Published January 15, 2018 | Version v1
Book

Covariance analysis in reactor physics experiments

Creators

  • 1. Reactor Physics Design Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Experimental reactor physics is an essential element of physics design of a nuclear reactor and plays an important role in the safe design and operation of nuclear reactors. Approximations in modelling the reactor using computer codes and the 'uncertainty in the nuclear data' that goes as input into these codes contribute to the uncertainty of the theoretically computed design parameters. Reactor physics experiments provide estimates of the uncertainty in the design by comparing the measured and computed values of these parameters. A thorium fuel cycle based advanced heavy water reactor (AHWR) is being designed in Reactor Physics Design Division, BARC. A zero power critical facility (CF) was commissioned to generate the experimental data for physics design validation of AHWR. A number of experiments were carried out in CF which includes the measurement of differential/integral parameters and various reaction rates. The covariance analysis of these measurement will be carried out to generate the relevant covariance matrices

Part of:
Proceedings of the international conference on linear algebra and its applications; Fourth DAE-BRNS theme meeting on generation and use of covariance matrices in the applications of nuclear data

Additional details

Publishing Information

Publisher
Manipal Academy of Higher Education
Imprint Place
Manipal (India)
Imprint Title
Proceedings of the international conference on linear algebra and its applications; Fourth DAE-BRNS theme meeting on generation and use of covariance matrices in the applications of nuclear data
Imprint Pagination
144 p.
Journal Page Range
p. 34

Conference

Title
international conference on linear algebra and its applications; 4. DAE-BRNS theme meeting on generation and use of covariance matrices in the applications of nuclear data
Acronym
ICLAA-2017
Dates
9-15 Dec 2017
Place
Manipal (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
50081147
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CROSS SECTIONS; DATA COVARIANCES; NUCLEAR FACILITIES; REACTION KINETICS; REACTOR ACCIDENTS; REACTOR SAFETY; SIMULATION; THORIUM CYCLE
Descriptors DEC
ACCIDENTS; FUEL CYCLE; KINETICS; SAFETY

Optional Information