Published August 2000 | Version v1
Miscellaneous

Development of a generalized perturbation theory program for applications to optimum refueling simulation and uncertainty analysis of a CANDU reactor

Description

A generalized perturbation theory (GPT) program, GENOVA, has been developed for the purpose of various applications to Canadian deuterium uranium (CANDU) reactor physics analyses. GENOVA was written under the framework of CANDU physics design and analysis code, RFSP. A sensitivity method based on the GPT was implemented in GENOVA to estimate various sensitivity coefficients related to the movement of zone controller units (ZCUs) existing in the CANDU reactor. The numerical algorithm for the sensitivity method was verified by a simple 2x2 node problem. The capability of predicting ZCU levels upon a refueling perturbation was validated for a CANDU-6 reactor problem. The applicability of GENOVA to the CANDU-6 core physics analysis has been demonstrated with the optimum refueling simulation and the uncertainty analysis problems. For the optimum refueling simulation, an optimum channel selection strategy has been proposed, using the ZCU level predicted by GENOVA. The refueling simulation of a CANDU-6 natural uranium core has shown that the ZCU levels are successfully controlled within the operating range while the channel and bundle powers are satisfying the license limits. An uncertainty analysis has been performed for the fuel composition heterogeneity of a CANDU DUPIC core, using the sensitivity coefficients generated by GENOVA. The results have shown that the uncertainty of the core performance parameter can be reduced appreciably when the contents of the major fissile isotopes are tightly controlled. GENOVA code has been successfully explored to supplement the weak points of the current design and analysis code, such as the incapacity of performing an optimum refueling simulation and uncertainty analysis. The sample calculations have shown that GENOVA has strong potential to be used for CANDU core analysis combined with the current design and analysis code, RFSP, especially for the development of advanced CANDU fuels

Availability note (English)

Available from Hanyang University, Seoul (KR)

Additional details

Publishing Information

Imprint Pagination
134 p.

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44096334
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Thesis, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; DESIGN; G CODES; PERTURBATION THEORY; REACTOR PHYSICS; SENSITIVITY; USES
Descriptors DEC
COMPUTER CODES; HEAVY WATER MODERATED REACTORS; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
41 refs, 19 figs, 28 tabs