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Journal Articles

Void reactivity evaluation by modified conversion ratio measurements in LWR critical experiments

Yoshioka, Kenichi*; Kikuchi, Tsukasa*; Gunji, Satoshi*; Kumanomido, Hironori*; Mitsuhashi, Ishi*; Umano, Takuya*; Yamaoka, Mitsuaki*; Okajima, Shigeaki; Fukushima, Masahiro; Nagaya, Yasunobu; et al.

Journal of Nuclear Science and Technology, 52(2), p.282 - 293, 2015/02

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

We have developed a void reactivity evaluation method by using modified conversion ratio measurements in a light water reactor (LWR) critical lattice. Assembly-wise void reactivity is evaluated from the "finite neutron multiplication factor", $$k^ast$$, deduced from the modified conversion ratio of each fuel rod. The distributions of modified conversion ratio and $$k^ast$$ on a reduced-moderation LWR lattice, for which the improvement of negative void reactivity is a serious issue, were measured. Measured values were analyzed with a continuous-energy Monte Carlo method. The measurements and analyses agreed within the measurement uncertainty. The developed method is useful for validating the nuclear design methodology concerning void reactivity.

Journal Articles

Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor

Shelley, A.; Shimada, Shoichiro*; Kugo, Teruhiko; Okubo, Tsutomu; Iwamura, Takamichi

Nuclear Engineering and Design, 224(3), p.265 - 278, 2003/10

 Times Cited Count:13 Percentile:30.92

Parametric studies have been done for a PWR-type reduced-moderation water reactor (RMWR) with seed-blanket fuel assembles to achieve a high conversion ratio, negative void reactivity coefficient and a high burnup. It was found that 50 to 60% of seed in a seed-blanket assembly has higher conversion ratio. The number of seed-blanket layers is 20, in which the number of seed layers is 15 and blanket layers is 5. The fuel assembly with the height of seed of 1000mm$$times$$2, internal blanket of 150 mm and axial blanket of 400mm$$times$$2 is recommended. The conversion ratio is 1.0 and the average burnup in core region is 38.2 GWd/t. The enrichment of fissile Pu is 14.6 wt%. The void coefficient is +21.8 pcm/% void, however, it is expected that the void coefficient will be negative if the radial neutron leakage is taken into account. It is also possible to use this fuel assembly for a high core averaged burnup of 45GWd/t, however, the height of seed must be 500mm$$times$$2 to improve the void coefficient. The conversion ratio is 0.97 and void coefficient is +20.8 pcm/%void.

Journal Articles

Experimental study on thermal-hydraulics and neutronics coupling effect on flow instability in a heated channel with THYNC facility

Iguchi, Tadashi; Shibamoto, Yasuteru; Asaka, Hideaki; Nakamura, Hideo

Proceedings of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), 16 Pages, 2003/10

Thermal-hydraulic and neutronic dynamics are always interrelated in BWR core. This is called thermal-hydraulic and neutronic (T/N) coupling. Channel stability experiments with T/N coupling under non-nuclear condition are very limited. This is mainly due to the difficulties in the real-time simulation of neutron dynamics and in the fast-response void fraction measurement under high-pressure and temperature conditions. Authors have developed techniques to solve the above difficulties, and have succeeded in experimentally simulating T/N coupling under non-nuclear conditions with the THYNC facility. Using THYNC facility, T/N coupling effect on channel stability was investigated. Experiments were performed under Pressure=2-7MPa, Subcooling=10-40K, and Mass flux=270-660kg/m$$^{2}$$s. THYNC results indicated T/N coupling lowered the channel stability threshold. The reduction of channel stability threshold due to T/N coupling was small within 10% at 7MPa in the present THYNC experiment, although the experimental condition was set to be more severe than that supposed in a reactor.

Journal Articles

Advanced concept of Reduced-Moderation Water Reactor (RMWR) for plutonium multiple recycling

Okubo, Tsutomu; Takeda, Renzo*; Iwamura, Takamichi; Yamamoto, Kazuhiko*; Okada, Hiroyuki*

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 7 Pages, 2001/09

An advanced water-cooled reactor concept named the Reduced-Moderation Water Reactor (RMWR) has been proposed to attain a high conversion ratio more than 1.0 and to achieve the negative void reactivity coefficient. At present, several types of design concepts satisfying both the design targets have been proposed based on the evaluation for the fuel without fission products and minor actinides. In this paper, the feasibility of the RMWR core is investigated and confirmed for the plutonium multiple recycling under advanced reprocessing schemes with low decontamination factors as proposed for the FBR fuel cycle.

Journal Articles

Study on reactivity feedback effects in the TRACY transient experiments

Nakajima, Ken; ;

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 3, p.1286 - 1292, 1999/00

no abstracts in English

Journal Articles

Experimental verification and analysis of neutron streaming effect through void holes for control rod insertion in HTTR

Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko

Journal of Nuclear Science and Technology, 34(2), p.185 - 192, 1997/02

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Hydrogen generation during cladding/coolant interactions under reactivity initiated accident conditions

Fuketa, Toyoshi;

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.271 - 277, 1991/00

no abstracts in English

Journal Articles

Application of a vibrating-vane type sensor to transient void measurements in nuclear reactor in-vessel environments

; Fuketa, Toyoshi;

Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA,Vol. 2, p.247 - 250, 1991/00

no abstracts in English

Journal Articles

Accuracy of cell calculation methods used for analysis of high conversion light water lattice

C-J.Jeong*; Okumura, Keisuke; ; Tanaka, Kenichi*

Journal of Nuclear Science and Technology, 27(6), p.515 - 523, 1990/06

no abstracts in English

JAEA Reports

Analysis of Space-Time Core Dynamics on Reactor Accident at Chernobyl

; ; ;

JAERI-M 87-059, 57 Pages, 1987/05

JAERI-M-87-059.pdf:1.54MB

no abstracts in English

JAEA Reports

Journal Articles

Double heterogeneity effect of fuel pin and subassembly in a fast power reactor

Nakagawa, Masayuki; *

Nuclear Science and Engineering, 53(2), p.214 - 228, 1983/00

no abstracts in English

JAEA Reports

Experiment and Analysis of Sodium Void Reactivity Worth on FCA Assembly VI-1

; *; *; ;

JAERI-M 9931, 41 Pages, 1982/02

JAERI-M-9931.pdf:1.34MB

no abstracts in English

Journal Articles

Analysis of sodium void reactivity measured in FCA V-1 assembly

Nakagawa, Masayuki; ; Katsuragi, Satoru

Journal of Nuclear Science and Technology, 10(7), p.419 - 427, 1973/07

no abstracts in English

Oral presentation

Core design study on 750 MWe JSFR with metal fuel, 2; Core neutronics design

Ohgama, Kazuya; Ota, Hirokazu*; Ikusawa, Yoshihisa; Oki, Shigeo; Ogata, Takanari*

no journal, , 

no abstracts in English

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