Development of fuel temperature calculation code "FTCC" for high temperature gas-cooled reactors

Inaba, Yoshitomo; Isaka, Kazuyoshi; Shibata, Taiju

JAEA-Data/Code 2017-002, 74 Pages, 2017/03

JAEA-Data-Code-2017-002.pdf:2.36MB

In order to ensure the thermal integrity of fuel in High Temperature Gas-cooled Reactors (HTGRs), it is necessary that the maximum fuel temperature in normal operation is to be lower than a thermal design target. In the core thermal-hydraulic design of block-type HTGRs, the maximum fuel temperature should be evaluated considering data such as core geometry and specifications, power density and neutron fluence distributions, and core coolant flow distribution. The fuel temperature calculation code used in the design stage of the High Temperature engineering Test Reactor (HTTR) presupposes to run on UNIX systems, and its operation and execution procedure are complicated and are not user-friendly. Therefore, a new fuel temperature calculation code, named FTCC, which has a user-friendly system such as a simple and easy operation and execution procedure, was developed. This report describes the calculation objects and models, the basic equations, the strong points (improvement points from the HTTR design code), the code structure, the using method of FTCC, and the result of a validation calculation with FTCC. The calculation result obtained by FTCC provides good agreement with that of the HTTR design code, and then FTCC will be used as one of the design codes for high temperature gas-cooled reactors. In addition, the effect of hot spot factors and fuel cooling forms on reducing the maximum fuel temperature is investigated with FTCC. As a result, it was found that the effect of center hole cooling for hollow fuel compacts and gapless cooling with monolithic type fuel rods on reducing the temperature is very high.

Heat transfer characteristics evaluation of heat exchangers of mock-up test facility with full-scale reaction tube for HTTR hydrogen production system (Contract research)

Shimizu, Akira; Ohashi, Hirofumi; Kato, Michio; Hayashi, Koji; Aita, Hideki; Nishihara, Tetsuo; Inaba, Yoshitomo; Takada, Shoji; Morisaki, Norihiro; Sakaki, Akihiro*; et al.

JAERI-Tech 2005-031, 174 Pages, 2005/06

JAERI-Tech-2005-031.pdf:20.71MB

Connection of hydrogen production system by steam reforming of methane to the High Temperature Engineering Test Reactor (HTTR) of the Japan Atomic Energy Research Institute (JAERI) has been surveyed until now. Mock-up test facility of this steam reforming system with full-scale reaction tube was constructed in FY 2001, and a lot of operational test data on heat exchanges were obtained in these tests.In this report specifications, structures and heat transfer formulae of steam reformer, steam superheater, steam generator, condenser, helium gas cooler, feed gas heater and feed gas superheater were described. Evaluation codes were newly made to evaluate heat transfer characteristics from measured test data. Overall heat-transfer coefficient obtained from the experimental data were compared and evaluated with the prospective value calculated with heat transfer formulae. As a result, heat transfer performance and thermal efficiency of these heat exchangers were confirmed to be appropriate.

New cryogenic steels and design approach for ITER superconducting magnet system

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Hada, Kazuhiko; Tada, Eisuke

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00

The Japan Atomic Energy Research Institute (JAERI) has conducted to develop a new design code for construction and operation/maintenance of the International Thermonuclear Experimental Reactor (ITER), which will be formed as a code case of ASME B&PV Code Section III, division 4, in collaboration with the ASME international. The new design code will also include the several new techniques and materials developed for each components of ITER. This paper describes the new cryogenic steels used in the magnet system and the design approach with taking account of unique features of the ITER superconducting magnets.

Benchmark problems of start-up core physics of High Temperature engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Nojiri, Naoki; Fujimoto, Nozomu; Nakano, Masaaki*; Ando, Hiroei; Nagao, Yoshiharu; Nagaya, Yasunobu; Akino, Fujiyoshi; Takeuchi, Mitsuo; Fujisaki, Shingo; et al.

Proc. of IAEA TCM on High Temperature Gas Cooled Reactor Applications and Future Prospects, p.185 - 197, 1998/00

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

Intelligent system for conceptual design of new reactor cores

Kugo, Teruhiko; Nakakawa, Masayuki

Transactions of the American Nuclear Society, 73, p.207 - 208, 1995/00

no abstracts in English

Development of REFLA/TRAC code for engineering work station

Onuki, Akira; ; Murao, Yoshio

JAERI-M 94-026, 60 Pages, 1994/03

JAERI-M-94-026.pdf:1.81MB

no abstracts in English

Development of shielding design code for synchrotron radiation beam line

Asano, Yoshihiro; Sasamoto, Nobuo

Radiation Physics and Chemistry, 44(1-2), p.133 - 137, 1994/00

https://doi.org/10.1016/0969-806X(94)90119-8

no abstracts in English

Development of a BWR core burn-up calculation code COREBN-BWR

*; Okumura, Keisuke

JAERI-M 92-068, 107 Pages, 1992/05

JAERI-M-92-068.pdf:2.79MB

no abstracts in English

An Explication of design data of the graphite structural design code for core support components of High Temperature Engineering Test Reactor

Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku

JAERI-M 91-154, 39 Pages, 1991/10

JAERI-M-91-154.pdf:0.73MB

no abstracts in English