High power transient characteristics and capability of NSRR

Nakamura, Takehiko; Katanishi, Shoji; Kashima, Yoichi; Yachi, Shigeyasu; Yoshinaga, Makio; Terakado, Yoshibumi

Journal of Nuclear Science and Technology, 39(3), p.264 - 272, 2002/03

https://doi.org/10.3327/jnst.39.264

In order to study fuel behavior under abnormal transients and accidents, the control system of the Nuclear Safety Research Reactor (NSRR) of the Japan Atomic Energy Research Institute (JAERI) was modified to achieve high power transients. With this new operational mode, called Shaped Pulse (SP), transients at the maximum power of 10 MW can be conducted for a few seconds. This new operational mode supplements the previous Natural Pulse (NP) operation at the maximum power of 23 GW for milliseconds. For high power transient operation, a simulator using a point kinetic model was developed, and characteristics of the NSRR in the new operational mode were examined through tests and calculations. With the new operational mode, new types of fuel irradiation tests simulating power oscillations of boiling water reactors (BWRs) can to be conducted in the NSRR. Reactor characteristics and capability, such as control rod worth, feedback reactivity, and operational limits of the NSRR for SP operations are discussed.

Behavior of rock-like oxide fuels under reactivity initiated accident conditions

Kusagaya, Kazuyuki*; Nakamura, Takehiko; Yoshinaga, Makio; Okonogi, Kazunari*; Uetsuka, Hiroshi

JAERI-Research 2001-010, 44 Pages, 2001/03

JAERI-Research-2001-010.pdf:9.91MB

no abstracts in English

Evaluation of burnup characteristics and energy deposition during NSRR pulse irradiation tests on irradiated BWR fuels

Nakamura, Takehiko; Takahashi, Masato*; Yoshinaga, Makio

JAERI-Research 2000-048, 77 Pages, 2000/11

JAERI-Research-2000-048.pdf:6.04MB

no abstracts in English

Development of sodium facilities for NSRR fast reactor fuel tests, 2; Sodium capsule

Yoshinaga, Makio; Nakamura, Takehiko; Yamazaki, Toshi*

JAERI-Tech 2000-017, p.59 - 0, 2000/03

JAERI-Tech-2000-017.pdf:2.31MB

no abstracts in English

Burnup calculation with estimated neutron spectrum of JMTR irradiation field; Development of the burnup calculation method for fuel pre-irradiated in the JMTR

Okonogi, Kazunari*; Nakamura, Takehiko; Yoshinaga, Makio; *

JAERI-Data/Code 99-018, 112 Pages, 1999/03

JAERI-Data-Code-99-018.pdf:4.48MB

no abstracts in English

Development of the new type moderator vessel for the cold neutron source in the JRR-3, 1; Pressure test

Yoshinaga, Makio; Tamura, Itaru; Komeda, Masao; Yamamoto, Kazuyoshi; Sagawa, Hisashi

no journal, , 

no abstracts in English

Optimum layout of upgraded cold neutron guides at the JRR-3 by computational neutron beam transportation

Tamura, Itaru; Yamamoto, Kazuyoshi; Hazawa, Tomoya; Yoshinaga, Makio; Komeda, Masao; Sagawa, Hisashi

no journal, , 

no abstracts in English