High Power Laser and Particle Beams, Volume. 34, Issue 2, 026009(2022)
Study of annual tritium discharge in pressurized water reactor based on historical data
Figures & Tables(8)
Fig. 2. Comparison between calculated and measured values of tritium production by neutron activation
Fig. 3. Comparison between calculated and measured values of tritium production (1% released from fuel)
Fig. 4. Comparison between calculated and measured values of tritium production of Daya Bay Nuclear Power Plant
Fig. 5. Schematic diagram of SNS in double-layer stainless steel cladding
Table 1. Nuclear reaction of tritium production in PWR
View tableView in ArticleTable 1. Nuclear reaction of tritium production in PWR
region nuclear reaction fuel $ {\text{U/Pu}} + {}_0^1{\text{n}}\xrightarrow{{}}{\text{FP1 + FP2}} + {}_1^3{\text{H}} $ boric acid（primary coolant） $ {}_{\text{5}}^{{\text{10}}}{\text{B + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{({\text{n,2α}} )}}}{\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,nα )}}}}{}_{\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,α )}}}}{}_{\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,α )}}}}{}_{\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,nα )}}}}{}_{\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,α )}}}}{}_{\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,α )}}}}{}_{\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,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $ lithium hydroxide（primary coolant） $ {}_{\text{3}}^{\text{6}}{\text{Li + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\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,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $ deuterium（primary coolant） $ {}_{\text{1}}^{\text{2}}{\text{H + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,γ )}}}}{}_{\text{1}}^{\text{3}}{\text{H}} $ antimony-beryllium in SNS $ {}_{\text{4}}^{\text{9}}{\text{Be + }}{}_{\text{0}}^{\text{1}}{\text{n}}\xrightarrow{{{\text{(n,α )}}}}{}_{\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,α )}}}}{}_{\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,nα )}}}}{}_{\text{2}}^{\text{4}}{\text{He + }}{}_{\text{0}}^{\text{1}}{\text{n + }}{}_{\text{1}}^{\text{3}}{\text{H}} $
Table 2. Relative contribution of expected tritium production in different reactor
View tableView in ArticleTable 2. Relative contribution of expected tritium production in different reactor
origin relative contribution/% EPR AP1000 VVER fuel 0 31 22 boric acid and lithium hydroxide 83 69 77 SNS 17 0 − total 100 100 100
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Pengtao Fu, Mingliang Dai, Zhaowen Zhu, Xinhua Liu, Lan Fang, Chunyan Xu. Study of annual tritium discharge in pressurized water reactor based on historical data[J]. High Power Laser and Particle Beams, 2022, 34(2): 026009
Paper Information
Category: Monte Carlo Methods and Applications
Received: Sep. 6, 2021
Accepted: Jan. 13, 2022
Published Online: Jan. 26, 2022
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