Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Ahmet Çifci; Adem Acır

Makale detayları

Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Yazarlar:

Ahmet Çifci | Adem Acır

Yayıncı:

Gazi University

Ana Başlıklar:

Mühendislik

Dergi:

Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji Vol.11 Issue 4, pp.903-912

Belge Tipi:

Makale

Yayın Tarihi:

12/2023

Belge Dili:

İngilizce

Document ID (Org No.):

2001306940

pISSN:

2147-9526

Anahtar kelimeler:

Özet:

 In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor HTGR which has 60 MWth full core geometry by using continuous-energy multi-purpose three-dimensional Monte Carlo particle transport Serpent code with ENDF B-VII data libraries. Nuclear fuel have been selected as 50  ThO250 RG-PuO2. Firstly, effective reactivity for three different qualities of graphite for operation period have been determined. The effective reactivity showed better performance with increasing densities of graphite. Secondly, it has been also examined to ZrC and SiC cladding materials effect on the effective reactivity. It is observed that SiC has a positive effect on reactivity compared to ZrC. As a results, the full core life low-power thorium-burner HTGR have been calculated as up to 4500 days depending on the graphite material whereas, the corresponding burnups came out to be  189 GWdton, for end of life.

 In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor HTGR which has 60 MWth full core geometry by using continuous-energy multi-purpose three-dimensional Monte Carlo particle transport Serpent code with ENDF B-VII data libraries. Nuclear fuel have been selected as 50  ThO250 RG-PuO2. Firstly, effective reactivity for three different qualities of graphite for operation period have been determined. The effective reactivity showed better performance with increasing densities of graphite. Secondly, it has been also examined to ZrC and SiC cladding materials effect on the effective reactivity. It is observed that SiC has a positive effect on reactivity compared to ZrC. As a results, the full core life low-power thorium-burner HTGR have been calculated as up to 4500 days depending on the graphite material whereas, the corresponding burnups came out to be  189 GWdton, for end of life.

 In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor HTGR which has 60 MWth full core geometry by using continuous-energy multi-purpose three-dimensional Monte Carlo particle transport Serpent code with ENDF B-VII data libraries. Nuclear fuel have been selected as 50  ThO250 RG-PuO2. Firstly, effective reactivity for three different qualities of graphite for operation period have been determined. The effective reactivity showed better performance with increasing densities of graphite. Secondly, it has been also examined to ZrC and SiC cladding materials effect on the effective reactivity. It is observed that SiC has a positive effect on reactivity compared to ZrC. As a results, the full core life low-power thorium-burner HTGR have been calculated as up to 4500 days depending on the graphite material whereas, the corresponding burnups came out to be  189 GWdton, for end of life.

 In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor HTGR which has 60 MWth full core geometry by using continuous-energy multi-purpose three-dimensional Monte Carlo particle transport Serpent code with ENDF B-VII data libraries. Nuclear fuel have been selected as 50  ThO250 RG-PuO2. Firstly, effective reactivity for three different qualities of graphite for operation period have been determined. The effective reactivity showed better performance with increasing densities of graphite. Secondly, it has been also examined to ZrC and SiC cladding materials effect on the effective reactivity. It is observed that SiC has a positive effect on reactivity compared to ZrC. As a results, the full core life low-power thorium-burner HTGR have been calculated as up to 4500 days depending on the graphite material whereas, the corresponding burnups came out to be  189 GWdton, for end of life.

Makale detayları

Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Yazarlar:

Ahmet Çifci | Adem Acır

Yayıncı:

Gazi University

Ana Başlıklar:

Mühendislik

Dergi:

Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji Vol.11 Issue 4, pp.903-912

Belge Tipi:

Makale

Yayın Tarihi:

12/2023

Belge Dili:

İngilizce

Document ID (Org No.):

2001306940

pISSN:

2147-9526

Monte Carlo

HTGR

Reactivity

Burnup analysis

Graphite

Sayı

Makale detayları

Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Yazarlar: Ahmet Çifci | Adem Acır

Yayıncı: Gazi University

Ana Başlıklar: Mühendislik

Dergi: Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji Vol.11 Issue 4, pp.903-912

Belge Tipi: Makale

Yayın Tarihi: 12/2023

Belge Dili: İngilizce

Document ID (Org No.): 2001306940

pISSN: 2147-9526

Monte Carlo

HTGR

Reactivity

Burnup analysis

Graphite

Sayı

Yazarlar:

Ahmet Çifci | Adem Acır

Yayıncı:

Gazi University

Ana Başlıklar:

Mühendislik

Dergi:

Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji Vol.11 Issue 4, pp.903-912

Belge Tipi:

Makale

Yayın Tarihi:

12/2023

Belge Dili:

İngilizce

Document ID (Org No.):

2001306940

pISSN:

2147-9526