High Power Laser and Particle Beams, Volume. 35, Issue 11, 116004(2023)
Analysis of influence of canceling secondary neutron sources ontritium source terms in pressurized water reactors
Figures & Tables(5)
Table 1. Nuclear reaction of tritium production in PWR
View tableView in ArticleTable 1. Nuclear reaction of tritium production in PWR
region nuclear reactions fuel $ {\text{U/Pu + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{}}{\text{FP1 + FP2 + }}{}_{\text{1}}^{\text{3}}{\text{H}} $ antimony-beryllium (in secondary source) ${}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{2}}^{\text{6}}{\text{He}}$ ⇨${}_{\text{2}}^{\text{6}}{\text{He}}\xrightarrow{{\text{β }}}{}_{\text{3}}^{\text{6}}{\text{Li}}$ ⇨${}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ${}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,T)}}}}{}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ⇨${}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n,n}}\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ boric acid (in the primary coolant and control rod) ${}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},2\alpha )}}{\text{2}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ${}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n,n}}\alpha )}}{}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{2}}^{\text{4}}{\text{He}}$ ⇨${}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ${}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{2}}^{\text{4}}{\text{He}}$ ⇨${}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n,n}}\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ${}_{\text{5}}^{{\text{11}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,T)}}}}{}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ⇨${}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{2}}^{\text{6}}{\text{He}}$ ${}_{\text{2}}^{\text{6}}{\text{He}}\xrightarrow{{\text{β }}}{}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{{{ - 1}}}^{\text{0}}{\text{e}}$ ⇨${}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ${}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,T)}}}}{}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ⇨${}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n,n}}\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ lithium hydroxide (in the primary coolant) ${}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ ${}_{\text{3}}^{\text{7}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n,n}}\alpha )}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}}$ deuterium (in the primary coolant) ${}_{\text{1}}^{\text{2}}{\text{H + }}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{({\text{n}},\gamma )}}{}_{\text{1}}^{\text{3}}{\text{H}}$
Table 2. Information of the reactors
View tableView in ArticleTable 2. Information of the reactors
reactor thermal capacity/MW number of assemblies active height/cm fuel configuration secondary neutron source (SNS) period of discharge group 1 A 3411 193 12 17×17 N 2000—2019 B 3411 193 12 17×17 N 2001—2019 C 3438 193 12 17×17 N 2001—2011 D 3438 193 12 17×17 N 2001—2011 group 2 E 3459 193 12 17×17 Y 2001—2019 F 3468 193 12 17×17 Y 2000—2019 G 3455 193 12 17×17 Y 2001—2019 H 3455 193 12 17×17 Y 2001—2019
Table 3. Statistical results of tritium emissions
View tableView in ArticleTable 3. Statistical results of tritium emissions
unit average tritium emission/(TBq·a−1) maximum tritium emission/(TBq·a−1) gaseous liquid total gaseous liquid total group 1 A 3.8 18.2 22.0 4.8 32.4 37.1 B 3.0 22.2 25.2 4.8 33.5 38.3 C 2.1 21.5 23.6 2.6 33.8 36.4 D 2.2 22.6 24.8 2.5 34.3 36.8 All 2.8±0.7 21.1±1.7 23.9±1.2 4.8±1.1 34.3±1.6 38.3±1.2 group 2 E 3.9 26.9 30.8 5.4 36.5 44.0 F 3.9 29.3 33.2 4.6 37.7 41.9 G 2.6 28.8 31.4 3.6 39.1 41.9 H 2.5 27.6 30.1 3.2 37.1 38.8 All 3.2±0.7 28.1±0.9 31.4±1.1 5.4±0.8 39.1±1.0 44.0±1.8
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Qi Wang. Analysis of influence of canceling secondary neutron sources ontritium source terms in pressurized water reactors[J]. High Power Laser and Particle Beams, 2023, 35(11): 116004
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Received: Apr. 21, 2023
Accepted: Oct. 24, 2023
Published Online: Dec. 26, 2023
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