuki

no journal, , 

no abstracts in English

Oral presentation

High burn-up BWR 9$$times$$9 fuel behavior under RIA conditions

Fukuda, Takuji; Sugiyama, Tomoyuki; Usami, Koji; Murao, Hiroyuki; Nagase, Fumihisa

no journal, , 

The pulse irradiation was carried out to simulate reactivity initiated accident (RIA) by using nuclear safety research reactor (NSRR). To get the fuel enthalpy when high burn-up BWR 9$$times$$9 fuel failure. Post irradiation examination was also carried out to get the information about fuel failure factor.

Oral presentation

Behavior of high burnup PWR and BWR fuel rods in reactivity-initiated accident tests at high temperature

Sugiyama, Tomoyuki; Udagawa, Yutaka; Fukuda, Takuji; Nagase, Fumihisa; Murao, Hiroyuki; Toyokawa, Takuya

no journal, , 

no abstracts in English

Oral presentation

Critical evaluation of the flesh fuel storage in NSRR

Murao, Hiroyuki; Motome, Yuiko

no journal, , 

no abstracts in English

Oral presentation

Experimental capability of Nuclear Safety Research Reactor (NSRR)

Amaya, Masaki; Udagawa, Yutaka; Murao, Hiroyuki

no journal, , 

This presentation describes an outline of the experiment at Nuclear Safety Research Reactor (NSRR) and the instrument technology used in the NSRR experiment.

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