Study on Pu-burner high temperature gas-cooled reactor in Japan; Design study of fuel and reactor core

Goto, Minoru; Aihara, Jun; Inaba, Yoshitomo; Ueta, Shohei; Fukaya, Yuji; Okamoto, Koji*

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 6 Pages, 2018/10

JAEA has conducted design studies of a Pu-burner HTGR. The Pu-burner HTGR incinerates Pu by fission, and hence a high burn-up is required for the efficient incineration. In the fuel design, a thin ZrC layer, which acts as an oxygen getter and suppresses the internal pressure, was coated on the fuel kernel to prevent the CFP failure at the high burn-up. A stress analysis of the SiC layer, which acts as a pressure vessel for the CFP, was performed for with consideration of the depression effect due to the ZrC layer. As a result, the CFP failure fraction at high burn-up of 500 GWd/t satisfied the target value. In the reactor core design, an axial fuel shuffling was employed to attain the high burn-up, and the nuclear burn-up calculations with the whole core model and the fuel temperature calculations were performed. As a result, the nuclear characteristics, which are the shutdown margin and the temperature coefficient of reactivity, and the fuel temperature satisfied their target values.

Development of pellet melting temperature measuring technique; Melting temperature measuring technique for small sample

Harada, Katsuya; Nakata, Masahito; Harada, Akio; Nihei, Yasuo; Yasuda, Ryo; Nishino, Yasuharu

JAERI-Tech 2004-034, 13 Pages, 2004/03

JAERI-Tech-2004-034.pdf:0.69MB

The Department of Hot Laboratories has been aiming the establishment of the melting temperature measuring technique for small samples obtained from the micro-region of irradiated fuel pellet. Due to the modification of the shape of tungsten capsule contained sample and the improvement of the detection method for melting temperature from indistinct thermal arrest point owing to small sample, it is possible to determine the melting temperature of small sample and to utilize effectively for the irradiated fuel pellet by using the existing apparatus. This paper describes the technique of the melting temperature measurement for small sample and the experimental results by using tantalum, molybdenum, hafnium oxide and un-irradiated UO pellet.

Light water reactor fuel analysis code FEMAXI-6, 1; Detailed structure and user's manual

Suzuki, Motoe; Saito, Hiroaki*

JAERI-Data/Code 2003-019, 423 Pages, 2003/12

JAERI-Data-Code-2003-019.pdf:17.7MB

A light water reactor fuel analysis code FEMAXI-6 is an advanced version which has been produced by integrating the former version with a number of improvements. In particular, the FEMAXI-6 code has attained a complete coupled solution of thermal analysis and mechanical analysis, permitting an accurate prediction of pellet-clad gap size and PCMI in high burnup fuel rods. Also, such new models have been implemented as pellet-clad bonding and fission gas bubble swelling, and the coupling with burning analysis code has been enhanced. Furthermore, a number of new materials properties and parameters have been introduced. With these advancements, the FEMAXI-6 code is a versatile tool not only in the normal operation but also in transient conditions. This report describes the design, basic theory, models and numerical method, improvements, and model modification. In order to facilitate effective and wide-ranging application of the code, formats and methods of input/output, and a sample output in an actual form are included.

Density, porosity and grain size, 2; Irradiated ROX fuels to burn-up of 28%FIMA

Yanagisawa, Kazuaki; Yamashita, Toshiyuki; Kanazawa, Hiroyuki; Amano, Hidetoshi; Muromura, Tadasumi

Journal of Nuclear Science and Technology, 36(12), p.1153 - 1159, 1999/12

https://doi.org/10.3327/jnst.36.1153

no abstracts in English

SRAC95; General purpose neutronics code system

Okumura, Keisuke; ;

JAERI-Data/Code 96-015, 445 Pages, 1996/03

JAERI-Data-Code-96-015.pdf:12.94MB

no abstracts in English

Performance of high burned PWR fuel during transient

Yanagisawa, Kazuaki;

Proc. of the 4th Int. Symp. on Advanced Nuclear Energy Research (JAERI-CONF 1/JAERI-M 92-207), p.509 - 516, 1992/12

https://jopss.jaea.go.jp/pdfdata/JAERI-M-92-207.pdf

no abstracts in English

Study of pellet-cladding interaction on light water reactor fuel, (I); PWR type fuel rod

; ; E.Kolstad*

Nihon Genshiryoku Gakkai-Shi, 28(7), p.641 - 657, 1986/00

https://doi.org/10.3327/jaesj.28.641

no abstracts in English

Reference Core Design of the Experimental Multi-Purpose Very High Temperature Reactor; Study of Core Nuclear Characteristics for Design of the Core Configuration

; ; Aruga, T.;

JAERI-M 8519, 113 Pages, 1979/11

JAERI-M-8519.pdf:2.75MB

no abstracts in English

「Burn-up measurement」, 5; Nondestructive measurement of burn-up

; ; Matsuura, Shojiro; ;

Nihon Genshiryoku Gakkai-Shi, 15(6), p.368 - 373, 1973/06

no abstracts in English

Design study on fuel and reactor core for plutonium burner high temperature gas-cooled reactor

Goto, Minoru; Inaba, Yoshitomo; Fukaya, Yuji; Ueta, Shohei; Aihara, Jun; Tachibana, Yukio; Kunitomi, Kazuhiko

no journal, , 

A concept of a plutonium burner HTGR (High Temperature Gas-cooled Reactor) with a high nuclear proliferation resistance has been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to attain the high burn-up, we propose to introduce a PuO-YSZ (Yttria Stabilized Zirconia) fuel kernel with ZrC coating to the plutonium burner HTGR. In this study, we conduct design of the coated fuel particle and of the reactor core to confirm the feasibility of the plutonium burner HTGR. This study was started in FY2014 and will be completed in FY2017, and the implementation is on schedule. This paper describes the implementation of the first and the second year.