Validation of the nuclear design code system for the HTTR using the criticality assembly VHTRC

Nuclear Engineering and Design

Volumn 233, Issue 1-3, 2004, Pages 155-162

  Fujimoto, Nozomu ^a   Nojiri, Naoki ^a   Yamashita, Kiyonobu ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CONTROL RODS; COOLANTS; DATA REDUCTION; MONTE CARLO METHODS; NEUTRONS; SPECTRUM ANALYSIS; THERMAL EFFECTS; THERMAL EXPANSION;

DESIGN CODES; HIGH TEMPERATURE ENGINEERING TEST REACTOR; NUCLEAR DESIGNS; REACTIVITY;

HIGH TEMPERATURE ENGINEERING;

EID: 10644243680     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.08.005     Document Type: Conference Paper

References (4)

1. Saito, S., et al., 1994. Design of high temperature engineering test reactor (HTTR). JAERI 1332.
2. Tsuchihashi, K., Ishiguro, Y., Kaneko, K., Ido, M., 1986. Revised SRAC code system. JAERI 1302.
3. Yamashita, K., Murata, I., Shindo, R., 1992. Analysis of overall temperature coefficient of reactivity of the VHTRC-1 Core with a nuclear design code system for the high-temperature engineering test reactor. Nucl. Sci. Eng. 110, 177-185.
4. Yamashita, K., Shindo, R., Murata, I., Murata, S., Fujimoto, N., Takeda, T., 1996. Nuclear design of the high-temperature engineering test reactor (HTTR). Nucl. Sci. Eng. 122, 212-228.