Published June 1996
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Thermal reactor benchmark testing of CENDL-2 and ENDF/B-6
Description
In order to test CENDL-2, ten homogeneous and eight heterogeneous thermal assemblies were used. Both of 123 group cross section libraries based on CENDL-2 and ENDF/B-6 were generated by a nuclear data processing system NSLINK, respectively. The calculations of resonance self-shielding, cell spectra, cell reaction rate ratios and effective multiplication factors (Keff) of these assemblies have been performed by the modified PASC-1 code system. The calculated results using CENDL-2 show an excellent agreement with corresponding experimental values. However, for some assemblies the Keff values calculated by ENDF/B-6 data are underestimated. (7 tabs.)
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Additional details
Publishing Information
- Imprint Title
- Communication of nuclear data progress: No.15 (1996)
- Imprint Pagination
- 110 p.
- Journal Page Range
- p. 87-94.
- Report number
- CNIC--01075
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 28028296
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; CROSS SECTIONS; DATA; DATA ANALYSIS; MULTIPLICATION FACTORS; P CODES; TESTING; THERMAL REACTORS; ZERO POWER REACTORS
- Descriptors DEC
- COMPUTER CODES; EXPERIMENTAL REACTORS; INFORMATION; REACTORS; RESEARCH AND TEST REACTORS
Optional Information
- Secondary number(s)
- CNDC--0018; INDC(CPR)--040/L.