Calculational method error correlation effect in data adjustment for large LMFBFs [liquid metal fast breeder reactors]
- 1. Osaka Univ. (Japan)
- 2. Power Reactor and Nuclear Fuels Development Corporation, Ibaraki (Japan)
Description
The analysis of JUPITER experiments, in a cooperative effort between the United States and Japan using the zero-power plutonium reactor (ZPPR), showed a discrepancy for the ratio of calculated experimental (C/E) values of control rod worth. The C/E value at the core edge was larger by ∼12% than that at the core center. This discrepancy has a strong effect on the design of control rods. To reduce the discrepancy, many effort have been made from the calculational point of view; however, a drastic improvement has not been achieved. The purpose of this paper is to clarify that the discrepancy is drastically improved by the cross-section adjustment if we consider the cross correlation between the calculational method's errors for individual control rods
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 599-600
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085783
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADMINISTRATIVE PROCEDURES; ALGORITHMS; CONTROL ELEMENTS; CONTROL ROD WORTHS; COORDINATED RESEARCH PROGRAMS; CROSS SECTIONS; DATA COVARIANCES; ERRORS; INTERNATIONAL COOPERATION; JAPAN; LMFBR TYPE REACTORS; REACTOR CORES; REACTOR PHYSICS; SPECIFICATIONS; USA; ZPPR REACTOR
- Descriptors DEC
- ASIA; BREEDER REACTORS; COOPERATION; DEVELOPED COUNTRIES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; NORTH AMERICA; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH PROGRAMS; RESEARCH REACTORS; ZERO POWER REACTORS
Optional Information
- Secondary number(s)
- CONF-891103--.