This report deals with radiation transport calculations supporting safety analysis of nuclear reactors. The calculations employ Monte Carlo with the MCNP code and use the DSA variance reduction methodology. The first part of the report contains an analysis of ex-core responses, in particular pressure vessel damage, in a Gen-III PWR. Results from two approaches are compared. The first approach involves a decoupling of the problem. An analog simulation of the eigenvalue problem is performed and a fission source is created. This source is then used in a fixed source calculation with variance reduction parameters generated with the DSA. The second approach calculates the ex-core responses within the eigenvalue problem, again employing the DSA. The second part of the report deals with the PCA-Replica benchmark (SINBAD archive NEA-1517/93) concerning integral experiments performed at the NESTOR research reactor (Winfrith, UK). A fission plate irradiates a mock-up reproducing key materials for LWRs. The results are neutron spectra and dosimeter responses. Various nuclear data libraries are compared. The results show a satisfactory agreement between calculation and experiment.

Development and Application of Monte Carlo Neutronics Methodologies for Safety Studies of Current Operating Reactors

Console Camprini, Patrizio;Burn, Kenneth William
2017-11-08

Abstract

This report deals with radiation transport calculations supporting safety analysis of nuclear reactors. The calculations employ Monte Carlo with the MCNP code and use the DSA variance reduction methodology. The first part of the report contains an analysis of ex-core responses, in particular pressure vessel damage, in a Gen-III PWR. Results from two approaches are compared. The first approach involves a decoupling of the problem. An analog simulation of the eigenvalue problem is performed and a fission source is created. This source is then used in a fixed source calculation with variance reduction parameters generated with the DSA. The second approach calculates the ex-core responses within the eigenvalue problem, again employing the DSA. The second part of the report deals with the PCA-Replica benchmark (SINBAD archive NEA-1517/93) concerning integral experiments performed at the NESTOR research reactor (Winfrith, UK). A fission plate irradiates a mock-up reproducing key materials for LWRs. The results are neutron spectra and dosimeter responses. Various nuclear data libraries are compared. The results show a satisfactory agreement between calculation and experiment.
File in questo prodotto:
File Dimensione Formato  
ADPFISS-LP1-093.pdf

accesso aperto

Licenza: Creative commons
Dimensione 9.92 MB
Formato Adobe PDF
9.92 MB Adobe PDF Visualizza/Apri

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7985
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
social impact